REP ORTHead Office31, avenue de la Division Leclerc
92260 Fontenay-aux-Roses
RCS Nanterre B 440 546 018
Telephone(+33) (0)1 58 35 88 88
Postal address
BP 17
92262 Fontenay-aux-Roses Cedex
Websitewww.irsn.fr

Pôle radioprotection environnement - déchets - crise (PRP)
Service d’étude et de surveillancede la radioactivité
dans l’environnement (SESURE)
31 rue de l’Ecluse
BP 40035
78116 Le Vésinet Cedex
Telephone(+33) (0)1 30 15 52 42

Report on the Radiological State of the Environment in France in 2010-2011

Enhancing nuclear safety

Report on
the Radiological Stateof the Environment
in France in 2010-2011

Report on
the Radiological Stateof the Environment
in France in 2010-2011

TABLE OF CONTENTS
How to Read this Report ..................................................................................................................................................................................... p. 3
Foreword..................................................................................................................................................................................................................... p. 5
Overview of IRSN’s Missions............................................................................................................................................................................... p. 6

		

2

I
I.1
I.2
I.3
I.4
I.5
I.6
I.7

Radiological Monitoring of the Environment...................................................................................................................................................p. 8
Natural and artificial radiation in France ......................................................................................................................................................p. 10
Why monitor environmental radioactivity? ................................................................................................................................................p. 15
What are the objectives of radiological monitoring of the environment? ........................................................................................p. 16
How is radioactivity monitored? ...................................................................................................................................................................p. 17
Methodological aspects of selecting monitoring stations .....................................................................................................................p. 18
Analysis plans...........................................................................................................................................................................................................p. 22
From preparation to physical measurement of samples ..........................................................................................................................p. 25

II
II.1
II.2

The National Environmental Radioactivity Measurement Network and Stakeholders Involved in Monitoring Radioactivity in France . p. 28
The National Environmental Radioactivity Measurement Network (RNM)........................................................................................p. 30
Who monitors radioactivity in France? ..........................................................................................................................................................p. 35

III
III.1
III.2
III.3
III.4

Events and Specific Assessments................................................................................................................................................................p. 42
Accidental tritium contamination at Saint-Maur-des-Fossés and Bondoufle, near Paris .............................................................p. 53
IRSN assessments on the Orflam-Plast site in Pargny-sur-Saulx in northeastern France ..............................................................p. 55
Radioactive releases associated with natural events ................................................................................................................................p. 57

IV
IV.1
IV.2
IV.3
IV.4
IV.5

Monitoring in Metropolitan France and the Overseas Territories ............................................................................................p. 60
Atmospheric compartment ...............................................................................................................................................................................p. 62
Continental environment ....................................................................................................................................................................................p. 70
Marine and coastal environment.......................................................................................................................................................................p. 75
Regional radiological reports ........................................................................................................................................................................... p. 100
Radiological monitoring in overseas France ............................................................................................................................................... p. 106

V
V.1
V.2
V.3
V.4
V.5
V.6

Monitoring of Nuclear Fuel Cycle Facilities ....................................................................................................................................... p. 110
Environmental monitoring near nuclear sites .......................................................................................................................................... p. 112
Environmental monitoring around former mining sites ........................................................................................................................ p. 113
Environmental monitoring of industries in the front end of the nuclear fuel cycle....................................................................... p. 121
Environmental monitoring of nuclear power plants .............................................................................................................................. p. 139
Monitoring of industries in the back end of the nuclear fuel cycle .................................................................................................... p. 184
Monitoring of waste disposal facilities ........................................................................................................................................................ p. 200

VI
VI.1
VI.2

Monitoring of Research Centers and Nuclear Naval Bases ....................................................................................................... p. 210
CEA nuclear research centers and the Institut Laue-Langevin (ILL) international research center........................................... p. 212
Nuclear naval bases............................................................................................................................................................................................. p. 250

VII
VII.1
VII.2

Monitoring of Facilities that Use Sources of Natural or Artificial Radioactivity............................................................. p. 256
Rhodia Electronics & Catalysis plant in La Rochelle................................................................................................................................. p. 259
Industrial ionization facilities............................................................................................................................................................................ p. 261

VIII
VIII.1
VIII.2
VIII.3
VIII.4
VIII.5
VIII.6

French Population Exposure to Ionizing Radiation ....................................................................................................................... p. 264
Average exposure of the population in France .......................................................................................................................................... p. 266
Assessing the biological effects of radioactivity on living organisms.................................................................................................. p. 268
Doses received by the population as a result of nuclear activities...................................................................................................... p. 268
Assessment of the radiological quality of drinking water in France.................................................................................................... p. 274
Dosimetric evaluation for French Polynesia................................................................................................................................................ p. 275
Assessment of the dosimetric impact of the Fukushima accident on the French population.................................................... p. 276

IX
IX.1
IX.2

Radioactivity Monitoring Information Sources and Data Distribution Networks......................................................... p. 280
Internet sites and public information media............................................................................................................................................... p. 282
Information released under the terms of treaties or international agreements.............................................................................. p. 289

X
X.1
X.2
X.3

Understanding Radioactivity .................................................................................................................................................................... p. 292
The atom and radiation .................................................................................................................................................................................... p. 294
Measuring radioactivity .................................................................................................................................................................................... p. 295
Biological effects of radioactivity and means of exposure .................................................................................................................... p. 298

XI
XI.1
XI.2
XI.3
XI.4

Appendices.......................................................................................................................................................................................................... p. 300
Presentation and analysis of results ............................................................................................................................................................. p. 302
Glossary................................................................................................................................................................................................................... p. 303
References............................................................................................................................................................................................................... p. 307
Credits and acknowledgements...................................................................................................................................................................... p. 308

Monitoring the impact of the Fukushima accident on France (metropolitan France and French overseas departments, regions and communities) ..................p. 44

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

HOW TO READ THIS REPORTOne of the goals of this report on the radiological state of the environment is to facilitate access to information. It has thus been
designed to allow quick, simple access to all information regarding
the stakeholders involved in monitoring radioactivity in France, andto the results of studies. It also includes an educational section that
explains radioactivity, how it is measured, its biological effects andother topics.
In addition, different approaches to reading this report have been
designed for the non-specialist public, well-informed readers andexperts. They are presented below.

Access by type of reader

Non-specialist public
Chapter X

Understanding Radioactivity

Chapter I

Radiological Monitoring of the Environment

Chapter IV

Monitoring in Metropolitan France and the Overseas Territories

Chapter VIII

French Population Exposure to Ionizing Radiation

Chapter IX

Radioactivity Monitoring Information Sources and Data Distribution Networks

Well-informed public
Chapter I

Radiological Monitoring of the Environment

Chapter II

The National Environmental Radioactivity Measurement Network and Stakeholders Involved in Monitoring Radioactivity in France

Chapter IV

Monitoring in Metropolitan France and the Overseas Territories

Chapter V

Monitoring of Nuclear Fuel Cycle Facilities

Chapter VI

Monitoring of Research Centers and Nuclear Naval Bases

Chapter VII

Monitoring of Facilities that Use Sources of Natural or Artificial Radioactivity

Chapter VIII

French Population Exposure to Ionizing Radiation

Experts and professionals• Access to all chapters, with a particular focus on those that include monitoring results (Chapters III-VII) and theevaluation of doses received by the population (Chapter VIII).
• To provide direct access to the results, a map showing a summary of those results can be found on the next page.

IRSN – Report on the Radiological State of the Environment in France in 2010-20113

Access by site: summary map
Gravelines (p170)

This summary map is intended forwell-informed readers and experts whoseek direct access to information andresults regarding the main nuclear sites
in France (Chapters V, VI and VII).

Maubeuge (p199)
Centre Manche (p184)
Penly (p170)
La Hague (p184)
Paluel (p170)
Flamanville (p170) Cherbourg (p253)

Chooz (p149)
Cattenom (p149)

Brest (p250)
Ile-Longue (p250)

Fontenay-aux-Roses (p222)
Saclay (p236)
Bruyères-le-Châtel (p218)
Soulaines (p201)
Morvilliers (p201)
Nogent-sur-Seine (p177)
Brennilis (p181)
Fessenheim (p149)
Saint-Laurent-des-Eaux(p140)
Sablé-sur-Sarthe (p262)
Dampierre-en-Burly (p140)
Chinon (p140)

Uranium conversion
Uranium enrichment
Production of fuel assemblies
Spent fuel reprocessing and recycling
Surface disposal of radioactive wastes
Nuclear power plants
Nuclear maintenance workshop
Research centers
Nuclear naval bases
Ore processing
Ionization centers

Belleville-sur-Loire (p140) Valduc (p242)

Pouzauges (p263)
Civaux (p140)
La Rochelle (p259)

Le Blayais (p156)

Golfech (p156)

Creys-Malville (p162)
Bugey (p162)
Dagneux (p262)
Saint-Alban (p162)
Grenoble (p246)
Romans-sur-Isère (p133)
Cruas-Meysse (p162)
Pierrelatte (p125)
Tricastin (p162)
Tricastin (p125)
Marcoule (p226)
Marcoule (p226)
Cadarache (p213)
Marseille (p263)
Malvési (p122)

Toulon (p254)

Map of French mining areas: p. 113

General environmental monitoring in France - access by theme

Atmospheric compartment (air, aerosols, rainwater) ...................................................................................................p. 62

Continental environment (milk, cereals, mushrooms, surface water) .....................................................................p. 70

Marine and coastal environment (water, sediments, algae, aquatic fauna)........................................................ p. 75

Regional radiological reports.............................................................................................................................................. p. 100

Radiological monitoring of overseas France.............................................................................................................. p. 106

Note: The results of marine and coastal environmental monitoring (sea water, sediments and aquatic flora and fauna) near nuclear facilities arepresented in Chapter IV.3 (Marine and coastal environment) so that all data available may be used. Similarly, in the atmospheric compartment,
the results of active and passive environmental dosimetry measurements are discussed in Chapter IV.

4

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

FOREWORD
The French Institute for Radiological Protection and Nuclear Safety (IRSN)
has published an annual Report on the Radiological State of the Environment
in France since 2004. Radiological monitoring of the environment in France
is one of IRSN's ongoing missions in connection with public policies addressing nuclear safety and radiation protection, and helps to ensure the highest
possible level of protection to the population. The objective of this mission
is to:• verify that nuclear activities are conducted in compliance with regulations
governing discharge;• e nsure that all components of the environment remain in a satisfactory
radiological state that does not entail excessive exposure of humans andecosystems;• detect as soon as possible any abnormal elevation in radioactivity that may
result from a radiological or nuclear accident in France or abroad.
As announced in the previous report, a new version of the report containing
all the data from the National Environmental Radioactivity Measurement
Network (RNM) is being issued this year. Since 2003, IRSN’s mission has been
to develop and manage the RNM, which was established under Articles R.
1333-11 and R. 1333-11-1 of the French Public Health Code.
The main goal of the network, which is described in Chapter 2 of this report,
is to gather and make available to the public the information held by publicauthorities on the radiological state of the various components of the environment. In accordance with regulations, IRSN must now prepare a summary
report on the radiological state of the environment based on RNM data, andsupplemented by estimates of the radiological impacts of the main nuclear
activities.
Publication of this report thus constitutes a major event in France’s nuclear
energy transparency policy as, for the first time, it incorporates all the datasubmitted to the RNM by the nuclear stakeholders that are part of the network. With more than 300,000 measurements considered, the report provides the most comprehensive view possible of all the environmental
radioactivity measurements taken by the various stakeholders.
In order to incorporate results relating to the Fukushima accident, this report
includes the data obtained between January 1, 2010 and June 30, 2011 acrossthe entire country. The monitoring results from French Polynesia are presented in a special report published annually by IRSN, which can be consulted
online.
The results are presented thematically:• by type of facility that discharges radioactive substances (for example,
nuclear power plants, spent fuel reprocessing facilities, or nuclear research
centers) for monitoring results from these sites;•b y environmental compartment (atmospheric, continental, marine andcoastal) for general monitoring results from across the country.

Differences may appear in monitoring plans across sites of a similar naturefor geographic or historical reasons or based on a specific study. To find results
or obtain access to those that are not included in this report, please consult
the RNM website (http://www.mesure-radioactivite.fr) or IRSN’s
environmental Internet portal (http://environnement.irsn.fr).
The first half of 2011 was marked by the accident at the Fukushima Daiichi
nuclear power plant, which occurred in the wake of the March 11, 2011
earthquake and tsunami. This report includes a summary of IRSN’s assessment of the impact of that accident in France (both in metropolitan andoverseas France), published in early 2012. More than 5,700 measurement
results obtained by IRSN and 3,000 results transmitted by operators and the
Association for Radioactivity Monitoring in Western France (ACRO) were
included in this scientific analysis. More generally, incorporating these results
involved a particular approach to managing data analysis and presentation,in that a distinction was made between ‘usual’ values measured in theenvironment and those obtained during the period after the accident.
Traces of this event were detected over several weeks. In addition, the results
shown in this report reveal the presence of artificial radionuclides in the environment close to known discharge sources (nuclear industry and hospital
activities) and outside the areas of influence, due to fallout over the entire
country (including from atmospheric nuclear weapons tests conducted from1945-1980 and the 1986 Chernobyl accident) or former, insufficiently controlled, industrial activities (polluted sites). In general, these traces are evident particularly in soils, continental waters, and the sea (sediment and floraand fauna). From a qualitative perspective, radiation levels measured in 2010
and 2011 remain low and are within the range of values typically seen inrecent years.
As it does every year, IRSN has continued to work on improving the content
of the report and making it easier to read. This latest report incorporates anumber of changes reflecting the integration of data provided by the RNM,
and modifications made by IRSN to its national radiological monitoring mission as of 2008 (the introduction of regional radiological reports andredeployment of coastal and food monitoring).
Other novelties in this report include the participation of RNM stakeholders
and the Belgian Federal Agency for Nuclear Control (FANC) in special Focus
sections that highlight a specific topic or significant event related toenvironmental radiological monitoring.
I hope you find this report on the radiological state of the environment in2010-2011 interesting and useful and that it meets your expectations.

Jacques Repussard
Director General

Each chapter of the report may be read independently of the others. In orderto provide the reader with a broader, more representative perspective of environmental radioactivity measurements, IRSN has chosen to express results
as a single estimator that takes into account all values measured at a given
point over the period in question, including values below decision thresholds.
This method avoids over-repetition of individual results in tables or graphs,
while remaining scientifically rigorous.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

5

OVERVIEW OF IRSN'S MISSIONS
IRSN, the French Institute for Radiological Protection and Nuclear
Safety was set up under Act No. 2001-398 of May 9, 2001. As the
public service expert on risks, IRSN contributes to public policy issues
relating to nuclear safety and human and environmental protectionin the area of ionizing radiation. It interacts with all parties concernedby these policies.
Nuclear risk prevention in France is based on four complementary
pillars:• Operators are responsible for the safety of their nuclear facilities.
They must demonstrate the appropriateness of the technical andorganizational resources implemented to that end (for example,
safety analysis reports, and discharge impact studies).
• Public authorities determine nuclear and radiation protection policies. They are responsible for the organization and implementationof control.
• IRSN, the public service expert in nuclear risks, assesses operator
reports and documents on behalf of the relevant authorities. It conducts on-going analysis of feedback on facility operation and humanand environmental exposure to radiation. IRSN’s expertise is basedon its research, designed in an international context, which ensuresthat it relies on the most effective investigative tools.
• Local Information Commissions (CLI) bring together the stakeholders concerned with a given nuclear facility. They provide accessto information and exercise vigilance on issues relating to safety andhealth and environmental protection.

Designer/builder
Operator

Researchon risks

Parliament

IRSN, Public
expertPublicauthorities

Stakeholders(CLI)
Civil society
Figure 1 - The four pillars of nuclear risk prevention.

6

IRSN is a French public authority with industrial and commercial
activities placed under the joint authority of:• the Ministry of Ecology, Sustainable Development and Energy;• the Ministry of Economic Regeneration;• the Ministry of Higher Education and Research;• the Ministry of Defense;• the Ministry of Social Affairs and Health.
Of its total expenditure (€282 million in 2011), €210.8 million is provided by a grant from the Ministry of Ecology, under the Budget Act’s“research and higher education” mission, the “energy, development andsustainable development” research program and the “research in thefield of risk” action. This grant is supplemented by national, European
and international funding assigned to specific research or assessment
programs. IRSN has more than 1,700 employees, including over 1,000
experts and researchers.
Its resources are allocated as follows:• 40.2% for research. The largest programs, which require nuclear
research reactors or considerable resources (for example, fuel behavior and accident simulations), are pooled at the international level;•5 0.2 % for technical support to public authorities and government
departments and for public service missions;•9 .6% for assessments and studies carried out under contract.
IRSN’s activities cover the following fields:•n uclear safety: reactors, fuel cycle, waste, medical applications;• t ransportation safety for radioactive and fissile materials;• protection of workers exposed to ionizing radiation: IRSN manages individual exposure data on approximately 350,000 workers;•p rotection of the population and the environment against risks
associated with ionizing radiation;•p rotection and control of nuclear materials;• protection of nuclear facilities and radioactive and fissile material
shipments against malicious acts.
IRSN promotes nuclear transparency:• informing the public is one of the Institute's missions. Its Internet
portal (www.irsn.fr) offers a wide range of information targeting different audiences.
• IRSN has signed a framework agreement with the ANCCLI, thefederation of local information commissions, to make its expertise accessible to stakeholders and thus contribute to an understanding of technical, often complex, matters;• At the request of the public authorities, IRSN leads joint expert
groups on topics that might become the subject of social debate.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

[Head office]

IRSN locations
Activities
Environment
Nuclear defense
expertise
Emergency response

Major accident
prevention
Human radiation
protection

Reactor safety
Safety of plants, laboratories,
transport and waste

Figure 2 - Location of IRSN sites.

IRSN, an international stakeholder
IRSN is a Technical Safety Organization (TSO), implementing scientific partnerships and overseeing scientific cooperation andnuclear safety, security and radiation protection services in 39
countries under bilateral or multinational consortium agreements,
under the auspices of the EU, the NEA or TSO networks (ETSON
in Europe), or in cooperation with the IAEA.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

7

RADIOLOGICAL MONITORING OF THE ENVIRONMENT

8IRSN – Report on the Radiological State of the Environment in France in 2010-2011

I
RADIOLOGICALMONITORING
OF THE ENVIRONMENT
I.1 Natural and artificial radiation in France
I.2 Why monitor environmental radioactivity?
I.3 What are the objectives of radiological monitoring of theenvironment?
I.4 How is radioactivity monitored?
I.5 Methodological aspects of selecting monitoring stations
I.6 Analysis plans© Leprieur/IRSN

I.7 From preparation to physical measurement of samples

RADIOLOGICAL MONITORING OF THE ENVIRONMENTRadioactivity in the environment today is due to radionuclides that may be natural, inother words, found on Earth since its very beginnings, or artificial, i.e. introducedby humans as from the mid-20th century. Some radionuclides, such as tritium andcarbon-14, are both natural and anthropogenic.

Natural radiation
Radioactivity is part of the universe. It occurs
naturally everywhere, without human action.
Radioactive elements can be found in theatmosphere and the Earth’s crust. From thevery beginnings of the Earth, some five billion
years ago, matter has been composed of both
radioactive and stable elements. Since then,radioactivity has declined steadily as many
radioactive atoms have transformed into
stable elements.

Sources of natural radiation• Cosmic rays have two components. The
first is the product of high-energy ions fromthe galaxies. The second comes from thesun - solar wind consists primarily of protons. The Earth’s magnetic field forms themagnetosphere which, with the atmosphere, acts as a protective screen that prevents all but 0.05% of cosmic radiationfrom reaching sea level. Conversely, theintensity of cosmic radiation increases
with altitude, doubling every 1,500 meters(Figure I.1).
• Radioactivity in the soil (or terrestrial radiation) is emitted by many radioactive elements found in the Earth’s crust, such asuranium and thorium. It varies with thetype of soil and is five to twenty times
higher in granite massifs, for example, thanin sedimentary soils.
• R adioactivity in water only partiallyreflects the geological character of the areas
crossed. Everything depends on the chemical nature of the water and the degree of• Radioactivity in the air mainly comesfrom gaseous radon-222, which, in turn,comes from uranium-238. This component
is the most significant in terms of natural
exposure and varies considerably. It depends
on the uranium-238 concentrations in thesoil, soil porosity, construction materials andhousing ventilation, which concentrates the
diffusion of the radon gas by confining it.
This gas, together with its derivative products, lodges in the airways.

• Radioactivity in the human body, which
represents some 120 Bq/kg (8,400 Bq fora person weighing 70 kg), comes fromingesting foods that contain radioactive
elements.1 Once ingested, these radionuclides lodge in tissues and bones. On average, the human organism contains
4,500 Bq of potassium-40 and 3,700 Bq ofcarbon-14.
1 – Source: La radioactivité naturelle en 10 épisodes,
Livret de la SFRP, 1998.

Hourlydose rate
15 km

10 microsieverts(µSv/h)10 km

5 microsieverts(µSv/h)6,7 kmHimalaya

1 microsievert(µSv/h)5 km
Lhassa (Tibet) 3.7 km
Mexico City 2.25 km
Denver 1.6 km
Sea level

0.1 microsievert(µSv/h)0.03 microsievert(µSv/h)Figure I.1 - The dose due to cosmic rays increases with altitude

10

IRSN – Report on the Radiological State of the Environment in France 2010-2011© Chromatiques/IRSN - Source: IRSN

I.1 Natural andartificial
radiation in
Francesolubility of the radionuclides. Mineral water
is more radioactive than surface water andsome ground water is rich in dissolved
radon gas.

I.1
Naturally occurring radionuclides
U238

Of the 340 types of atoms that exist innature, 70 have unstable radioactive nuclei(radionuclides). Only 20 or so of these “primordial” radionuclides still exist today, as theshort-lived ones – that is, in relation to theage of the Earth – have disappeared. Thesenaturally occurring radionuclides, which
account for most environmental radioactivity, are found in the air, soil, water and livingorganisms, including humans.
They are either radionuclides with a very long
half-life that have been present on Earthsince it was formed (potassium-40, uranium238, uranium-235 and thorium-232), or
those created continuously in the upper
atmosphere as a result of cosmic radiation,referred to as cosmogenic radionuclides (tritium, carbon-14, krypton-85, beryllium-7 andsodium-22). While most of these radionuclides disintegrate directly into stable, nonradioactive elements, three of them (238U,
235U and 232Th) produce several radioactive
decay products, which form families or decay
chains, each containing between 10 and 15
different radionuclides (Figure I.2).

a4.47 x 109 yrs
1.17 min24.10 d

Th

234

Pa

234m

ß

ß

2.44 x 105 yrs

U

234

a

Th 7.54 x 104 yrs

230a

Ra 1,600 yrs

226a

Rn 3.82 d

222

a

Po

218

a

3.05 min26.8 minPb

214

19.9 min

Bi

214

ß

164.3 µs

Po

214

ß
22.3 yrs

5.01d

a

Pb

210

Bi

138.38 d

Po

210

210

ß

ß

a

Pb

206

Figure I.2 - Uranium-238 progeny

Special case of radon
Radon (Rn) is a radioactive gas that is foundeverywhere on the Earth’s surface. It has threenatural isotopes (219Rn, 220Rn, 222Rn) that are
decay products of radioelements in the soil
(235U, 232Th and 238U).
0–50

Radon-222 in its gaseous form, a decay product of radium (226Ra), which is, in turn, a decay
product of uranium-238, is the most common isotope in the atmosphere because its
half-life of 3.82 days is long enough to allow
it to migrate, from the rock where it wasformed to the soil and into the atmosphere(Figure I.3). As it decays, radon emits alphaparticles and generates solid decay productsthat are also radioactive (including polonium,
bismuth and lead).
It migrates from the soil to the open air
through various physical processes, and may
accumulate in the more confined atmosphereof buildings. For the French population, inhaling radon and its decay products is the leading cause of exposure to natural sources ofionizing radiation. The increased risk of lungcancer explains heightened vigilance withregard to radon in homes and undergroundmines.

51–100
101–150> 150

Figure I.3 - A
 verage radon concentration in air in homes by department (Bq/m3)

IRSN – Report on the Radiological State of the Environment in France 2010-2011

11

RADIOLOGICAL MONITORING OF THE ENVIRONMENT
Technologically enhanced
naturally occurring radioactive
materials
Natural background radiation has always
existed and, on the whole, total human exposure has doubtless changed very little overthe centuries. However, lifestyle changes andthe introduction of new practices may havechanged that situation somewhat.
Certain circumstances may lead to relatively significant exposure to technologically enhanced, naturally occurring
radioactive materials:
1 – confinement of radon in housing: theuse of certain radon-emitting construction
materials, construction that is poorly insulated from uranium-bearing soil and overly
confined housing may result in significant
exposure;
2 - production processes in certain industrial activities, not related to the nuclear
power cycle, may change the physical-chemical equilibria of natural radioactivity contained in the materials used and concentrate
it in the generated waste. That is what ismeant by technologically enhanced naturalradioactivity. It represents a potentially
increased risk of radioactive release to theenvironment and consequently of human
exposure, even after industrial activity hasceased.
This unintentionally technologicallyenhanced, naturally occurring radioactive
material comes from ore extraction and geologic resources, as well as from the successive
phases of separation, purification, transformation, and use of by-products. It mainly concerns the following activities:• coal-fired power plants;• tin, aluminum, copper, titanium, niobium,
bismuth and thorium ore processing;• refractory ceramic production;• production or use of compounds containing
thorium;• zircon and baddeleyite production;• phosphate fertilizer production and phosphoric acid manufacturing;• titanium dioxide processing;• rare earth processing and production of pigments containing them;• ground water filtration for drinking water;• spas.

3– Extraction and processing of uranium
ore also generates technologically enhanced,
naturally occurring radioactive materials, but,unlike the industrial activities referred toabove, the ore is used for its radioactive
properties.

Artificial radiation
Sources of artificial radiation
Unlike naturally occurring radionuclides,‘artificial’ radionuclides are radioactive
elements that are no longer found innature but recreated artificially. Since theearly 20th century, human activity has generated
artificial environmental radioactivity.
Artificial radionuclides are produced using
particle accelerators or nuclear reactors.
Some radionuclides may be used as an X-ray
source or as sources for industrial and medical
applications of radiation (radiation therapy forexample).

Others are produced in nuclear reactors. Someof these radionuclides, which are highly radioactive and not currently used by humans, form
nuclear waste that must be placed under strict
surveillance in disposal facilities.
Currently, around ten artificial radionuclides
are measured regularly in the environment inFrance, including strontium-90, cesium-137,
iodine-131, plutonium isotopes (238Pu, 239Pu,
and 240Pu) and americium-241.
These radionuclides have the following main
sources (Figure I.4):• regulated and authorized discharge from
nuclear facilities or relating to nuclear medicine activities (radiological tests and medical
treatments);• fallout from atmospheric nuclear weapons
testing (1945 to 1980) and the 1986 Chernobyl accident;
Remaining fallout from the Chernobyl accident and atmospheric nuclear tests accountfor the artificial background radioactivity inFrance today.

Atmospheric nuclear weapons testing atfive main sites (1945 - 1980)
Chernobyl accident (1986)
Fall and disintegration, in the atmosphereof the US SNAP-9a satellite (1964)

Map of cesium-137
activities in the soil

Spent fuel reprocessing facilities
and research centers
Nuclear power plants
Figure I.4 - Main sources of artificial radiation in the environment in France

12

IRSN – Report on the Radiological State of the Environment in France 2010-2011

I.1

Discharges
into the air
Control

Facility that contains
or generates
radioactivity

Temporarystorage
Reprocessing

Reuse

Solid
waste

IntakeControlLiquiddischarges

Control© Chromatiques/IRSN - Source: IRSN

Effluents

Figure I.5 - Sources and types of effluent from nuclear facilities - a simplified view

Discharge from industrial and nuclear energy
research facilities, including nuclear power
plants, is regulated. Most nuclear fuel cycle
facilities use water drawn from rivers or theocean (Figure I.5). The use of this water ispartly responsible for effluent that is treated
so that most of it can be retained as solid
waste. The remaining effluent is then discharged into the water and air after testing
to ensure that it complies with the regulatory requirements laid down by the authorities (rate, discharged activity levels andradionuclides contained).
Nuclear facilities discharge many kinds ofradionuclides, depending on the type of facility and operating phase (for example, production, maintenance outage, or dismantling).
The activity levels discharged by these facilities in normal operating mode have alsochanged over time due to increased restrictions on discharge permit renewals issued by
the authorities, and as new waste treatment
processes are introduced.
Today, three radionuclides make up most of
the discharge from French nuclear fuel cycle
facilities:• krypton-85, a chemically inert noble gas
with a half-life of 10.7 years, discharged ingaseous form during nuclear fuel reprocessing (Areva NC facility in La Hague);• tritium;• carbon-14.

Last, discharge from nuclear medicine activities is characterized by radionuclides with avery short half-life (eight days for iodine-131
and six hours for metastable technetium-99).

freshwater ecosystems is not in equilibriumwith atmospheric CO2. The activity levels
there are lower, in the region of 200 Bq/kg ofcarbon.

The main artificial radionuclides
found in the environment inFrance (Table I.1)

With regard to tritium, apart from all anthropogenic sources, activity concentration values range from one to several Bq/L in fresh
water or kg wet in foodstuffs, and from 0.01
to 0.05 Bq/m3 in air.

Tritium and carbon-14
Also produced naturally in the atmospherethrough the interaction of cosmic radiationand matter and as a result of fallout from
nuclear testing, tritium (3H) and carbon-14(14C) are among the radionuclides most frequently discharged by the nuclear industry.
They are quite uniformly distributed acrossFrance. The heterogeneity of fallout from
nuclear testing is no doubt masked by theprevailing natural component, which is very
homogeneous. In the terrestrial environment,in areas unaffected by discharge from nuclear
facilities, the specific activity of 14C expressedin becquerels per kilogram of total carbon isin equilibrium with the environmental components and, specifically, with atmospheric
CO 2. In 2009, this specific activity wasapproximately 237 ± 6 Bq/kg of carbon,
close to the atmospheric activity prior toatmospheric nuclear tests (226 Bq/kg of carbon). In the aquatic environment, the 14C of

Near some nuclear facilities, however,exposed to prevailing winds or downstream
from the outfalls of nuclear facilities, 3H and
14C activity levels can be considerably higher.
While most nuclear facilities have a slight but
visible impact on their environment in termsof 14C, 3H activity levels only stand out clearly
from the background near certain French
nuclear sites such as Valduc, Marcoule, La
Hague, Saclay and Bruyères-le-Châtel. Last,
3H was discharged by certain industries thatuse it for its luminescent properties for watch
hands or for signage. For example, the upper
reaches of the Rhône are affected by 3H fromdischarge from the Swiss watchmaking
industry.

IRSN – Report on the Radiological State of the Environment in France 2010-2011

13

RADIOLOGICAL MONITORING OF THE ENVIRONMENT

Cesium-137
Cesium-137 results from nuclear testing andthe Chernobyl accident and is also found indischarge from certain nuclear facilities,
including nuclear power plants, spent fuelreprocessing facilities and research centers. It
is almost impossible, however, to detect what
proportion of the discharge from these facilities enters the terrestrial environment
because it is masked to a great extent by thepersistence of earlier fallout.
After reaching a maximum of 4,000 Bq/m2
in 1963, soil surface activity in terms of 137Cs
then fell slowly after the U.S. and the Soviet
Union ended atmospheric nuclear weapons
testing and as a result of radioactive decay
and dilution and migration processes. The
May 1986 Chernobyl accident resulted inadditional cesium-137 deposits, distributed
irregularly across the country.
Today, cesium-137 soil activity levels mayvary by nearly two orders of magnitudedepending on initial radioactive deposits.
Deposits in the western two-thirds of thecountry are homogeneous and below
5,000 Bq/m2, while in the eastern part of thecountry, deposits are very heterogeneous andup to 40,000 Bq/m2 (Figure I.6).
Cesium-137, still measured in the air in
France, is found at an average level of lessthan 1 µBq/m3; in rainwater the level ranges
from 0.01 to 0.1 mBq/L. In recent years, however, the activity of this radionuclide stopped
falling. A balance appears to have beenreached between the activity deposited on
the surface of the soil and the activity inresuspension from inventory present in thesoil and plants. Levels in foodstuffs range
from the detection limit to several hundred
Bq/kg wet for some mushrooms.

Strontium-90
Strontium-90 comes almost entirely from
nuclear testing fallout. Soil surface contamination with 90Sr thus increased gradually asfrom 1945, reaching a maximum of
2,500 Bq/m2 in 1963. The halt of nuclear
weapons testing then led to a slow reduction
as a result of radioactive decay, which continues today. Strontium-90 is still detectable insoil, milk and plant samples. In general, levels
found in foodstuffs are around 0.1 Bq/kg wet.

14

137Cs
Bq/m2

40,00035,00030,00025,00020,00015,00010,0006,000
3,000

Figure I.6 - Surface activity levels of 137Cs potentially present in French soils in 2007

Transuranium elements(plutonium and americium)
Plutonium isotopes (238Pu, 239Pu, 240Pu and
241Pu) are almost exclusively due to fallout
from atmospheric nuclear weapons testing
and, in the case of 238Pu, from the disintegration of the US SNAP-9A satellite in 1964,
which used a 238Pu-fueled generator. In foodstuffs, the activity levels of 239Pu can reachseveral mBq/kg wet, but often remain below
the detection limit.
Liquid effluent and plutonium discharged into
the atmosphere in the past by certain facilities, such as Marcoule and La Hague, haveproduced concentrations of 238Pu, 239Pu and
240Pu in their immediate environment, relative to the background of earlier fallout.
Americium-241 does not come from fallout,
but from 241Pu decay. Thus, its activity
increases regularly and will reach its maximum around 2036, when there will no longer
be enough 241Pu to allow the production of
241Am to compensate for its slow radioactive
decay (half-life of 433 years).

IRSN – Report on the Radiological State of the Environment in France 2010-2011

Other artificial radionuclides
Other artificial radionuclides are measured
on a more ad hoc basis in continental aquaticand marine environments:• i n areas impacted by discharge from
nuclear facilities, manganese-54 (54Mn),cobalt-58 and -60 (58Co and 60Co), silver-110(metastable) (110mmAg), iodine-129 (129I) and,very sporadically, ruthenium-106 (106Ru) andcesium-134 (134Cs);• in areas impacted by discharge from hospitals, iodine-131 (131I) in suspended matter orin aquatic plants.
These radionuclides are very rarely detectedin the terrestrial environment and, when they
are, only at levels close to the detection
limits.
Last, IRSN has begun to monitor the activity
concentration of the gaseous radionuclide
krypton-85 (85Kr) in the air close to La Hague.
An initial assessment was conducted in 2010.

I.2
Table I.1 - Main artificial radionuclides in the environment in France

Radionuclide

H

Radioactive half-life

12.32 years

3

Main emissions

Main decay product

Beta

Main sources

3

He

Cosmic,nuclear tests,
discharge from the nuclear
and watchmaking industries

N

Cosmic,nuclear tests,
discharge from the nuclear
industryand research

NiDischarge from the nuclear
industry

Y

Nuclear tests,
discharge from the nuclear
industry

14C

5,730 years

Beta

14

Co

5.27 years

Beta, gamma

60

Sr28.78 years

Beta

90

I

8 daysBeta, gamma

131

Xe

Discharge from the nuclear
industryand nuclear
medicine departments

Ba

Nuclear tests,
Chernobyl accident,
discharge from the nuclear
industry

U

Nuclear tests,
discharge from the nuclear
industry

U

Nuclear tests,
discharge from the nuclear
industry

60

90

131

Cs

30.07 years

Beta, gamma

137

Pu

87.7 years

Alpha

234

Pu

24,100 and 6,560 years

Alpha

235+236

137

238

239+240

I.2 Why monitor
environmental
radioactivity?
Industrial and other human activities thatuse radioactive substances may lead toradionuclides being discharged to the environment, either during normal operation orunder emergency conditions.
The following cases are concerned:• discharge of radioactive substances into
the air or the aquatic and marine environments as a result of nuclear activities. This is carried out under controlled
conditions defined by the discharge permits
issued by the authorities. Regulations applicable to discharge have changed over theyears, with regular reductions in authorized
limits;• diffusion of radionuclides, in particular via
seepage water, in residues deposited on soil
surfaces or underground, under conditions
that do not guarantee total confinement ofradionuclides. This particular case arises inconnection with former sites that used naturally occurring radionuclides during thefirst half of the 20th century;• accidental release of radioactive substances into the air, in water, or on the
ground, directly or as a result of atmospheric dust fallout (for example, the Chernobyl accident);• persistence of long-lived radionuclides inthe environment (radioactive half-life
exceeding several years) from discharge into
the air or water, accumulating in the soil,
sediments or certain living organisms. In
France, as in the rest of Europe, radionuclides persist due to atmospheric fallout
from nuclear weapons testing and theChernobyl accident.

In addition, natural sources regularly contribute radionuclides to the environment; forexample, carbon-14 (14C), potassium-40 (40K),
uranium and thorium and their radioactive
decay products.
The presence of these radioactive substancesin the environment must be monitored andstudied to understand their potential impact
on human health, the environment, and economic resources, particularly water and agriculture. Radiological monitoring is therefore
carried out in all the environmental compartments: air, water, soils, biological compartments (fauna and flora) and the food chain.

IRSN – Report on the Radiological State of the Environment in France 2010-2011

15

RADIOLOGICAL MONITORING OF THE ENVIRONMENT

I.3 What are theobjectives ofradiologicalmonitoring of
the environment?

• knowledge of the radiological state of
the environment

Monitoring environmental radioactivity
involves many organizations on the French
nuclear scene. Based on its missions or regulatory obligations, each stakeholder is positioned in a specific context and respondswith its own monitoring strategy.

• the early detection of any abnormal
increase in radioactivity that may
result from an incident or accident at anuclear facility

The radiological monitoring of the environment conducted by these many organizations
addresses a variety of objectives:• protecting human health and theenvironment against the effects ofradiation exposureRadiological monitoring of the environment
makes it possible to detect and monitor, as
quickly as possible, any abnormal increase inradioactivity, whether due to an accident orincident, or specific natural events - extreme
weather situations in particular;• compliance with regulations by
nuclear operators
The impact of nuclear facilities is first evaluated on the basis of discharge, not throughdirect environmental measurements. However, regardless of the legal status of the facility (basic nuclear installation, environmentally
regulated facility, or activity falling under the

French Public Health Code), specific monitoring must be put in place to verify that thedoses generated by these facilities remain
well below the regulatory limits (1 mSv/year
for the public) and that the operator complies with the discharge limits set by theauthorities;• informing the public
All monitoring activities must provide forpublic information on activity levels found in
the environment. While each stakeholder has
its own communication methods (Internet
sites, periodic information brochures andannual reports), since 2009, the National
Environmental Radioactivity Measurement
Network (RNM) has centralized and reported
on these measurements by setting up a single
database and an Internet site (www.mesureradioactivite.fr). One of the main objectives of
the RNM is to ensure that the public receives
reliable, credible and understandable
information.

© Noak/Le Bar Floréal/IRSN

Monitoring the environment will help to estimate the impact of ionizing radiation onhumans and the environment, whether natural or anthropogenic (including discharge
from nuclear facilities).

This objective involves monitoring spatial andtemporal changes in levels of radioactivity
found in different environmental compartments across the country, although it focusesparticularly on areas surrounding major facilities likely to discharge radionuclides;

Figure I.7 - Taking water samples from the Donzère-Mondragon canal downstream from the Pierrelatte nuclear site

16

IRSN – Report on the Radiological State of the Environment in France 2010-2011

I.4
I.4 How isradioactivity
monitored?

© Caroline Pottier/Le bar Floréal/IRSN

Radiological monitoring of the environmentis based on three kinds of sampling systems
and/or measurements:• spot samples taken in the environment
for subsequent laboratory measurement
These samples are taken from a variety ofmatrices: rainwater, surface water (fresh
water and sea water), biological indicators(including mosses and algae), soil and sediment, as well as foodstuffs (milk and dairy
products, meat, fish, mollusks, crustaceans
and cereals);• continuous sampling procedures withsubsequent laboratory measurement ofcollected samples

Figure I.8 - Taking filter samples of atmospheric aerosols

This method primarily concerns measurements taken in the atmospheric compartment (aerosols, measurements of specificradionuclides in the air, such as tritium andcarbon-14) and in surface water (using water
samplers);© Arnaud Bouisson/MEDDTL/IRSN• continuous in situ measurement
systems, possibly associated with a realtime retransmission system. These systems are mainly used for early detectionof radiological events. The main continuous
measurement networks are the monitors
used to measure the ambient gamma dose
equivalent rate.

Figure I.9 - New-generation IRSN Téléray monitor (for gamma radiation dose rate measurement)
installed in Paris (French naval staff headquarters)
IRSN – Report on the Radiological State of the Environment in France 2010-2011

17

RADIOLOGICAL MONITORING OF THE ENVIRONMENT

I.5 Methodological aspects of
selecting monitoring stations

The general sampling principles are similar
to those used to characterize any
contamination. They rely on guides andstandards (Table I.2) developed specificallyby the nuclear equipment standardization
office (the BNEN, part of the FrenchStandards Association, Afnor). In the field ofradiological monitoring of the environment,
contamination bioindicators must be used.
These help to identify and quantify theconcentration in question.

Regarding methodology, the sampling strategy chosen is one of the key elements thatdefines the representativeness and validityof the measurements. In this document, theenvironment is presented as a set of compartments (terrestrial, atmospheric, continental aquatic and marine), also referred toas ‘environments’. Criteria must be definedfor each compartment as the basis forchoosing the location of stations.

Table I.2 - Examples of standards applicable to sampling for radiological measurement purposes

18

MatrixStandard

Air

NF M60-760(October 2001)

Water

PR NF EN ISO 5667-1(November 2005)

Soil

NF ISO 18589-1(December 2005)• Nuclear energy• Environmental radioactivity measurement• Soil• Part 1: General guidelines and definition

Biologicalindicators

NF M60-780-2(March 2001)• Nuclear energy• Environmental radioactivity measurement• Bioindicators• Part 2: General guide to sampling techniques

Foodstuffs

NF V03-009-1(July 2002)• Food products• Measurement of radioactivity in foodstuffs• Part 1: Guide to sampling, transportation and preservation of foodstuffs• Obtaining a laboratory sample

Title• Nuclear energy• Environmental radioactivity measurement• Air• Aerosol sampling for environmental radioactivity measurement• Water quality• Sampling• Part 1: General guide to setting up sampling programs and techniques

IRSN – Report on the Radiological State of the Environment in France 2010-2011

I.5
Selecting the location of sampling stations

Terrestrial and atmosphericcompartments
Sampling stations are chosen by considering the dispersion conditionsof atmospheric discharge from the nuclear facility monitored. Atmosphericaerosol sampling stations and rainwater collectors are installed systematicallyaround nuclear facilities for sectors under the influence of prevailing winds.
Whenever possible, milk samples are also taken from farms located near the facility,
under the prevailing winds. In addition, some metropolitan areas are also subject
to radiological monitoring to assess the exposure of populations in densely
built-up areas, whether or not they are close to nuclear or industrial sites.

Continental
aquatic
compartment
In this compartment, the siting of samplingstations takes into account the presence of
nuclear facilities. Samples of water, flora and,sometimes, fauna are taken both upstream
and downstream from the liquid effluent
outfall of a monitored facility and results arecompared to determine that facility’s
actual contribution.

Marine compartment
The siting of stations considers the location of potential sourcesof discharges and the conditions of their dispersion in the sea (ocean
currents and tidal ranges). The marine environment close to nuclear facilities
located along the Channel and North Sea coasts is subject to tidal currents,
resulting in the displacement of water masses from west to east.
Sampling locations are determined by the fact that the west of the Channel constitutes
upstream and the North Sea is downstream in terms of discharge from facilities locatedalong these coasts. In the Mediterranean, the Ligurian current, which runs from east to
west, is the primary influence on the movement and dispersion of discharge, for themost part into the Rhône. Samples of seawater, sediments and aquatic floraand fauna are taken in the eastern and western Rhône delta, making
allowance for the Ligurian current.

IRSN – Report on the Radiological State of the Environment in France 2010-201119

Collection of environmental monitoring samples
from the Marcoule site
In connection with the environmental monitoring of the Marcoule site, the CEA takes
more than 4,000 samples annually at 120
different spots. The various nuclear operators on this site are subject to the same
monitoring and the site’s effluent and environmental control and impact assessment
laboratory (LCEI) works with several thousand chemical and radiological analysis
results.
In this context, the laboratory, which
ensures that samples comply with current
standards, took the initiative of compiling acollection of data sheets describing samples
taken for environmental monitoring purposes on the site. For each sample, the collection provides an overview of theapplicable internal reference systems andthe references of sampling standards andregulations. The collection meets therequirements of the laboratory’s quality
and safety standards (NF EN ISO/CEI 17
025, ISO 14 001, OHSAS 18 001).

It is made up of 26 sheets all on the samemodel that is intended to be simple andintuitive, and which was distributed to every
laboratory employee. It is updated regularly
and includes a page for personal notes forusers who can add to it as necessary. The
analysis of all of these notes helps to update
and improve the collection.
Each sheet is designed according to a standard model and includes the following
information:• details of the sampling point: location,access, why this location was chosen,
sampling frequency and reproducibility;• sampling procedure, equipment used andreferences of applicable documents;• specific sampling conditions adopted toguarantee analysis quality and analysis list;• i nformation required to identify the
sample;• maintenance and periodic equipment
checks;• specific comments on safety, sampling
conditions and equipment.

Many photos and maps illustrate thesampling methodology.
The collection was completed in September
2010 and monitoring personnel responded
to it very positively and consult it daily. It
supports training and enhances the versatility of laboratory teams. It serves as an
essential reference document during
inspections and audits.

© CEA/Marcoule

CEA • FOCUS

RADIOLOGICAL MONITORING OF THE ENVIRONMENT© CEA/Marcoule

Figure I.10 - Sample of an aliquot of surface
water

Figure I.11 - Surface water sample from Codolet lake
20

IRSN – Report on the Radiological State of the Environment in France 2010-2011

I.5
Choice of environmental matrices
The tables below show the monitoring methods for the terrestrial, continental aquatic andmarine compartments, together with thecriteria associated with these choices.

Atmospheric and terrestrial compartments
Table I.3 - Strategic criteria for selecting the matrices sampled in the terrestrial compartment

Strategic criteria associated with this environment/product

Means of sampling
and/or direct measurement

Air

Receiving environment for atmospheric discharge. Radioactive particles andgases in the air deliver a dose to humans through external and internal exposure(inhalation).

• P robes for continuous measurement(air: ambient gamma dose rate).
• Continuous sampling and measurement sensors (aerosols).
• Aerosol collectors for laboratory
measurements.
• Environmental dosimeters.

Rainwater

Wet deposition of aerosols (and consequently radioactivity) by leaching fromthe air column through which the drops of water pass.

• Rainwater collectors.

Soil

Accumulation – concentration of radioactivity by wet or dry deposition. The soil
may also be responsible for contaminating vegetables, fruit and grasses throughthe root system.

• Spot samples (manual).
• In situ gamma spectrometry.

Vegetable
cropsContamination by deposition on the aerial portion of the plant or by absorption
through the roots. Risk of internal contamination after consumption.

• Spot samples (manual).

Animalproducts

Radioactivity in feed is transferred to products of animal origin, including milk,
which is a major vector for radionuclides (including cesium, strontium, andiodine).

• Spot samples (manual).

Environment/
product

Continental aquatic compartment
Table I.4 - Strategic criteria for choosing the matrices sampled in the continental aquatic compartment

Environment/
product

Strategic criteria associated with this environment/product

Means of sampling
and/or direct measurement

Continental
watersAs the receiving environment for liquid effluent from facilities and any
contributions from runoff, water is the direct vector for contamination of theaquatic environment.

• Continuous sampling and measurement systems(IRSN Hydrotéléray monitor).
• Water sampler.
• Spot samples.

Suspendedmatter inwater

Suspended matter is the preferred vector for radionuclides. Its mobility
contributes to the contamination of river banks, beaches or land after flooding.

• Settling tanks used with watercollectors.
• Laboratory filtration of water
samples.

Sediments

Sediments are good integrators of contamination and a reservoir of contamination of the aquatic environment through desorption.

• S pot samples(manual or mechanical).

Aquatic plants

Aquatic plants can fix certain radionuclides quickly. Their broad geographic
distribution allows comparison among specific radionuclide activities indifferent locations.

• Spot samples (manual).

FishHumans regularly consume fish, which are good integrators of radionuclides.
The geographic distribution of the species sampled also allows comparison of
specific activities measured at different sampling points across the country.

• Spot samples (fishing).

IRSN – Report on the Radiological State of the Environment in France 2010-2011

21

RADIOLOGICAL MONITORING OF THE ENVIRONMENT
Marine compartment
Table I.5 - Strategic criteria for selecting the matrices sampled in the marine compartment

Environment/
product

Strategic criteria associated with this environment/productSea water

As the receiving environment of liquid effluent and contributions ofradionuclides via runoff, sea water is a direct vector of contamination in
the marine environment.

• Spot samples (manual).
• Water collectors.

Sediments

Sediments are good integrators of radionuclides and a reservoir ofcontamination of the aquatic environment through desorption.

• Spot samples (manual).

Algae

Marine algae react quickly to changes in the radionuclide
content of water.

• Spot samples (manual).

Mollusks

Given their feeding methods, marine mollusks are good bioindicators forlong-term monitoring, whether they are filter feeders or grazers.

• Spot samples (manual or directcollection from producers).

Crustaceans
Fish

As they are at the end of the food chain, fish are good integrators ofradionuclides. They are also a large part of the human diet.

• Spot samples (fished or directcollection at ports).

I.6 Analysis plans
As soon as they arrive at the laboratory, samples are processed and conditioned according
to the radiological tests to be performed. The
tests performed on each sample follow predefined plans based on the type of sample,

the compartment, and the type of facility orsite surveyed (size, type of discharge) and its
event history (past incidents, past release,fallout, etc.).
In the case of nuclear facilities, the types ofsamples and analysis plans are in proportion
to the environmental hazards or drawbacks

Means of samplingthat the facility may represent. Regulatory
monitoring around basic nuclear installations is adapted to each type of facility(nuclear power plant, factory or laboratory).
Table I.6 summarizes environmental radiological monitoring principles in accordancewith existing regulatory provisions.

Table I.6 - Examples of regulatory monitoring requirements applicable to operators near their facilities (source: ASN).

Environment
monitored ortype of test
Air at groundlevel

Ambient gamma
radiation

Laboratory or factory• 4 continuous sampling stations collecting atmospheric dust on fixed filters with daily measurements of grossbeta activity. Gamma spectrometry if gross beta activity > 2 mBq/m3.
• 1 continuous sampling station under prevailing winds with weekly tritium measurement (3H).
• 4 monitors at a distance of 1 km with continuous measurement•4
 monitors at a distance of 1 km withand recording.
continuous measurement and recording.
• 10 monitors with continuous measurement at site perimeter•1
 0 integrating dosimeters at site perimeter(monthly readings).
(monthly readings).
• 4 monitors at a distance of 5 km with continuous measurement.
•1 station under prevailing winds (monthly collector) withmeasurement of gross beta activity and 3H on a monthly
mixture.

•2
 continuous sampling stations, including
one under prevailing winds with weekly
measurement of gross beta activity and 3H.

Liquid waste
receivingenvironment• River samples taken upstream and at mid-discharge for eachdischarge (riverside plant), or sampling after dilution in thecooling water and bi-monthly sampling at sea (coastal plant):
measurement of gross beta activity, potassium (40K) and 3H,
measurement of gross beta activity on suspended matter.
• Continuous sampling of 3H (daily average mixture).
• Annual sampling of sediments and aquatic flora and fauna withmeasurement of gross beta activity, 40K and 3H, gamma spectrometry.

• At least weekly sampling of water in thereceiving environment with measurementof gross alpha activity, gross beta activity,
40K and 3H.
• Annual sampling of sediments, aquatic floraand fauna for gamma spectrometry.

Ground water• 5 sampling points (monthly check) with measurement of grossbeta activity, 40K and 3H.

• 5 sampling points (monthly check) withmeasurement of gross beta activity, 40K and 3H.
• Measurement of gross alpha activity.

Rain

Soil

PlantsMilk

22

Nuclear power plant• 1 annual sample of topsoil with gamma spectrometry.
• 2 grass sampling points (monthly check) with measurement ofgross beta activity, 40K and gamma spectrometry. Measurementof carbon-14 (14C) and total carbon (quarterly).
• Annual campaign on the main agricultural products withmeasurement of gross beta, 40K, 14C and total carbon and gamma
spectrometry. activity• 2 sampling points (monthly check) with measurement of beta
activity, 40K and, annually, 14C.

IRSN – Report on the Radiological State of the Environment in France 2010-2011• 4 grass sampling points (monthly check).
• Annual campaign on the main agricultural
products with measurement of gross beta
activity 40K, 14C and total carbon andgamma spectrometry.
•1
 sampling point (monthly check) withmeasurement of beta activity and gamma
spectrometry (+ 3H and 14C periodically).

I.6
Table I.7 provides a simplified representation of the analysis plans as prepared by
IRSN around different types of sites andthroughout the country.
Table I.7 - Model analysis plans developedby IRSN in connection with radiological monitoring in France

Radionuclides targeted
Environment studiedUAm, Pu

H

3

C

14

Sr

90

Cs

137

Iodines

Other beta/
gamma (*)

Environment far from a nuclear site
Former mining site
Site in the front end of the nuclear fuel cycle
Decommissioned NPP

Gross alphaactivity

Operating NPP
Site in the back end of the nuclear fuel cycle
Waste disposal site
Civilian and military research centers
Naval bases

AFCN • FOCUS

Radionuclide targeted systematicallyRadionuclide targeted on a spot basis, depending on the sites or during specific studies(*) Other beta/gamma-emitting radionuclides: 58Co, 60Co, 134Cs, 40K, 99mTc and others.

Radiological monitoring in Belgium
Radiological monitoring conducted by the
Belgian government agency, the Federal
Agency for Nuclear Control (FANC), can beseen as a type of ‘environmental screening.’
The hope is that nothing or, to be moreexact, nothing significant will be found. This
monitoring has shown, year after year, thatthe radiological situation in Belgium generally gives no cause for concern. It reflects
efforts by operators of facilities whose
activities may have a radiological impact on
the environment to reduce that impact. To
this end, operators are required not only totake every step to ensure that discharge
from their facilities remains below authorized limits, but also to minimize it byapplying the ALARA principle.
Radiological monitoring in Belgium covers
two complementary aspects:• general monitoring across the country,
outside areas where significant nuclear
activities are carried out. This indicates thelevel of radioactivity to which the population is naturally exposed. It covers areas at
a distance from nuclear sites, such as thecoastal region, and other areas known as‘reference’, such as the Brussels metropolitan area, which is Belgium’s largest andhome to 10% of the population;• close monitoring around sites where
activities with a possible radiologicalimpact on the environment are carriedout. Nuclear power plant operators in Belgium (GDF-Suez Electrabel) are not under
any obligation to conduct environmental
radiological monitoring. Other facilities
set up dosimetric control both onsite andin the surrounding area and, in very rarecases, conduct environmental monitoring
nearby. The radiological monitoring
implemented by FANC aims at covering
the entire country and areas in the vicinityof the following nuclear sites:• the Doel and Tihange nuclear power
plants;• t he area of Belgium close to Chooz
nuclear power plant in France;• the Belgian Nuclear Research Center(SCK•CEN) site, in Mol;
• the Belgoprocess, Belgonucléaire and theFranco-Belgian fuel manufacturing
plants (FBFC International) in Mol and
Dessel;• the National Institute for Radioelements(IRE), MDS-Nordion, Sterigenics and Ion
Bean Applications SA (Iba) in Fleurus.
Close monitoring also covers facilities
where radioelements are used, including
hospitals, universities and certain industrial
sectors such as feed phosphate productionin the Tessenderlo region. The process usedin this non-nuclear industrial activity concentrates a natural radioelement –radium-226 – in the liquid effluent it
discharges.
In practice, radiological monitoring in the
country keeps track of both artificial andnatural radiation levels in two ways:• continuously, via the automatic Telerad
network, which measures ambient gamma
radioactivity in the air;• intermittently, through periodic measurement campaigns in the field and by
taking samples for subsequent laboratory
analysis.

Focus (continued)
IRSN – Report on the Radiological State of the Environment in France 2010-2011

23

RADIOLOGICAL MONITORING OF THE ENVIRONMENT

Sampling campaigns and measurements inthe field are the keystone of radiologicalsurveillance in Belgium. They are used toobtain a more precise idea of Belgium’s
radiological profile and must help to determine the exact levels of natural and artificial radiation in the environment and assessradiation doses to the population. They systematically target the main environmental
compartments and components of the foodchain liable to be contaminated and towhich the population may be exposed. Specialized SCK•CEN and Ire-Elit teams takesamples for FANC. Sampling frequency has
been defined to generate the most useful
information possible, making allowance fortechnical and equipment constraints. The
samples are then analyzed in these institutions’ laboratories to determine theprecise nature and level of radioactivity
they contain.
These analyses measure alpha-, beta- andgamma-emitting radionuclides, alltogether or according to type. In the latter
case, they seek, in particular, to measurenaturally occurring radionuclides (such as
beryllium-7 and potassium-40), which
serve as reference points, and radionuclides

24

Borssele

Doel

Gravelines

Nete Mol

Ru
pe
l

ut
ca
Es

Tihange
Fleurus

bre
Sam

Me
us
e

The Telerad network is the automatic
remote radioactivity measurement network
in Belgium. It is made up of 219 stations
that continuously measure radioactivity inthe air and river water. The stations are distributed across the country, around the
Tihange, Doel, Mol and Fleurus nuclear
facilities, and in urban areas near them, as
well as in the vicinity of the Chooz facility inFrance. They are connected to a centralized
system and issue automatic warnings if theydetect abnormally high radiation levels. In
the event of a nuclear accident, the Telerad
network plays a critical role in accident
severity assessment, decision-making, optimizing response and countermeasures, andkeeping the population informed on an
ongoing basis. In normal situations, the Telerad network measures the ambient dose
rate due to gamma radiation. This dose rateis associated with the level of natural radiation, which is also called backgroundradiation.

Meuse

FANC• FOCUS

Focus (continued)

Chooz
Monitors – national
Monitors – urban areas
Monitors – rivers
Nuclear sites

Cattenom

Figure I.12 - Geographic distribution of the FANC’s Telerad network monitoring stations in Belgium.

that are characteristic of specific humanactivities (such as those associated with the
production of nuclear reactor fuel, radioactive tracers used in nuclear medicine andradium-226, a naturally occurring radionuclide that is concentrated in liquid effluent
from the feed phosphate production process). FANC then centralizes, analyzes andinterprets the results.
The Belgian radiological monitoring program involves nearly 5,000 samples every
year, and 29,500 analyses. Atmosphericdischarge and liquid effluent from themain nuclear sites are also monitored andanalyzed.

Overall, the radiological situation is
excellentRadiological monitoring in Belgium, which
provides a precise inventory of environmental radioactivity in the country, as well as
the risks to the population, has not revealed
any major problems. Artificial radiation isusually much lower than natural radiation,
if not simply below the detection limit.
Monitoring also clearly shows that the dose
rate (ambient radioactivity) under normal
conditions, and excluding medical exposure, is determined primarily by the type of

IRSN – Report on the Radiological State of the Environment in France 2010-2011

soil. The rocky soils in the south of the country give off more radon (natural radioactivegas) than those in the north, which are
sandy. The dose rate measured in Wallonia,
for example, is higher than that measured
in the area around the Doel nuclear plant,
which has a negligible radiological impact
on the environment. The radiologicalimpact of nuclear power plants, in particular, is negligible, or so low as to be below
the detection limit.

Special attention is required
While the radiological situation in Belgium
is quite satisfactory, one drainage system,
the Laak-Winterbeek-Nete-Escaut system,
stands out because of its abnormally highartificial and natural radiation (226Ra) level.
Some nuclear facilities in the Mol–Dessel
region do have a measurable, albeit slight,
impact on the environment. The same istrue for the non-nuclear feed phosphateproduction industry in the Tessenderlo
region, which discharges 226Ra. However,
the measurable radiological impact of thesefacilities in the northwest of the country has
seen a sharp decline in recent years.

I.7
I.7 From preparation
to physicalmeasurementof samples

Figure I.13 summarizes the main stages in thetransformation of a grass sample, from its
collection to physical measurement andarchiving.

© IRSN

Measuring the radioactivity of an environmental sample begins with its physical preparation. This may range from simply placing
it in a standardized container to a more elaborate preparation, such as drying, calcination
or freeze-drying, to concentrate the sample.
In most cases, analysis does not require theentire sample. The sample is first homogenized so that the amount taken for the test

does not bias the representativeness of themeasurement. Most monitoring organizations also archive some of the samples analyzed (especially filters) for possible
subsequent analysis using additional or more
effective methods.

2 • Drying in the oven.

3 • Freeze-drying.

4 • Crushingand homogenization.

5 • Calcination.

6 • Radiation chemistry.

7/1 • Detectionof alpha radiation.

7/2 • Detectionof beta radiation.

7/3 • Detectionof gamma radiation.

8 • Archiving.

© IRSN1 • Grass sampling.

After the sample is collected in
the field (1), it must be packaged
quickly to prevent any degradation and taken to the laboratory
for processing.
When it arrives, the sample’scharacteristics are recorded toensure traceability throughout
the process.

Radioactivity measurement for asample begins with its physicalpreparation. This ranges from
simple packaging in a standardized container to more elaborate
preparation, such as drying in anoven (2), freeze-drying (3),crushing (4) and calcination (5),all of which serve to concentrate
the sample's radioactivity.

The need to concentrate thesample or extract the targetedradionuclides sometimes involves
advanced radiation chemistry
processing (6), which generally
concentrates or separates theradionuclides in question.

At the end of this phase, thesamples are measured using
different kinds of countersdepending on the targetedradionuclides (7) (alpha/beta
proportional counters, alphacounters with photomultipliertubes, liquid scintillation
counters and gamma detectors).
They are then archived (8).

Figure I.13 - Sample and laboratory analysis phases for monitoring purposes

IRSN – Report on the Radiological State of the Environment in France 2010-2011

25

RADIOLOGICAL MONITORING OF THE ENVIRONMENT

After physical preparation, radiochemistry
procedures are generally employed to concentrate or separate the targeted radionuclides. In general, laboratories also havemethods for processing and conducting
physical-chemical analyses of the samples.
At the end of this phase, the samples areencapsulated and sent to the nuclear measurement laboratory. Counters or spectrometers (alpha/beta proportional counters,alpha counters with photomultiplier tubes,
liquid scintillation counters, Ge gamma
detectors with sample changers, NaI gamma
detectors, grid ionization chambers withchanger and semi-conductors) are used todetect alpha, beta and gamma radiation.
Measurement quality in terms of activity,
density and nature, is guaranteed by the useof tracers or standard specific reference
sources.

• measurement of natural or artificial gammaemitting radionuclides (including 137Cs, 134Cs,
60Co, 125Sb, 131I, 129I, 40K, 7Be, 210Pb, 234Th, 214Pb,
and 222Rn);• measurement of alpha-emitting radionuclides such as plutonium, 241Am and 244Cm,
uranium, thorium and 210Po;•m easurement of stable elements, such as
K, Na, Ca, Fe, Sr, Ni, Pb.

© A. Cheziere/CEA

Concentrating the sample or extracting theradionuclides to be measured requires theuse of a laboratory guaranteeing the highest level of quality during all or some of thestages involved in characterizing theradionuclides in a sample.

Figure I.14 - Spectrometry measurement on alpha spectrometry system with a grid ionization chamber© Y. Geoffray/Areva

The range of metrological skills implemented by laboratories to measure environmental radioactivity can be seen below:• gross alpha/beta measurements to monitor aerosol and water filters;• 226Ra measurement;• measurement of beta-emitting radionuclides (such as 3H, 14C, 63Ni, 90Sr, 241Pu, and
210Pb);© IRSN

Figure I.15 - Alpha spectrometry measurement© AcroFigure I.16 - Measurement by liquid scintillation

Figure I.17 - Preparation for measuring uranium and radium

26

IRSN – Report on the Radiological State of the Environment in France 2010-2011

© Laurent Zylberman/Graphix-Images/IRSN

I.7

Figure I.18 - Algae sampling (cystoseira) on the coast.
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THE NATIONAL ENVIRONMENTAL RADIOACTIVITY MEASUREMENT NETWORKAND THE STAKEHOLDERS INVOLVED IN MONITORING IN FRANCE

28

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

II

THE NATIONALENVIRONMENTAL
RADIOACTIVITY
MEASUREMENTNETWORK AND THE
STAKEHOLDERS INVOLVEDIN MONITORINGIN FRANCE

II.1 The National Environmental Radioactivity Measurement
Network (RNM)© French Navy

II.2 Who monitors radioactivity in France?

THE NATIONAL ENVIRONMENTAL RADIOACTIVITY MEASUREMENT NETWORKAND STAKEHOLDERS INVOLVED IN MONITORING IN FRANCE

II.1 The National
Environmental
Radioactivity
Measurement
Network (RNM)

The goals of the French National
Environmental Radioactivity
Measurement Network (RNM) include
centralizing information on
environmental radioactivity in France,
ensuring that information is transparent
and understood by all audiences, andpromoting the standardization andquality of laboratory measurements.

Background and goals
Monitoring environmental radioactivity
involves many organizations on the French
nuclear scene. Based on its missions or regulatory obligations, each stakeholder is positioned in a specific context and respondswith its own monitoring strategy. Thousandsof results are thus available in France, whether
provided by IRSN, nuclear facility operators orother stakeholders in the public, private andnon-profit sectors. However, despite the efforts
made regarding information and transparency
in this area, the great number of stakeholders
and information sources makes it difficult forthe public to obtain a clear grasp of the results
and each stakeholder’s role. The quality of
information is also a critical issue, particularly
in a context as sensitive as environmental
radioactivity and in a field as complex as
nuclear metrology. It is therefore essential toensure, in advance, that the laboratories havethe requisite technical and organizational skills.

Further to the transposition of European
Directive 96/29 into French law, the RNM
was set up under the French Public Health
Code, as amended by Decree No. 2002-460
of April 4, 2002 on the general protection of
persons against the dangers of ionizing radiation. The operating procedures of this network, which were initially set out by
ministerial order (October 17, 2003 and thenJune 27, 2005), were replaced by a decision
ratified by ASN in 2008 (No. 2008-DC-0099
of April 29, 2008) to incorporate regulatorychanges and, specifically, the publication of
Act No. 2006-686 of June 13, 2006 on nuclear
transparency and safety (the TSN Act).
The RNM was set up with two main goals:• to ensure the transparency of information
on environmental radioactivity by making
the results of environmental radiologicalmonitoring in France available to the public;

Health (DGS)
Environment (DGPR)
Consumer Affairs(DGCCRF - SCL)
Agriculture (DGAL)
Defense (EMM - SPRA)Regional Directors for
the Environment,
Town and Country
Planning and Housing(DREAL)

Regional Health Agency(ARS)
Departmental Directorate
for Public Health and
Safety (DDPP) and
Departmental
Directorate for Social
Cohesion and Public
Health and Safety

The measurements that the RNM gathers are
essential for assessing the impact of radioactive substances on health, the environment
and economic resources (particularly, waterand agriculture).

RNM organization andoperation
The RNM operates under the auspices of ASN
in collaboration with IRSN (Figure II.1) and in
partnership with the RNM's main stakeholders, including the Ministries of the Environment (DGPR), Consumer Affairs (DGCCRF),
Health (DGS and ARS), Defense (SPRA andIntercomparison organization

Certification commission secretariat

Government agencies
in charge ofhealth controls

The RNM's mission is to help estimate thedoses of ionizing radiation to which the population is exposed and inform the public. Tothat end, it gathers and issues to the public:• results of environmental radioactivity
measurements;• summary documents on the country's
radiological status and assessment of ionizing radiation doses to which the population
is exposed.

Steering committee secretariat

Presidency of the different bodies

Ministries• to continue developing a quality policy on
environmental radioactivity measurementsby setting up a laboratory certification
system, under the authority of ASN.

Information system development andadministration

Health safety agencies

Nuclearoperators

Public institutes

Agency for Food,
Environmental andOccupational Healthand Safety (ANSES)

Institute for Public
Health Surveillance(InVS)
Institute for RadiologicalProtection and Nuclear
Safety (IRSN)(DDSCPP)EDF
AREVA
Alternative Energies
and Atomic Energy
Commission (CEA)
National Radioactive
Waste Management
Agency (ANDRA)
French Navy
Laue-Langevin Institute(ILL)

Regional governments

Associations

Organization of Scientists
for Information about
Nuclear Energy (GSIEN)
Association for Radioactivity
Monitoring in WesternFrance (ACRO)
Approved Air Quality
Monitoring Associations(AASQA)
Nuclear Equipment
Standardization Office(BNEN)
National Association of
Local Information
Commissions andCommittees (ANCCLI)
and Local Information
Commissions andCommittees (CLI)* Different representatives, which may or may not be from other organizations, are also appointed as certified professionals.
Figure II.1 - Stakeholders of RNM bodies and main producers of measurements of environmental radioactivity in France.

30

IRSN – Report on the Radiological State of the Environment in France 2010-2011

II.1
the French Navy), and Agriculture (DGAL),
health and safety agencies (InVS and ANSES),
the main nuclear operators (EDF, Areva, CEA
and ANDRA) and environmental and consumer
protection associations (ACRO and GSIEN).
It is coordinated by two entities supervised
by ASN. These are a steering committee,
which is responsible for the network's strategic policy, and a certification commission,
which issues opinions on certification
requests. Figure II.1 illustrates the roles of
IRSN and ASN, as well as of the main stakeholders in the national network and the mainorganizations involved in taking environmental
radioactivity measurements.
The steering committee issues its opinion on
the national network guidelines put forward
by ASN. It ensures that the radioactivity data
referred to in Article R1333-11 of the French
Code of Public Health is published. It may
also be required to give its opinion on summary reports on the radiological state of theenvironment and the impact of nuclear facilities, issued by IRSN or any other entity thatrequests it to do so.

Who sends theenvironmental
radioactivity
measurements to thenational network?
In accordance with Article 1333-11 of theFrench Public Health Code, the results ofenvironmental radioactivity measurements
gathered by the RNM are those obtained:• under laws or regulations concerning theassessment of doses to which the population is exposed and, in particular, results
showing the environmental impact of
nuclear activities: nuclear operators that are
required by law or regulations to provide
environmental radioactivity measurements
must have these measurements performedby certified laboratories or IRSN and transmit the results for publication on the RNM
website;• by the French Nuclear Safety Authority,
regional authorities, government agencies,
and public bodies that have measurements
performed by certified laboratories or by
IRSN;• by any non-profit association or other private entity that has measurements performed by certified laboratories or by IRSN
when the organization that holds theseresults asks that they be transmitted to the
RNM.

Interlaboratory
proficiency tests andcertifications issued by
ASN
Certification to measure radioactivity in theenvironment concerns all laboratories (public, private, university and non-profit), but
directly concern those that perform measurements under legal or regulatory provisions
and are required to transmit their measurements to the RNM. These laboratories must
submit comprehensive documentation demonstrating the compliance of their organizational structure and practices, as well as takepart in interlaboratory proficiency tests organized by IRSN to test the laboratories' technical competency (see Focus and Figure II.2).
This generally involves aptitude tests inwhich results obtained by laboratories on
identical samples are compared to an
assigned value (reference value defined by
IRSN). The IRSN tests concern the measurement of beta- and gamma-emitting radionuclides, pure beta emitters and artificial alphaemitters, as well as radionuclides from thedecay chains of uranium, thorium and radiumand of uranium content, amounting to morethan 43 types of different tests.

The samples prepared by IRSN are distributed simultaneously to the participants tobe measured at the same time. The sample
batch must be homogeneous and stable (interms of radioactivity) so that no discrepancy can be attributed to a lack ofhomogeneity or stability.
The number of participants in each test
ranges from 15 to 70 and includes several
laboratories from outside France. IRSN has
been organizing this kind of test for 40 years,
with six to seven tests/year conductedtoday. IRSN has been certified by the French
Accreditation Committee (COFRAC) since2006 to hold these specific interlaboratory
tests. These tests primarily allow participating laboratories to obtain or renew certification from ASN or the DGAL, in connection
with the regulation, and to ensure the quality of the analytic methods implemented
and provide the accrediting organizations
with the information needed to determine
whether the laboratories have expertise in
the analytic processes.
A dedicated Internet site (https://cilei.irsn.fr/)
has been available since January 2011 forthe dissemination and exchange of
information among IRSN and participants.

IRSN is entrusted with a number of tasks
regarding these tests, either by ASN throughits Decision No. 2008-DC-0099 of April 29,
2008, or by the DGAL as the national reference laboratory for radionuclides, (LNR RN)
further to the Order of December 29, 2009.
These tasks include preparing samples, delivering them to the laboratories taking part in
the tests, determining the assigned values,and conducting statistical analysis oflaboratory results.

IRSN – Report on the Radiological State of the Environment in France 2010-201131

THE NATIONAL ENVIRONMENTAL RADIOACTIVITY MEASUREMENT NETWORKAND STAKEHOLDERS INVOLVED IN MONITORING IN FRANCE

Organization of an interlaboratory test
for ASN laboratory certification
Definition/planning ofinterlaboratory tests
by ASN and the certification commission

Search for a raw sample in the environment
or production of an artificial sample
by IRSN

Announcement of interlaboratory test
(Official ASN bulletin, Internet sites)

Registration of the laboratories

Samples prepared by IRSN,
measurements to confirm homogeneity,stability and determination of reference values
by IRSN

Samples sent to the laboratories, analyses by thelaboratories

Final report sent to the laboratories,
ASN and the certification commission

Review of requests by certification commission
and investigation of requests by ASN

Publication of ASN’s laboratory certification decision

Figure II.2 - Organization of an interlaboratory proficiency test for ASN certification

32

IRSN – Report on the Radiological State of the Environment in France 2010-2011

ASN • FOCUS

II.1
Certification of environmental radioactivity
measurement laboratories
The ASN certifies laboratories that may
release their results on this RNM site. The
laboratory certification processes aredefined in ASN’s decision No. 2008-DC0099 of April 29, 2008. The certification
issued covers measurements made in thelaboratory as well as provisions concerning
environmental sampling methods.
Each measurement category, which combines a type of measurement (artificial or
natural radionuclides, gamma-, beta- or
alpha-emitting radionuclides and ambient
gamma dosimetry) and an environmental
compartment (water, soil, biological products, including plants, fish and milk) is covered by a specific certification (Figure II.3).
ASN thus issues 43 different types ofcertification.
aerosols
14%

gas
air 12%

soils 16%

ambient
gamma 5%water 35%

biological 18%

Figure II.3 - Distribution of certifications
by environmental compartment as ofJanuary 1, 2012

Conducting intercomparison tests of laboratories involves low levels of activity even
if, in the environment, the activities of artificial radionuclides are rarely higher thanthe decision thresholds for the most sensitive measurement methods. Laboratory
proficiency is thus tested on samples‘recharged’ in the laboratory to reach activity levels of around 0.5 to 10 Bq/kg for artificial gamma-emitting radionuclides (60Co,
137Cs) and 0.05 to 1 Bq/kg for alpha emitters (Pu, Am). However, as the activity

levels of uranium and thorium decay chain
radionuclides found in the environment are
naturally higher (near or above 50 Bq/kg ofsoil), the proficiency tests are generally performed on samples taken directly from theenvironment.
Every French or foreign laboratory thatseeks acknowledgement of its expertise inthis area in connection with the RNM mustobtain certification, whether the scope of
its activity is defined (industrial site) or not(service provision), and regardless of its status, size, and sector of activity. Primarily,
this concerns environmental monitoring
laboratories that conduct measurements inaccordance with laws or regulations andthat, as of January 1, 2009, are required toobtain certification to transmit their measurements to the RNM (including Andra,
Areva, CEA, EDF, Max Von Laue – Paul Langevin Institute and the French Navy). However, it also covers all public, private,
university and non-profit association laboratories that monitor environmental radioactivity for public agencies, regional
authorities or for their own purposes.
To obtain certification, the laboratory must
submit documents to ASN showing that its
organizational structure and practices comply with the ISO/CEI 17025 standard, whichsets out the general requirements applicable to laboratories. These documents also
include an application for the certifications
sought, along with the laboratory results of
the interlaboratory comparison tests conducted by IRSN.
Certification is issued for a maximum of five
years on the recommendation of a joint certification commission that bases its findings
both on the results obtained in the interlaboratory comparison tests and on the certification application documents submitted
by the laboratory.

Status of certified laboratories
on January 1, 2011
On January 1, 2011, there were a total of 60
certified laboratories (Figure II.4). Of that
number, 42 were nuclear operators’ laboratories, and the others were divided among
the private (9), university (5), institutional(2) and non-profit association (2) sectors.
These laboratories held 746 certifications
covering the 43 certification categories.
operator 71%

university 8%
institutional 3%

association 3%
private 15%

Figure II.4 - Distribution of certified
laboratories by status as of January 1, 2012

The largest group (55) of certified laboratories monitor radioactivity in the water,
with up to 13 different certifications formonitoring in this environment. Some 40
laboratories have been certified to measure
biological matrices (the food chain), atmospheric dust, the air and ambient gamma
dosimetry. Another 30 laboratories focus on
soils. While most laboratories can measure
gamma emitters in all environmental matrices, only a dozen are certified to measurecarbon-14, transuranium elements, or uranium and thorium natural decay chain
radionuclides in water, soil and biologicalmatrices.

These decisions are published on ASN’s
Internet site (www.asn.fr) at the same timeas the list of certified laboratories, which is
updated twice a year.

Focus (continued)
IRSN – Report on the Radiological State of the Environment in France 2010-201133

THE NATIONAL ENVIRONMENTAL RADIOACTIVITY MEASUREMENT NETWORKAND STAKEHOLDERS INVOLVED IN MONITORING IN FRANCE

ASN • FOCUS

Focus (continued)

Overall assessment of the laboratory
certification process
The process for certifying environmental
radioactivity laboratories, which came into
effect in 2003, drives continuous improvement of practices, regarding both sampling
methods and radioactivity measurements.
These improvements, due specifically to theimplementation of standardized methods,
are significant in the area of sampling, butalso in the area of measurement. The analysis of eight years of feedback from interlaboratory comparison tests shows, from one
test cycle to another, that values transmitted by the laboratories are closer to the ref-erence value provided by IRSN. This isreflected in a generally lower interlaboratory standard deviation between the tests
in the first and second certification cycles(2003-2008 and 2008-2012 respectively).

sources of information. The system isintended to boost public confidence inmeasurements of the radiological state of
the environment released on the RNM
Internet site.

The challenges now facing the ASN laboratory certification system include maintaining the quality of the environmental
radioactivity measurement data provided
by certified laboratories, improving it further, encouraging certified laboratories tobroaden their scope of activity, and allowing new laboratories to participate in thecertification process to ensure multiple

Table II.1 - Certifications and intercomparison test schedule 2011-2015

Type 1
Code

Radioactive
measurement
category

Type 2

Water **

Type 3

Soil matrices

Biologicalmatrices

Aerosols on
filterType 5

Type 6

Gas air

Ambient
environment(soil/air).. _01Gamma emitters
E > 100 keV

1_01

2_01

3_01

4_01

5_01

-

.. _02Gamma emitters
E < 100 keV

1_02

2_02

3_02

4_02

5_02

-

.. _03Gross alpha.. _04Gross beta.. _05

H-3

1_03

-

-

4_03

-

-

**

1_04

-

-

4_04

-

-

**

1_05

2_05

3_05

-

See
water

-

.. _06

C-14

1_06

2_06

3_06

-

5_06

.. _07

Sr-90/Y-90

1_07

2_07

3_07

4_07

-

-

.. _08Other pure beta
emitters (including
Tc-99)

1_08

2_08

3_08

-

-

-

.. _09Isotopic U

1_09

2_09

3_09

4_09

-

-

.. _10

Isotopic Th

1_10

2_10

3_10

4_10

-

-

.. _11

Ra-226 + desc.

1_11

2_11

3_11

-

Rn-222:
5_11-.. _12

Ra-226 + decay
prod.

1_12

2_12

3_12

-

Rn-220:
5_12-.. _13

Pu, Am isotopes(Cm, Np)

2_13 *

3_13

4_13
*

.. _14

Halogen gases

-

-

-

-

5_14

-

.. _15

Noble gases

-

-

-

-

5_15

-

.. _16

Gamma dosimetry

-

-

-

-

-

6_16

.. _17

Uranium content

1_17

2_17

3_17

4_17

-

-

2011

2012

2013

*

2014

1_13 **

2015* in 2015 and 2016: reversal of EIL 1_13 and 2_13** EIL 1_04 and 1_05 in sea water scheduled in 201434

Type 4IRSN – Report on the Radiological State of the Environment in France 2010-2011

-

II.2
The RNM information
system and its Internet site
Article 4 of ASN approved decision No. 2008DC-0099 puts IRSN in charge of managing the
RNM. To that end, the Institute must:• centralize environmental radioactivity measurement data, transmitted in accordancewith Article II of Article R1333-11;• analyze this data;• send it to ASN and the French Institute for
Public Health Surveillance (INSV), in accordance with Article L.1413-4 of the French
Public Health Code;• release the data to the government agencies responsible for nuclear activities and to
the public;• p reserve and archive the data for an
unlimited period of time.
The RNM information system, which wasdeveloped by IRSN, allows organizations that
produce radioactivity measurements to send
their data, formatted in accordance with ajointly defined data exchange protocol(Figure II.5), via a secure Internet connection.

Data transmitted(RNM exchange protocol)

Data checked and recordedin the database

National
network

Producers

Data provided to the
public and experts

Responses transmitted
to producers

Figure II.5 - Organization of the RNM information system

The data is fed into the RNM database thatcame into operation in January 2009 andthat has already received 600,000 measurement results (as of December 31, 2011). The
database is updated very regularly, with anaverage of 17,500 measurements added
every month. More than 40% of the results
sent to the RNM come from IRSN
monitoring networks.
The database is accessed via an information
system that can provide all the information
to the public and experts through an Internet
mapping portal (www.mesure-radioactivite.fr).

The opening of the RNM Internet site was amajor step forward in achieving transparency.
The RNM has been developed with an awareness of the need to take into account theconcerns of all stakeholders who contributeto the network as data producers or membersof the network’s bodies.

Visual presentation, educational content,
accessibility and understanding of data
placed online have all been identified bythese stakeholders as areas that could be
improved. The national network’s information
system will go on changing, not only toincorporate the technical improvements it
needs to function properly, but also to meetthe expectations of Internet users and take
into account their comments on how
measurement data is presented.

II.2 Who monitors
radioactivity inFrance?
Monitoring involves many stakeholders, primarily nuclear facility operators, nuclear
safety authorities who are responsible forregulation, and IRSN. Other stakeholders inthe society, specifically associations – including local information commissions and committees, air quality monitoring and non-profit
environmental protection associations - also
participate in studies or environmental radioactivity monitoring.

The French Institute forRadiological Protection
and Nuclear Safety (IRSN)

IRSN helps to assess the radiological statusof the environment in three ways:• by conducting assessments as part of its
technical support to the relevant authorities: ASN or the French Representative incharge of Nuclear Safety and Radiation Protection for Defense-related Activities andFacilities (DSND), prefects and Regional
Directorates for the Environment, Town andCountry Planning and Housing (DREAL).
These assessments involve examining
nuclear facility applications for water intake
and liquid effluent discharge permits(DARPE), analyzing nuclear facility safety
reports, with a particular focus on the characteristics and vulnerability of knowledge ofground water and the provisions made by

IRSN – Report on the Radiological State of the Environment in France 2010-201135

THE NATIONAL ENVIRONMENTAL RADIOACTIVITY MEASUREMENT NETWORKAND STAKEHOLDERS INVOLVED IN MONITORING IN FRANCE

the operator to monitor it, and evaluating
technical documentation (on the environmental impact of former uranium mining
sites, for example). This work allows the relevant authority to set out the requirements
for discharge permits or operating licenses
for these facilities, and those for controllingthe impact of former uranium mining sites.
In addition, IRSN experts may be called on
to support the inspections initiated by ASN
or the DREALs;• by contributing to radiological monitoring
across the country, as part of the tasks
assigned to it in its founding charter, Decree
No. 2002-254 of February 22, 2002,
amended on April 7, 2007. In that connection,
IRSN conducts regular monitoring aroundnuclear sites, complementing the monitoringprocedures set up by nuclear operators, as well
as more general monitoring in France;• by conducting studies and research on
environmental radioactivity IRSN regularly
acquires data on environmental radioactivity from the radioecological studies it conducts at the request of nuclear operators,
public authorities or civil society representatives (including CLIs, local authorities, andnon-profit associations), or as part of its
own research programs. This data allows it
to consolidate its knowledge of the radiological state of the environment.
Its main measurement results can be consulted via its environmental radioactivity
Internet portal, (http://environnement.irsn.fr).
Internet site: www.irsn.fr

French Nuclear Safety
Authority (ASN)

As part of its responsibilities defined in the
Nuclear Safety and Transparency Act (theTSN Act), ASN makes technical regulatory
decisions that apply to nuclear facility operators.

36

Within this context, it lays down radioactivity monitoring requirements concerning
nuclear sites and the areas surrounding them(excluding defense-related facilities).

Nuclear facility operators

These requirements are defined in ratified
decisions (and previously in ministerial
orders). ASN ensures that these requirements
are met, particularly by reviewing the monitoring records kept by operators, and by conducting inspections. Under the TSN Act, ASN
is responsible for organizing continuousradiation protection monitoring in France.
As part of its regulatory monitoring of
nuclear facilities, it also accredits laboratories
that measure environmental radioactivity.
Last, it assists the French Ministry of Healthin defining the technical requirements applicable to health inspections of the radiological quality of water intended for humanconsumption, and in accrediting
laboratories conducting control measures.
Internet site: www.asn.fr

Nuclear Safety Authority
for Defense-Related
Facilities and Activities(ASND)
With regard to defenserelated facilities and activities, the DSND, which
reports to the Minister ofDefense and the Ministerof Industry, is responsible
for reviewing effluent discharge and water intake permit applications,in accordance with the French Defense Code.
Requirements for environmental radiologicalmonitoring at these facilities are defined byministerial orders, based on the DSND report
after the operators' permit applications havebeen examined.
The two authorities, ASN and the DSND, consult on all issues that may have an impact on
effluent discharge and water intake permit
applications, and on environmental monitoring at sites accommodating civil and defense
facilities.

IRSN – Report on the Radiological State of the Environment in France 2010-2011

Nuclear facility operators are responsible formonitoring effluents discharged by theirfacilities and for environmental monitoringon and around nuclear sites. In general, thismonitoring activity is defined by the regulatory requirements laid down in discharge permits, which require operators to implementa regular environmental monitoring programat their sites (known as ‘regulatory’ monitoring). The radioactivity measurements on thesamples taken in this regard must be
conducted by certified laboratories.
This monitoring system, which is the responsibility of the nuclear site operator, is themain source of measurement results thatprovide a regular update on the radiologicalstate on these sites and within a few
kilometers of them.
Nuclear facility operators have laboratories
specializing in radiological monitoring thatsample and analyze air, soil and water samples.
Internet sites:www.areva.com
www.edf.fr
www.cea.fr
www.andra.fr
www.ill.fr
www.defense.gouv.fr/marine

IRSN • FOCUS

II.2
What are the main fuel cycle
facilities in France ?
Systematic environmental monitoring is
conducted at all fuel cycle facilities.
This cycle includes the following industrial
stages (Figure II.6):• extraction of uranium from mines (former
mining sites now managed by Areva);• concentration and conversion of uranium
compounds (Comurhex Malvési and
Pierrelatte);• isotope enrichment in uranium-235, a
process that involves increasing the concentration of a chemical element in one of
its isotopes (Eurodif and SET on the
Tricastin site);• fabrication of MOX fuel (Marcoule);• f u e l f a b r i c a t i o n a n d a s s e m b ly
(FBFC Romans-sur-Isère);• use in nuclear power plant reactors (EDF,
22 plants including 19 in operation,

representing a total of 58 pressurizedwater reactors);• processing of spent fuel removed fromreactors and recycling (Areva La Hague)and R&D in these areas (CEA Marcoule);• waste processing and disposal (Andra,
waste disposal facilities in the Manche
department and in Soulaines andMorvilliers).

CHEMITRY
ENRICHMENT
MINES

FUEL
PRODUCTION

REACTORSRECYCLING:
PRODUCTION OF MOX FUELWASTE DISPOSALSPENT FUELREPROCESSING

Figure II.6 - Simplified illustration of the nuclear cycle

IRSN – Report on the Radiological State of the Environment in France 2010-201137

Ministry directorates andgovernment agencies
in charge of healthinspections
These directorates and agencies are generally
responsible for conducting health inspections
on food (animal and vegetable foodstuffs anddrinking water) and animals intended forfood. This activity entails looking for chemical, physical and biological agents, including
radioactive substances, that could pose ahealth risk for the population.
The Directorate
General on Food
Safety (DGAL) prepares an annual planfor monitoring
potential radionuclide contaminationof foodstuffs (milkand dairy products,
eggs, meat, fish andseafood). The objective of this plan is to test
the radiological quality of foodstuffs, particularly food products from areas aroundnuclear facilities. Samples are taken on a
department-by-department basis by agentsfrom the Departmental Directorate for Social
Cohesion and Public Health and Safety(DDCSPP).
Internet site:www.agriculture.gouv.fr/alimentation

38

DGAL • FOCUS

THE NATIONAL ENVIRONMENTAL RADIOACTIVITY MEASUREMENT NETWORKAND STAKEHOLDERS INVOLVED IN MONITORING IN FRANCE

Monitoring of foodstuffs
by the DGALRadionuclides are addressed specifically inan annual monitoring plan. This was first set
up following the Chernobyl accident tocheck contamination levels in French food,then established on a permanent basis withthe cooperation of the AFSSA (now ANSES).
The plan was revised in 2008 with IRSN
involved as the national reference laboratory in the field. As such, the Institute orgaThe regulatory basis for health inspections nizes interlaboratory tests for laboratories
includes several European texts grouped certified by the DGAL to inspect the radiologtogether in a ‘health and safety package’. Its ical quality of foodstuffs, develops analyticalframework is EC Regulation No. 178/2002, methods and techniques, and provides thewhich sets out the overall principles and DGAL and the laboratory network with
instructions regarding food legislation, technical and scientific support.
establishes the European Food Safety
Authority and defines food safety proce- The radiological quality of a foodstuff is regdures. It includes the Community’s rapid ulated only in post-accident situations,alert system (RASFF, the Rapid Alert System starting with import inspections on foodfor Feed and Food), which allows immedi- stuffs potentially affected by the Chernobyl
ate communication among Member States and Fukushima accidents (EC regulationin the event of a health threat caused by an No. 733/2008 and EC regulation No.
operator or a country outside the EU, and 297/2011 respectively). Simultaneously,
all the tools available to the risk manager: Euratom Regulation No. 3954/87 sets thecontacts with the organization responsible maximum acceptable national levels of
for assessing food risks (EFSA at the Euro- radioactive contamination for foodstuffs
pean level, ANSES/IRSN at the national and animal feed after a nuclear accident, orlevel) based on its areas of expertise, the any other radiological emergency.
possibility of withdrawing/recalling products from the market, and/or notifying The prospective monitoring plan in placeaddresses two objectives: to increase
consumers.
knowledge regarding a reference contamiUnder this body of regulation, each EU nation level that could provide comparison
Member State may or must perform analy- values in the event of a nuclear accident
ses on certain foods. Every year, the DGAL and improved understanding of the actualsets up several dozen contaminant moni- impact on food; and to maintain an active
toring and inspection plans to track network of certified laboratories (ninechanges in contamination levels and con- departmental laboratories, overseen byfirm that a foodstuff complies with a regu- IRSN), capable of managing the quality andlatory standard (Figure II.7). The plans set quantity of the many analyses to be
out to confirm that operators are not undertaken in the event of emergency.
responsible for any fraud (addition of prohibited substances or presence of residues The plan addresses the monitoring of foodof veterinary drugs), non-observance of stuffs produced near nuclear facilities orhealth and safety standards (microbiologi- located in the area of persistent fallout from
cal contaminants), or inadvertent industrial the Chernobyl accident or previous atmoor natural contamination (mycotoxins, spheric tests, and the study of contaminaenvironmental contaminants such as heavy tion levels of products from across themetals or dioxins).
country (bulk milk) or products fromThe Directorate General on Food Safety(DGAL) of the Ministry of Agriculture, Food,
Fisheries, Rural Affairs and Town and Country Planning (MAAPRAT) is responsible forsafety inspections of animal feed and foodstuffs of animal origin and, for primary production (at the farming stage), of vegetable
foodstuffs.

IRSN – Report on the Radiological State of the Environment in France 2010-2011

II.2

coastal areas (fish, mollusks and crustaceans). It involves performing multi-radionuclide analysis (including cesium isotopes,
iodine and tritium) of some 700 annual
samples taken by the Departmental Directorates for Social Cohesion and Public
Health and Safety. The assessments show
very slight radiological traces, with the vast
majority of results below detection limits
and a few quantifiable results (particularly
for game in the areas where fallout
persists), but below the applicable standards in the event of accident. For example,
in 2010, quantifiable levels of cesium-137
were found in only two samples of milk, oneof honey, two of beef and eight of fish, at an
average of 0.07 Bq/kg, by comparison to
the regulatory limits of several hundred
Bq/kg. Only certain boar samples taken in
the areas where fallout persists show moremarked, although still slight, contamination levels, with a maximum of 50 Bq/kg
and an average of 12.43 Bq/kg (for seven of
the 58 samples taken).
All of the annual foodstuff monitoringassessments conducted by the DGAL may
be viewed at: http://agriculture.gouv.fr/dispositif%20-surveillance%20-controlesecurite-sanitaire-aliments-564

Residuesof veterinary drugs

Physical-chemical
contaminants

ImportAnimal feed

- Microbiology- Contaminants- Dioxins- PCB- Radionuclides- Mycotoxins

More than 60,000 samples
More than 100,000 analyses

Antibiotic resistanceMicrobiology
and toxins- Listeria- Salmonella- Lipophilic toxins

Figure II.7 - DGAL monitoring of foodstuffs

Plant careproducts

The Directorate forCompetition, Consumer Rights, andProtection Against
Fraud (DGCCRF)
has regularly
inspected the radioactive contamination of consumer products since 1986, theyear of the Chernobyl accident. These inspections primarily concern vegetable foodstuffs.
Every year, several hundred samples are takenfrom the domestic market at the productmarketing stage.
Internet site: www.economie.gouv.fr/dgccrf
Regarding water,
the Directorate
General for Health(DGS) ensures theprotection of the
public with regard tovarious uses ofwater (drinking water, water for recreation,
domestic hot water, bottled water and waste
water). As part of the health inspection activities assigned to them under the French Public Health Code, the Local Health and Social
Services Departments (DDASS) or Regional
Health Agencies (ARS), as they are now
called, have regularly inspected the radiological quality of water intended for human consumption since 2005

In February 2011, the French Nuclear
Safety Agency, the Directorate Generalfor Health and the Institute for Radiological Protection and Nuclear Safety published the results of the second annual
national assessment of the radiologicalquality of water distributed in public systems. Over the 2008-2009 period, theRegional Health Agencies (ARS) conducted 72,300 analyses at catchment or
on water available through public distribution systems, in accordance with theEuropean 98/83/EC directive. These controls are based on measuring four indicators: tritium, the activity of alpha- andbeta-emitting radionuclides and the total
indicative dose (exposure to ionizing radiation attributable to the ingestion ofwater over a one-year period).
For more informationwww.mesure-radioactivite.fr/public/IMG/
pdf/ASN_DGS_IRSN_Bilan-qualiteradiologique-eau-2008-2009.pdf
Internet site:www.sante.gouv.fr/eau-potable.html

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THE NATIONAL ENVIRONMENTAL RADIOACTIVITY MEASUREMENT NETWORKAND STAKEHOLDERS INVOLVED IN MONITORING IN FRANCE

Local authorities
Some local authorities,
especially the Conseils
Généraux (local government authorities at
department level), have
set up complementary
environmental monitoring networks, independent of industry andgovernment agencies, in departments where
significant nuclear activities are carried out.
Many Conseils Généraux, along with municipalities and metropolitan areas, rely on analytical laboratories to test the radioactivity ofvarious environmental samples (including
water, air, foodstuffs, soil and waste).
If these radioactivity measurements aretaken to meet legal or regulatory requirements, for example under the French Public
Health Code or the Environmental Code, theymust be conducted by certified laboratories
and their results published on the RNM
Internet site.

the auspices of the Ministry of the Environment. The air quality monitoring system
includes 40 approved associations, whichmake up the ATMO monitoring network. The
Environment and Energy Management
Agency (ADEME), is responsible for the technical coordination of this system, together
with the Ministry of the Environment. SomeAASQAs have sensors for monitoring environmental radioactivity, in general when
nuclear facilities are located in the region. Tenor so AASQAs are equipped with one or more
automatic continuous monitors that measureatmospheric radioactivity.
Internet sites:www.atmo-france.org/fr
www.ademe.fr

Non-profit associations

Local Information Commissions and Committees (CLI) were set up in the 1980s in areas
around most nuclear facilities at the initiativeof the Conseils Généraux, pursuant to a circular issued by the Prime Minister on December
15, 1981. The TSN Act strengthened the CLIs
by granting them legal status. Article 22 of
the Act provides for the creation of a CLI for
each basic nuclear installation (one CLI may
cover several facilities in the same area). The
CLIs, which form the French National Association of Local Information Commissions
and Committees (ANCCLI), are generally
concerned with monitoring, information andconsulting in the area of nuclear safety, radiological protection and the impact of nuclear
activities on humans and the environment.
The information they need to fulfill their mission comes from facility operators, ASN andother government agencies. They may haveassessments conducted or measurements
taken of environmental discharge from thefacilities concerned.
Internet site: www.anccli.fr

In France, various non-profit associations thatcome under the French Act of 1901 are also
involved in monitoring radioactivity in theenvironment. Some of them send data to the
RNM (e.g., Acro).
The Association for Radioactivity Monitoring in Western France (ACRO) and theCommission for Independent Researchand Information on Radioactivity(CRIIRAD), created in 1986 following theaccident in Chernobyl, have their own radioactivity measurement laboratories and publish their results. They mainly work for local
authorities, environmental organizations, laboratories and producer and consumer organizations.
Internet sites:www.acro.eu.org
www.criirad.org
The Approved Air Quality Monitoring
Associations (AASQA) operate and develop
a national network of measurements of thephysical-chemical quality of the air, under

40

IRSN – Report on the Radiological State of the Environment in France 2010-2011

© Noak/Le bar floréal/IRSN

II.2

Figure II.8 - Grass sampling
IRSN – Report on the Radiological State of the Environment in France 2010-201141

Events and Specific Assessments

42

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III
Eventsand Specific
Assessments
III.1 M onitoring the impact of the Fukushima accident on France(metropolitan France and French overseas departments, regions
and communities)
III.2 Accidental tritium contamination at Saint-Maur-des-Fossésand Bondoufle, near Paris
III.3 IRSN assessments on the
Orflam-Plast site in Pargny-sur-Saulx in northeastern France[© French Navy]

III.4 R
 adioactive releases associated with natural events

Events and Specific Assessments

III.1 Monitoring
the impact of
the Fukushima
accident on
France (metropolitan Franceand Frenchoverseas
departments,
regions andcommunities)
Introduction
In order to monitor the radiological impact
on France of the Fukushima Daiichi accident
on March 11, 2011, IRSN stepped up environmental radioactivity monitoring in metropolitan France and in French overseas
departments, regions and communities. The
purpose of this enhanced monitoring was toconfirm and quantify the expected presencein the atmosphere of radioactive elements inthe form of particles in suspension (aerosols)and gaseous radioactive iodine (especially
iodine-131), and to monitor their fate in theenvironment and their possible impact on thefood chain (via rainwater, grass, leafy vegetables or milk). The collaboration of many institutional partners across France ensured that
this enhanced monitoring was conductedunder optimum conditions.
Moreover, the French Nuclear Safety Authority (ASN) also asked operators of basic
nuclear installations, who already continuously carry out regulatory radioactivity monitoring in the vicinity of their facilities, toperform additional measurements for the
purpose of detecting any airborne artificial
radionuclides, attributable to the accident.
Over a period of six weeks, this yielded a
total of:• more than 5,700 measurement resultsfrom IRSN, from approximately 1,400 samples (all types);• more than 3,000 measurement resultsfrom nuclear operators and associations.

Description of the enhanced
monitoring program

All of these monitoring results were analyzed
by IRSN in real time and posted on a dedicated website. Between March and May
2011, the authorities and the public therefore
had access to the latest information (daily at
first and then at less regular intervals) on theradiological situation in France.
Since early May 2011, concentrations of artificial radionuclides have returned to levels
close to the decision thresholds and theenhanced monitoring programs have beensuspended.

IRSN's enhanced monitoring program
involved putting the Teleray monitoring
network on alert, taking specific environmental samples at more frequent intervals,
and installing environmental dosimeters at
various sites in France.
To set up certain equipment and carry out
environmental sampling, IRSN sought thehelp of local contacts in the French meteorological institute, Météo-France, theNational Gendarmerie and some nuclear
operators, as well as decentralized government departments in metropolitan France(Departmental Directorates for Public Healthand Safety – DDPP) and in the French overseas departments and regions (Directoratesof Food, Agriculture and Forestry – DAAF).
This was done with the agreement and on
the instructions of the Directorate General on
Food Safety (DGAL).

At the same time, nuclear operators havecontinued the regulatory monitoring requiredof them and associations have also done
their part to remain vigilant by carrying out
sampling campaigns. This chapter takes into
account these results, which focus on theterrestrial compartment.
Lastly, IRSN published a detailed report(IRSN-DEI 2011-01) on its website in late
January 2012 analyzing the impact of the
Fukushima accident on France: http://www.
irsn.fr/FR/expertise/rapports_expertise/Documents /environnement /IRSN_Analyseimpact-Fukushima-France_012012.PDF

The maps in Figures III.1 to III.3 provide an
overview of IRSN's enhanced monitoring system, set up to provide optimum coverage ofFrench territory in order to assess the radiological impact of air masses contaminated by
the Fukushima accident.

Saint Pierre and Miquelon

Metropolitan France

T

T

AS D

P

V

AS D

R

P

V

R

L

Saint Barthélémy
R

GuadeloupeTD

French Polynesia
T

AS D

P

V

R

P

Martinique
T

V

AS D

R

P

V

L

French Guiana

Mayotte

T

D

R

R

P

V

L

RéunionR

L

French overseas communities
French overseas departments & regions

T

D

R

New Caledonia

P

V

L

T

D

R

P

V

L

Teleray sensor (continuous measurement of
ambient gamma dose rate)
AS Aerosol sampler with iodine-trapping
cartridge
D Thermoluminescent dosimeter (TLD)
R Radiophotoluminescent dosimeter (RPL)P Sampling of rainwater
V Sampling of plants(grass, vegetables, land mosses)
L Sampling of milk
T

Figure III.1 - Overview of the IRSN systems set up in French overseas departments, regions andcommunities to monitor the impact of the Fukushima accident.

44

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III.1Throughout the period during which thiscontamination was measured, the monitoring program was constantly adapted to thechanging situation in Japan and to theresults obtained. Milk and plants were initially sampled two to three times a week,
but this was gradually reduced to once aweek right across France. After April 25,
given the general downward trend in activity levels measured in the environment, thenumber of monitoring points was also scaled
down.
Once airborne activity had returned to virtually the same levels as those measured
prior to the accident, the bulk of the specificprogram put in place by IRSN was discontinued as of May 6. Most of the environmental
dosimeters were analyzed on or after thisdate. For the purpose of research, specificsamples - mainly of meat - neverthelesscontinued to be taken.

Atmospheric monitoring
Type of monitoring
Teleray
RPL dosimeter
Rainwater
OPERA-Air Low-volume
with iodine trapping cartridge
OPERA-Air High-volume

As well as the actions mentioned above,
ASN asked nuclear operators to performmeasurements on air samples in order tolook for trace levels of artificial radionuclides
attributable to the accident.

Figure III.2 - Location of the atmospheric compartment monitoring systems usedby IRSN to monitor the consequences in metropolitan France of the accident
at the Fukushima Daiichi nuclear power plant.

Pas-de-CalaisThis special monitoring, which complemented the usual regulatory monitoring,
comprised:• a daily gamma spectrometry measurement performed on the geographically distributed cluster of aerosol sampling filters,
for the purpose of detecting artificial radionuclides, aiming for a decision threshold1
lower than 0.1 mBq/m3 (for cesium-137);• a gamma spectrometry measurement ofgaseous radioactive iodines sampled onan activated carbon cartridge at intervalsof 24 to 72 hours.

L
V
L
V

MancheL
V

Ardennes
YvelinesIlle-et-Vilaine
L

L

Mayenne

L

V

V

V

Indre-et-Loire

L

Doubs

L

V

V
V

VendéeL

Puy-de-Dôme

V

LV

Lot-et-Garonne

ArdècheL

Pyrénées-AtlantiquesV

Haut-Rhin

L
V

L

L

Vosges

L

V

V
L
L

Aude

V

Alpes-Maritimes

Bouches-du-Rhône

Hautes-Pyrénées
V

L
V

V

L

Savoie L
Isère
V

L
V

L

Haute-Corse V

Monitoring of the terrestrial compartment
L Sampling of milk (from cows, goats or sheep)
V Sampling of plants (grass or leafy vegetables)

Figure III.3 - Places where milk and plant samples were taken specifically as part of IRSN's efforts tomonitor the consequences in France of the accident at the Fukushima Daiichi nuclear power plant.

1 – The metrological decision threshold is theminimum counting value obtained while measuring
a sample, above which the presence of radioactivity inthe sample can be concluded, with an acceptable riskof error.

IRSN – Report on the Radiological State of the Environment in France in 2010-201145

Events and Specific Assessments

In all, 36 nuclear sites (EDF, Areva, CEA,ANDRA and ILL) took part in this additional
monitoring (Figure III.4).
In addition to the measurements submitted
by basic nuclear installation operators, thefour French Navy bases (Cherbourg, Brest, ÎleLongue and Toulon) also provided information, specifically gamma spectrometry dataon atmospheric aerosol filter samples, gaseous iodine-trapping cartridges, andrainwater and grass samples.

In view of the changing environmental situation in France, ASN eased its additional monitoring requirements for operators with effectfrom April 18:• a weekly gamma spectrometry measurement performed on the cluster of daily
aerosol sampling filters, aiming for a decision threshold lower than 0.01 mBq/m3 forcesium-137;• a gamma spectrometry measurement ofgaseous iodines sampled on a cartridge at
one-week intervals.

The Bordeaux-Gradignan nuclear research center also sent IRSN its gamma spectrometry
analysis results.

On May 4, ASN asked the nuclear operators
to stop additional monitoring, as it was nolonger justified given the steady decline inlevels of airborne artificial radionuclides.

Gravelines
Chooz

Penly
CSM waste disposal facility
La Hague site

PaluelCherbourg
Flamanville
Seine
Fontenay-aux-Roses
SaclayBrest
Brennilis
Saint-Laurent-des-EauxÎle Longue
Loire

ChinonCattenom

Meuse

MoselleNogent-sur-Seine
Soulaines Rhin
Dampierre-en-Burly

Fessenheim

Belleville-sur-Loire
VienneCivauxLoire

Le Bugey

Saint-Alban

Le Blayais

Rhône

Dordogne
Tricastin
Marcoule

GolfechGaronneCreys-Malville
Grenoble
Cruas-Meysse
Tricastin (Pierrelatte)
PhénixCadarache

MalvésiToulonUranium enrichment (Eurodif Tricastin)
Uranium conversion (Comurhex Malvési and Tricastin)
Spent fuel processing, radioactive waste conditioning(Areva La Hague, CEA Marcoule)
Nuclear power plants (22 EDF sites, of which 19 in operation)
Surface disposal of radioactive waste (ANDRA; CSM and Soulaines waste disposal facilities)
Nuclear naval bases operated by the French Navy
Nuclear research centers (CEA and ILL Grenoble)

Figure III.4 - Location of the nuclear sites that participated in additional monitoring of airborne
radioactivity after the Fukushima accident.

Results ofenhanced atmosphericmonitoring
Measurement resultsfor iodine-131 in aerosols
In metropolitan France, all measurement
results obtained on air samples taken up to
March 23 were below the decision thresholdsof the analysis techniques used, and were
between less than 0.01 and 0.05 mBq/m3.
Traces of particulate iodine-131 weredetected for the first time in an aerosol sample collected between March 21 and 24 at avery high-volume IRSN sampling station,
located on the summit of Puy-de-Dôme insouth-central France, at an altitude of
1,465 m (activity concentration estimated at
0.04 mBq/m3 with the activity measured
being normalized to a single day, i.e.
March 24). The other measurement results
obtained on daily samples taken on March 24
were all below the decision thresholds (nineIRSN samplers and 25 nuclear operator samplers, representative of the whole country).
Further results in the days that followed confirmed that particulate iodine-131 had been
detected nationwide. The average activity
concentrations over the sampling period
peaked in metropolitan France between
March 27 and April 9 (Figure III.5), with values
sometimes reaching 1 to 2 mBq/m3 in different regions of the country. After this date, theactivity fell to levels lower than 0.01 mBq/m3
by early May.
With regard to the French overseas departments, regions and communities, particul a t e i o d i n e - 1 3 1 wa s d e t e c t e d a t
Fort-de-France in a sample collected between
March 24 and 31 (0.21 mBq/m3), and also on
Saint Pierre and Miquelon in a sample collected between March 25 and April 1(0.48 mBq/m3). Significant values continued
to be observed at Fort-de-France until
April 14 (0.15 mBq/m3), and on Saint Pierre
and Miquelon until April 22 (0.28 mBq/m3).

Measurement results for gaseousiodine-131 trapped on activatedcarbon cartridges
In metropolitan France, all measurement
results obtained from sampling up to March
25 were below the decision thresholds of theanalysis techniques used (Figure III.6).

46

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III.1In the case of the French overseas departments, regions and communities, significant
gaseous iodine-131 activity levels were measured only on Saint Pierre and Miquelon, in asample collected between March 26 and 28(0.81 mBq/m3 and in several two-day samples collected between April 1 and 19 (average values between 0.12 and 4.8 mBq/m3).

Comparison with historicallevels measured in France

mBq/m3
2.5

2

1.5

1

0.5

0

No activity detectedin the 65 samples
analyzed by IRSN

11/3
13/3
15/3
17/3
19/3
21/3
23/3
25/3
27/3
29/3
31/3
2/4
4/4
6/4
8/4
10/4
12/4
14/4
16/4
18/4
20/4
22/4
24/4
26/4
28/4
30/4
2/5
4/5
6/5

Iodine-131 in gaseous form was detected forthe first time in samples collected between
March 24 and 26 at Cherbourg and Cadarache (a few tenths of a mBq/m3). During thenext few days, further traces of gaseousiodine-131, with activity concentrations
between a few tenths and a few millibecquerels per cubic meter, were detected
throughout metropolitan France. Peak activity concentrations were measured in samples
collected between March 28 and April 8 (17values between 3 and 7.4 mBq/m3). From
April 25 on, the activity concentrations measured were below the decision thresholds. All
significant measurements (above the decision threshold) obtained in metropolitan
France during the whole monitoring period
are shown in the previous figure, with theresults corresponding to the last sampling
date.

Significant operator result
Significant IRSN result

Figure III.5 - Iodine-131 activity concentrations measured in aerosols in metropolitan France (mBq/m3).

mBq/m38

6

4

Normally, no iodine-131 can be detected in
the atmosphere. Only significant releases asa result of an incident or accident may cause
measurable concentrations, as was the caseafter the Chernobyl accident in 1986 or, more
recently, following a release from a Hungarian plant producing radionuclides forpharmaceutical purposes.

2

By way of comparison, the iodine-131 activity levels measured during the second half ofMarch and early April 2011 were 1,000 to
10,000 times lower than those measured inwestern Europe in the days following theChernobyl accident. This mainly concerns theparticulate fraction of iodine-131 , as, at thattime, few measurements of the gaseous
fraction were carried out.

Figure III.6 - Gaseous iodine-131 activity concentrations measured in metropolitan France (mBq/m3).

No activity detectedin the 7 samples
analyzed by IRSN

No activity detectedin the 23 samples
analyzed by IRSN

11/3
13/3
15/3
17/3
19/3
21/3
23/3
25/3
27/3
29/3
31/3
2/4
4/4
6/4
8/4
10/4
12/4
14/4
16/4
18/4
20/4
22/4
24/4
26/4
28/4
30/4
2/5
4/5
6/5

0

Significant operator result
Significant IRSN result

IRSN – Report on the Radiological State of the Environment in France in 2010-201147

Events and Specific Assessments

Measurement results for
cesium-134 and -137 in aerosols
Traces of cesium-134 and cesium-137 weredetected in different locations in France atlevels about ten times lower than those ofiodine-131 (Figure III.7). The activity ratio
between the 134 and 137 isotopes of cesium
measured in aerosols was calculated to beclose to 1.

mBq/m3
0.3
0.25
0.2
0.15
0.1

No cesium-134 had been measured in theatmosphere since the mid-1990s due to its
relatively short half-life (2.1 years), resulting
in its rapid disappearance. Before the Fukushima accident, cesium-137 could be measured in the atmosphere in France, at a levelin the region of 0.1 to 0.2 µBq/m3, using
sampling stations equipped with powerful air
intake systems (300-700 m3/h).
The cesium-137 activity levels measured
after the Fukushima accident were 10,000 to
100,000 times lower than the highest values
recorded in France in the days following theChernobyl accident, which corresponded toa million-fold increase in the ambient value
at that time (approximately 1 µBq/m3). Furthermore, the releases as a result of the Chernobyl accident had a lasting effect on theactivity levels in the atmosphere since, eventhough the level of cesium-137 fell very
quickly in the days and weeks following thearrival of contaminated air masses in France,
due to fallout in rain and the effect of dispersion, it took well over ten years for it toreturn to the level measured in the days
before the accident.
Cesium-137 release caused by the Fukushima
accident (less than 10% of that occurring in
the wake of the Chernobyl accident) and its
dispersal over a distance of more than
10,000 km increased the ambient level inFrance only by a factor of 1,000 comparedwith the level during the few days prior to
the accident. These quantities were clearly
not sufficient to replenish the levels of atmospheric cesium-137 since, by October 2011,
i.e. five months after the accident, the ambient level of cesium-137 in the atmospherealready represented just twice the levelmeasured before the accident.

48

0.05
0

No activity detectedin the 114 samples
analyzed by IRSN

11/3
13/3
15/3
17/3
19/3
21/3
23/3
25/3
27/3
29/3
31/3
2/4
4/4
6/4
8/4
10/4
12/4
14/4
16/4
18/4
20/4
22/4
24/4
26/4
28/4
30/4
2/5
4/5
6/5

Comparison with historicallevels measured in France

Significant operator result
Significant IRSN result
Figure III.7 - Cesium-134 activity concentrations measured in the atmosphere in metropolitan
France (mBq/m3).

Results of monitoring ambient
dose rate (Teleray network)
To illustrate the absence of any significant
increase in the ambient gamma dose equivalent rate, the graphs in Figure III.8 show thetrends over time in the regional average dose
200
180
160
140

Dose rate in nSv/h
North-Eastern France
AlsaceFranche-Comté

Lorraine
Champagne-Ardenne

rate for northern, northeastern, northwestern,
central, southeastern and southwesternFrance. Each curve represents the average ofthe hourly measurements from each of thesensors set up in the French administrative
regions.

200
180
160
140

Dose rate in nSv/hSouth-Western France
Aquitaine
Languedoc-Roussillon

Midi-Pyrénées
Poitou-Charente

120
100

120
100

80
60
40
10/03 14/03 18/03 22/03 26/03 30/03 05/04 09/04 13/04 17/04

80
60
40
10/03 14/03 18/03 22/03 26/03 30/03 05/04 09/04 13/04 17/04

Dose rate in nSv/hCentral France
200
Auvergne
Limousin
180
CentreBourgogne
160
140
120
100
80
60
40
10/03 14/03 18/03 22/03 26/03 30/03 05/04 09/04 13/04 17/04
Dose rate in nSv/h
North-Western France
200
Bretagne
Pays-de-la-Loire
Picardie
180
160
140
120
100
80
60
40
10/03 14/03 18/03 22/03 26/03 30/03 05/04 09/04 13/04 17/04

Dose rate in nSv/h
Northern France
200
Basse-Normandie
Haute-Normandie
180
Nord-Pas-de-Calais
Île-de-France
160
140
120
100
80
60
40
10/03 14/03 18/03 22/03 26/03 30/03 05/04 09/04 13/04 17/04
Dose rate in nSv/hSouth-Eastern France
200
Corse
Provence-Alpes-Côte-d’Azur
Rhône-Alpes
180
160
140
120
100
80
60
40
10/03 14/03 18/03 22/03 26/03 30/03 05/04 09/04 13/04 17/04

Figure III.8 - Regional averages (per French administrative region) of the hourly measurementsfrom the Teleray sensors, with metropolitan France divided into six large zones (nSv/h).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III.1
These results show minor fluctuations (ofabout 10 nSv/h), comparable with those usually observed by the Teleray network, due tothe behavior of natural radionuclides in theatmosphere, e.g. radon and its decay products, during changing weather conditions.

Bq/kg wet weight
16
14
12
10

In any event, the artificial radionuclide activity levels observed in France after the Fukushima accident, which were a few mBq/m3 at
most, cannot be the cause of theseoccasional regional fluctuations.

8
6
4
2

Enhanced monitoring of the land environment primarily focused on analyzing samplesof plants (grass, moss/lichen mixture andleafy vegetables) and milk. In the discussion
below, where the measurements were carriedout more than 15 days after sampling, any
non-significant results (those below the decision thresholds) obtained from these samples
were disregarded and are not shown on thegraphs, because of the short radioactive halflife of iodine-131 (8 days).

Measurement resultsfor iodine-131 in grass,mosses and lichens
A total of 226 samples of plants (grass, moss/lichen mix) were specifically analyzed by
IRSN, and a further 33 by the Association forRadioactivity Monitoring in Western France(ACRO) and the Manche department analytical laboratory (LDA 50). The nuclear operators also contributed by carrying out theirown regulatory environmental monitoring
and by occasionally collecting additional
samples (Figure III.9).
In metropolitan France, the first traces ofiodine-131 were measured in a grass sample
taken in Pélussin in central France on March
26 (0.09 Bq/kg wet weight). This became
more widespread in the days that followed,
detected at activity levels between 0.29 and
15 Bq/kg wet weight, with average activity
levels of about 2.08 Bq/kg wet weight overthe period from March 26 to April 15. The
highest activity was observed in a grass sample collected on March 28 in Gradignan, near
Bordeaux.

0
11/3
13/3
15/3
17/3
19/3
21/3
23/3
25/3
27/3
29/3
31/3
2/4
4/4
6/4
8/4
10/4
12/4
14/4
16/4
18/4
20/4
22/4
24/4
26/4
28/4
30/4
2/5
4/5
6/5

Results of enhanced
monitoring of the land
environment

Decision threshold
Significant IRSN result
Significant operator result
Significant ACRO and LDA 50 result

Figure III.9 - Iodine-131 activity measured in grass in metropolitan France by IRSN, nuclear operators and various associations between early March and early May 2011 (Bq/kg wet weight).

After April 15, the iodine-131 activity levels
in grass showed a downward trend. The values measured from early May on did notexceed 0.12 Bq/kg wet weight and were frequently below the decision thresholds of themeasuring equipment.
Analysis of the data acquired based on a geographical division of France (north/south andeast/west) indicates that activity levels of asimilar magnitude were observed right acrossFrench territory, albeit with some geographical and chronological fluctuations due to the
movements of the air masses. The variationin activity levels observed may also be
related to that observed in precipitations
causing deposits in the soil and to the variability of sampling. Based on these findings,
it cannot be concluded that some French
regions were more affected than others, as
was expected, given the global dispersion of
the radionuclides released during the
Fukushima accident.

Miquelon. Iodine-131 was not detected in
the other French overseas departments,
regions and communities of French Guiana,
Réunion, Tahiti and New Caledonia.

Measurement results for cesium
isotopes
A total of 43 grass samples collected in metropolitan France were found to have significant cesium-134 activity levels attributableto releases from the Fukushima Daiichi
nuclear power plant. The values ranged
between 0.07 and 2.79 Bq/kg wet weight.
Cesium-137, associated with cesium-134 orotherwise, was also measured at several sampling stations in metropolitan France, withactivity levels of between 0.04 and 4.7 Bq/kg
wet weight, i.e. values that were often
observed pre-Fukushima due to the persistence of this radionuclide, which was deposited following atmospheric nuclear tests andthe Chernobyl accident.

In the French overseas departments,
regions and communities, analysis of a grasssample collected on March 28 in Martiniquefound iodine-131 for the first time, with a
specific activity of 0.80 Bq/kg wet weight.
Traces of iodine-131 were also detected in
the next few days on Guadeloupe in two
grass samples, and in five samples of moss/lichen mixtures taken on Saint Pierre and

IRSN – Report on the Radiological State of the Environment in France in 2010-201149

Events and Specific Assessments

1.2

Overall, the activity measured is similar fromone place to another and, at the same location, the cesium-134 or cesium-137 activity
is generally ten times lower than that ofiodine-131.

Bq/kg wet weight1
0.8

Looking at the specific activity of theseradionuclides over time, observed at thesame sampler in southwestern France, there
is an activity peak in grass around April 6(Figure III.10).

0.6
0.4

The activity ratio of cesium-134 tocesium-137 measured in grass is close to 1
(Figure III.11).

0.2

Cesium-134

29/4

27/4

25/4

23/4

21/4

19/4

17/4

15/4

13/4

11/4

9/4

7/4

5/4

3/4

1/4

30/3

28/3

26/3

24/3

0

Cesium-137

Figure III.10 - Variation in activity levels of cesium-134 and cesium-137 measured in grass
at Sainte-Colombe-en-Bruilhois (southwestern France) in March and April 2011 (Bq/kg wet weight).

137

Cs (Bq/kg wet weight)

5
4.5

Some plant samples only had significant
cesium-137 activity, measuring about
10 Bq/kg wet weight (13.8 Bq/kg wet weightfor one land moss sampled on Saint Pierre
and Miquelon on March 29). Since nocesium-134 was detected, these activity levels
cannot be attributed to the accident at the
Fukushima nuclear power plant, and are
explained by the persistence in the soil (and inplants growing in the soil) of cesium-137,
deposited following atmospheric nuclear tests.

4
3.5
3
2.5
2
1.5
1
0.5
0

In the French overseas departments,
regions and communities, only two samplesof plants (mixtures of mosses and lichens),
collected on Saint Pierre and Miquelon, were
found to have significant combined
cesium-134 and cesium-137 activity levels,
attributable to releases resulting from the
Fukushima accident.

00.5
Operator data

1
IRSN data

1.5

2

2.5

3

3.5

134Cs (Bq/kg wet weight)

Figure III.11 - Correlation of activity levels of cesium-134 and cesium-137 measured in grasssamples taken between March 18 and May 6, 2011.

Analyses carried out
on vegetables and herbs
More than a hundred vegetables were monitored in metropolitan France and Frenchoverseas departments, regions and communities (leafy vegetables such as lettuce andspinach) and, to a lesser extent, other typesof vegetables and herbs (headed cabbage,celeriac, carrots and thyme).
The first traces of iodine-131 (0.14 Bq/kg
wet weight were detected on March 28 on
spinach leaves sampled in the municipalityof Narbonne in southern France. Further significant values were subsequently measured
in metropolitan France, mainly on lettuce
and spinach samples collected in the southeast of the country. Up until April 19, theactivity levels measured varied between 0.05
and 2.10 Bq/kg wet weight (Figure III.12).

50

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III.1

No significant iodine-131 or cesium activity
was measured in the 11 lettuce samples collected on Guadeloupe. In the other Frenchoverseas departments, regions and communities, radiological monitoring concerned only
samples of milk and grass, and of mosses andlichens in the case of Saint Pierre and Miquelon.

Analyses of milk
IRSN, nuclear operators and the Manche
department analytical laboratory (LDA 50)
analyzed more than 200 samples of milk
(from goats, sheep and cows) between March
18 and May 5, 2011.
Beginning on March 28, iodine-131 wasdetected in the north-west of France(0.43 Bq/L in goat's milk in Sepmes and0.15 Bq/L in cow's milk in Les Brouzils). In thedays that followed, significant activity levels
were detected at most of the sampling stations in metropolitan France, with levels varying between 0.05 and 3.10 Bq/L. The highest
levels were observed in goat's and sheep's
milk, with values between 0.06 and3.10 Bq/L, while the activity range measured
in cow's milk was 0.05 to 0.66 Bq/L.
From mid-April on, activity levels fell in metropolitan France, and by early May, only
goat's milk contained significant levels, lower
than 0.2 Bq/L (Figure III.13). After April 22,
the amount of iodine in cow's milk could nolonger be quantified. Note that, following theChernobyl accident in April 1986, theiodine-131 activity levels measured in France
in milk samples taken in May 1986 ranged
from 100 to 600 Bq/L.

Bq/kg wet weight

2
1.5
1
0.5
0
11/3
13/3
15/3
17/3
19/3
21/3
23/3
25/3
27/3
29/3
31/3
2/4
4/4
6/4
8/4
10/4
12/4
14/4
16/4
18/4
20/4
22/4
24/4
26/4
28/4
30/4
2/5
4/5
6/5

Cesium-134 was only detected four times, inspinach sampled on April 4 in Tourdan andBollène, both in the south-east,
and in thyme sampled in Ginasservis andHerqueville, in south-eastern and northwestern France, respectively. The activity levels recorded were low, between 0.05 and0.34 Bq/kg wet weight.

2.5

Decision threshold
Significant IRSN result (lettuce-all varieties)
Significant IRSN result (headed cabbage)
Significant IRSN result (spinach)
Significant IRSN result (celeriac)

Significant operator result (carrots)
Significant operator result (lettuce-all varieties)
Significant operator result (headed cabbage)
Significant operator result (thyme)

Figure III.12 - Iodine-131 activity measured in vegetables and herbs grown in metropolitan France
between early March and early May 2011 (Bq/kg wet weight).

3.5

Bq/L

3
2.5
2
1.5
1
0.5
0
11/3
13/3
15/3
17/3
19/3
21/3
23/3
25/3
27/3
29/3
31/3
2/4
4/4
6/4
8/4
10/4
12/4
14/4
16/4
18/4
20/4
22/4
24/4
26/4
28/4
30/4
2/5
4/5
6/5

Analyses conducted after this date showedthat there was no longer any significant
activity in metropolitan France. By way ofcomparison, after the Chernobyl accident, themaximum iodine-131 activity observed in
lettuce in France ranged from 300 to
3,000 Bq/kg wet weight in May 1986.

Decision threshold
Significant IRSN result (sheep's and goat's milk)
Significant IRSN result (cow's milk)
Significant operator result (goat's milk)
Significant operator result (cow's milk)

Figure III.13 - Iodine-131 activity measured in milk in metropolitan France between mid-Marchand early May (Bq/L).

Only three samples had very low cesium-134
activity levels (maximum of 0.1 Bq/L for the
sample taken in Sepmes on April 7, 2011.
Traces of cesium-137 were measured in several samples due to the persistence of
cesium-137 deposited following atmosphericnuclear tests and the Chernobyl accident.

As regards the French overseas departments,
regions and communities, significant
iodine-131 activity levels (maximum
0.27 Bq/L) were found in only three samples
of cow's milk collected in French Guiana. No
significant activity was detected elsewhere inthese regions during this period.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

51

ACRO • FOCUS

Events and Specific Assessments

Monitoring of plant cover in France
set up after the Fukushima accident
As soon as the arrival of radioactive gas
a n d p a r t i c le s f r o m J a p a n w a sannounced, the Association for Radioactivity Monitoring in Western France(ACRO) began organizing the task ofmonitoring fallout in metropolitan
France. Volunteers took grass samples
methodically and regularly at various
locations throughout the national territory for analysis purposes. The objective was to find out whether the foodchain might be affected (Figure III.14).

these changing contamination levels, a
third campaign took place between April 8
and 13. During this third week, cesium-134
was detected in Puy-de-Dôme and Girondein south-central and southwestern France,
respectively. As with radioactive iodine,cesium-134 (and most likely associatedcesium-137) originated from releases
from the Fukushima plant. A fourth campaign was organized in May 2011. This time
no iodine-131 was detected andcesium-137 was found on only one site.

The first sampling campaign was carriedout between March 27 and 31, 2011 (Figure III.15). After radioactive iodine(iodine-131) was detected in the plant coverin some places, a second campaign wasorganized a week later, which confirmed
its presence nearly everywhere within
French territory at levels higher than thosemeasured during the first campaign. Given
the situation in Japan and in order to track

Why is grass so important?
Plant cover, especially grass, is first to beaffected by atmospheric deposition.
Accordingly, radiological analysis of plant
samples by gamma spectrometry often
provides more information about the overall situation than direct analysis of the air
mass. By monitoring grass that cows, sheep
and other livestock will graze on, any
impact on the food chain (particularly meatand milk) can be anticipated. This type ofmonitoring also makes it possible to findout more about the potential level of contamination of leafy vegetables, such as lettuce, for example. To sum up, organizing
plant cover monitoring yields data about
actual radioactive fallout and enables apreventive estimate to be made of therisk associated with eating various
foodstuffs.

What protective measures wereneeded?
The contamination levels measured during
this evaluation period remained low,requiring no food restriction measures.
ACRO simply advised consumers to wash
leafy vegetables, even though this is only
effective up to a point. However, although
this contamination may be relatively low
level, it is not normal and should not be
trivialized.
Samples were taken by volunteers fromvarious associations in accordance with astrict, codified approach to ensure reliable
analyses. Sampling was preferably carriedout in places well away from trees, hedges
and houses. At each site, a sufficient number of surface area units were collected tomeet analysis requirements. At the ACRO
laboratory, the wet samples were qualitatively and quantitatively analyzed by
gamma spectrometry as soon as possible.

Figure III.14 - Samples of grass were taken by ACRO as part of its campaign to monitor
plant cover in France in the wake of the Fukushima accident.
Evaluation from March 27-31, 2011

Non-detectable contamination

Evaluation from April 3-7, 2011

Measured contamination (iodine-131)

Figure III.15 - Evaluation of iodine-131 contamination of grass between March 27 and April 13, 2011.

52

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Evaluation from April 8-13, 2011

III.2

Figure III.16 summarizes the changes overtime observed in tritium concentrations inwater vapor in the air of the 2M Processbuilding, in the premises adjacent to thiscompany's site and in the courtyard of 2M
Process between November 25, 2010 and
February 1, 2012.

As from March 16, 2011, IRSN cut back its
monitoring to take into account the measures implemented by CEA in response to

It can be seen that the activity levels fell bya factor of 100 between mid-November
2010 and mid-July 2011, in connection withthe various decontamination operations. During the last quarter of 2011, the tritium activity of the plant bubbler decreased seven-fold(from 1,410 Bq/m3 on September 7, 2011 to
186 Bq/m3 on February 1, 2012).

Bq/m3
100,000

10,000

1,000

100

10

1

Adjacent building 1

2M Process upper-floor office

2M Process courtyard

1/2/2012

7/1/2012

18/11/2011

24/10/2011

4/9/2011

2M Process plant

29/9/2011

10/8/2011

16/7/2011

21/6/2011

2/5/2011

27/5/2011

7/4/2011

13/3/2011

16/2/2011

22/1/20110.1
28/12/2010

At the request of the French Nuclear Safety
Authority (ASN), IRSN staff arrived at SaintMaur-des-Fossés the next day to carry out an
initial characterization of the tritium contamination of the company premises and theimmediate vicinity. Early results revealed significant contamination of the premises andclear traces in samples taken very close(within a few meters) to the company site.
These initial findings prompted IRSN to conduct several investigations, once again at therequest of ASN:
• tritium measurements on samples of water,
air and plants collected in the vicinity of thecompany building, in order to ascertain thesignificance and extent of the environmental traces found and to monitor changes
over time;• measurements of tritium in the urine of
local residents living close to the 2M Processbuilding. The results showed traces of tritium
in some samples but the evaluations performed by IRSN based on these results produced extremely low dosimetric estimates,with no associated health risks for these
individuals;

IRSN's environmental monitoring activities in2010 and 2011 were conducted in parallelwith CEA's cleanup operations in the 2M Process building on and after November 9, 2010.
Cleanup proceeded in several stages, under
the supervision of ASN and the Val-de-Marne
prefecture: removal of the most contaminated objects, i.e. the main sources of tritium
emission (November 9-10, 2010), disposal ofplant equipment (November 30 to December
3, 2010) removal of casework and carpets(December 8-10, 2010), and cleaning of surfaces (December 2010 and early January).

3/12/2010

On November 3, 2010, CEA informed thenuclear safety authorities that an employee
of one of its outside contractors (2M Process
based in Saint-Maur-des-Fossés, near Paris)
had been found to be contaminated with tritium during routine screening on the Valducsite in eastern France. The contamination was
due to the presence, in one of the company's
buildings, of an experimental device comprising a molecular sieve, which had come fromthe CEA Valduc site and had been wrongly
assumed not to contain tritium. This experimental equipment had previously been used
for tests on the Études et Diffusion site in
Bondoufle, south of Paris.

administrative order no. 2010/7819 ofDecember 15, 2010. Under the terms of thisorder, IRSN periodically received the results
obtained by CEA and was tasked with interpreting them, in particular comparing themwith its own measurement results.

8/11/2010

III.2 Accidental
tritium
contamination
at Saint-Maurdes-Fossés andBondoufle,
near Paris• d osimetric evaluations of the exposure totritium of 2M Process employees and visitors on the Saint-Maur-des-Fossés and Bondoufle sites, and investigation of tritium
remaining on the premises of Études et Diffusion in Bondoufle.

Adjacent building 2
Figure III.16 - Summary of tritium activity in water vapor in air measured
at Saint-Maur-des-Fossés between November 2010 and February 2012 – IRSN and CEA measurements(NB logarithmic scale).

IRSN – Report on the Radiological State of the Environment in France in 2010-201153

Events and Specific Assessments

The final results of measurements carried out
by CEA and IRSN in the courtyard of 2M Process confirmed the continued gradual decline
observed since December 2010 in the airborne tritium levels measured in the courtyard, but nevertheless indicated thepersistence of tritium emissions from the 2M
Process building.

Figure III.18 shows the changes over time in
the tritium activity measured between
November 5, 2010 and December 14, 2011
in leaves (nettles, bay and ivy) sampled nearthe 2M Process building.

Bq/kg wet weight
100,000

10,000

1,000

100

Jul
.1
1
Au
g.
11
Se
pt.
11
Oc
t. 1
1
No
v. 1
1
De
c. 1
1

10
Ap
r. 1
1
Ma
y1
1
Jun
.1
1

Similarly, since leaves are excellent biologicalindicators (exchanges with tritium present in
the air (molecules of tritiated water) are
rapid, permanent and make it possible tomonitor the dynamic changes in airborne tritium during the days prior to sampling), IRSN
regularly collected samples of plants (mainly
ivy leaves at the stem tips, but also bay
leaves) at various locations in the monitoredzone, in order to measure total tritium activity. As from March 16, 2011, IRSN shared thismonitoring task with CEA. All of the results
obtained, including those from the last campaigns conducted from August to December
2011, are available on the IRSN website andcan be used to track geographical andchronological changes in the tritium traces.

Figure III.17 - Sampling of water vapor in air with the H3R-7000 system in the courtyard of 2M Process.

No
v. 1
0
De
c. 1
0
Jan
.1
1
Fe
b. 1
1
Ma
r. 1
1

In addition, as part of its environmental monitoring brief, IRSN regularly took samples ofrainwater in the courtyard and surface waterat various locations in the monitored zone, inorder to measure tritium activity. The tritium
traces observed in November 2010 in thiswater gradually decreased during 2011, andby the end of the year had reached levels
that were difficult to detect with the analytical techniques used. Since the final results
obtained were below the decision thresholds,
IRSN decided to cease water monitoring
beyond the perimeter of the courtyard of the2M Process building at the end of 2011.

Sampling date
Nettles (2 m from the 2M Process building)Ivy (18 m from the 2M Process building)

Bay leaves (10 m from the 2M Process building)Ivy (50 m from the 2M Process building)Figure III.18 - Changes over time in tritium activity (in Bq/kg wet weight) measured between
5 November 5, 2010 and December 14, 2011 in leaves (nettles, bay and ivy) sampled nearthe 2M Process building (NB logarithmic scale).

54

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III.3
Tritium activity was highest in the leaf samples taken less than 10 meters from thebuilding, mainly in the courtyard of 2M Process. A slow but gradual decline in tritium
activity in leaves was observed as time wentby, falling from several thousand Bq/kg wetweight in November and December 2010 inplants growing 2 meters away from the building to less than 50 Bq/kg wet weight since
the last quarter of 2011. Beyond the courtyard, within a radius of about 50 meters
around the 2M Process building, tritium activity in foliage can still be measured today but
is often close to or below the decision thresholds (30 Bq/kg wet weight for Q4-2011).
Finally, beyond the 50-meter mark, the tritium level in plants is systematically below
the decision thresholds of the measuring
equipment, confirming a rapid decrease withincreasing distance from the 2M Process site,previously observed in surface water.
Values between 30 and 100 Bq/kg wetweight are currently observed only within a
50 m radius of the site. These results clearly
indicate the influence of the tritium emitted
by the 2M Process building, which falls off
rapidly with distance from the site. In absolute terms, the values obtained are negligiblein terms of radiological risk to human health.
Consequently, IRSN decided in late 2011 tostop taking plant samples beyond a 50 m
perimeter of the contaminated building.
With more than 350 measurement results
acquired during 24 sampling campaigns, IRSN
had access to accurate information about
geographical and chronological changes intritium levels on the premises and in theimmediate vicinity of the 2M Process site.
The final measurement results obtained fromIRSN and CEA's environmental monitoringaround the site confirmed the main earlier
observations:• tritium in plant (leaves) and water samples taken in the vicinity was by then measurable only very close to the site. Its
concentration decreased rapidly with distance from the site, becoming undetectablewith the analytical methods used, beyond aradius of about 50 meters;• the general decline in tritium activity was
likewise confirmed in the atmosphere andin the plant samples taken in the courtyardof the 2M Process building. This trend canbe correlated to that observed in the measurements made by CEA inside the 2M Process building , which is still being
decontaminated.
Although all of the results obtained in thevicinity demonstrate beyond doubt thatslight environmental traces caused by tritium
releases from the 2M Process building still
persisted by early 2012, they cannot invalidate the evaluation of the doses received by
local residents living closest to the building(see the report on the IRSN website). Given
the persistence of observable environmental
traces and the environmental monitoring
program implemented by CEA, IRSN decided
to continue monitoring on a more limited
scale during the first half of 2012, at quarterly intervals, in the immediate vicinity of
the 2M Process building.
All tritium measurement results, both on surface water and rainwater and on plants, havebeen mapped and can be consulted on the
IRSN website (www.irsn.fr).
To find out more and to view the latest information notice published by IRSN, see http://
www.irsn.fr/FR/Actualites_presse/Actualites/
Pages/20120222_contamination-tritium-stmaur_resultats-mesures-environnement.aspx

III.3 IRSN assessmentson the OrflamPlast site in
Pargny-surSaulx in northeastern France
In support of government departments,
IRSN regularly conducts special studies onsites where radioactive material has beenused or disposed of, and where a level ofradioactivity higher than natural background radiation still persists today. These
are usually former industrial sites that generated manufacturing process residues, orformer research laboratories. The Institute's
role is to look for sources of contamination
and assess the environmental and humanrisks. These assessments form the basis ofregular reports submitted to the authorities. Below is a summary of the ongoingassessments conducted by the Institute in2010 in the municipality of Pargny-surSaulx in northeastern France, the site ofOrflam-Plast, a company that is now
defunct.
Between 1932 and 1967, Orflam-Plast, a
company once based in Pargny-sur-Saulx inthe northeast of the country, made lighter
flints using cerium extracted from monaziteore. The chemical extraction process resulted
in significant quantities of solid, thorium saltbased residues, which were used as backfill
and spread all around the plant.
Since 2009, IRSN has conducted many radiological assessments at the request of theFrench National Radioactive Waste Management Agency (ANDRA) on areas suspected ofbeing contaminated by deposits of these tailings (see IRSN's 2009 radiological report, pp.
151-152).
In July 2010, ANDRA asked IRSN to carry out
further radiological investigations in thevicinity of the plant. This pinpointed two newcontaminated areas:

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

55

Events and Specific Assessments• The first is located on the property of theformer plant chemist, where four areas ofinterest, each limited in size, were identified
and found to have a dose equivalent rate at
50 cm ranging from 100 to 700 nSv/h (i.e.
more than ten times the background value
measured in the municipality). Analysis of
the soil sample taken in the most contaminated area confirmed the presence of decay
products of the 232Th series, in particular
228Ac, the first decay product of the 232Th
series. The specific activity measured for thiselement is 2,300 Bq/kg, i.e. more than 75
times the value found in soil in the Marne
region.
• The second area is located on the banksof the Saulx river, where an area of interest
has been found with a dose equivalent rate
at 50 cm of between 120 and 315 nSv/h.
Furthermore, an empty contaminated drum
was found in the Saulx.
The conclusions of these assessments were
submitted to ANDRA, which is responsible formanaging the work to be carried out on the
Orflam-Plast site and for securing thecontaminated areas outside the site.
In addition, from mid-June to mid-July 2010,
ANDRA commissioned the restoration of theshoreline of the Étang de la Gravière in southern France. Figure III.19 shows the radiological surface mapping obtained during theinitial inspection in April 2009. The threeareas of interest circled in red are where work
was carried out.
Contaminated soil was removed to a depthof several meters and replaced with clay andtopsoil. The criterion used in cleaning up theaffected areas was a measured dose equivalent rate of 200 nSv/h, which will allow
anglers and hikers to reuse the site without
any constraints.

Figure III.19 - Initial mapping of the shoreline of the Étang de la Gravière in southern France; the threeareas of interest that were cleaned up are highlighted.

At the request of ANDRA, IRSN carried out
the final radiological inspection after thecleanup operations. Since no indication of
distance had been associated with the dose
equivalent rate value, IRSN used a 50 cm
measuring distance, in accordance with standard practice in this field.

400 nSv/h have subsequently been recorded
in any of the three areas.

Radiological surface mapping was carried out
using IRSN's Socrate mobile device (Figure III.20).

Additional work was therefore required inthese four areas of interest (indicated byblack circles in Figure III.20), which ensured
compliance with the cleanup criteria
established.

Comparison of the maps before and after
cleanup (Figures III.19 and III.20) confirmed
the effectiveness of these operations, sinceno dose equivalent rate values higher than

However, this inspection revealed the existence of four relatively small patches withmeasured values exceeding the criterion
applied (200 nSv/h).

LegendDose equivalent rate at 50 cm in nSv/hFigure III.20 - Radiological surface mapping of the shoreline of the Étang de la Gravière after
initial restoration. The areas marked with black circles had dose equivalent rates higher than 260 nSv/h.

56

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III.4

III.4 Radioactive
releases
associated withnatural events
At European level, 2010 was marked by twonatural events that both resulted in radioactive ash being released into the atmosphere,
albeit with significant differences in terms ofthe type of particles, the origin of the radioactivity and the concentrations involved. The
first of these events is associated with theeruption of the Eyjafjöll volcano in Iceland
between mid-April and mid-May, while thesecond concerns the fires that raged in western Russia mainly during the first two weeks
of August 2010.

Forest fires
in the regions
contaminated by the
Chernobyl accident
The spate of forest fires in western Russia
during the summer of 2010 (Figure III.21) asa result of the heat wave prompted IRSN toconsider the environmental impact of fires inareas contaminated by radioactive fallout
from the Chernobyl accident, and particularly
the possibility of long-range redistribution of
artificial radioactivity.

5,000

In consultation with Météo-France, IRSN
monitored changes in the air masses andselected around ten aerosol samplers within
its OPERA-Air atmospheric monitoring network to undertake priority measurements.
Weather conditions, and particularly the factthat the air masses originated over the ocean,prevented the plumes of ash from heading forwestern Europe. The values measured wereamong the lowest usually recorded and are
typical of oceanic air masses. These results
can be explained by the prevailing westerly
winds over western Europe during this period
and by the fact that the few high-pressure
systems were not strong enough to affect thegeneral wind conditions.
A fact sheet on monitoring this phenomenon
is available on the IRSN website at: http://
www.irsn.fr/FR/Actualites_presse/Actualit
Pages/20100831_resultats-analyse-IRSNfeux-de-forets-russie.aspx
For more information
Forest fires had already run rampant inUkraine, Belarus and Russia between midAugust and early September 2002, during
which time a momentary advection ofmasses of air towards western Europe
resulted in an increase (by a factor of four atmost) in the residual 137Cs background activity in the atmosphere. Cesium-137, an artificial radionuclide present in the atmosphere
only in aerosol form, has been monitored
since the late 1950s using filtration stationsin the OPERA-Air network. It has persisted forseveral years in ultra-trace amounts (approximately 0.2 µBq.m-3 of air)2 in the lower
atmosphere, primarily due to the wind resuspending soil particles containing traces of
earlier deposits of 137Cs. As they grow, plants
take up a very small fraction (transfer factor
of about 10-3 m2/kg) of the 137Cs activity
present in the soil, by root transfer.
IRSN research has shown that approximately
8% of the 137Cs activity in wood is emitted
into the atmosphere when wood is burned.
Consequently, the combustion of biomass,
particularly in winter, also contributes tomaintaining a residual level. In all cases, theairborne levels are so low that around 30 to
50,000 m3 of air per sample have to be filtered to be able to quantify the 137Cs present.
In conclusion, the summer 2010 fires in eastern Europe are not thought to have had any
environmental radiological impact or, logically, any health impact on France. The same
applies for other countries that closely monitored this episode, such as Finland.

2 – 1 μBq.m-3 = 1 millionth of a becquerel per m3 of air
is equivalent to the decay of one radioactive atom
per second in a volume of one million m3 of air.

Number of fires

4,000
3,000
2,000
1,000

24/8/10

17/8/10

10/8/10

3/8/1027/7/10

20/7/10

13/7/10

6/7/1029/6/1022/6/1015/6/10

8/6/101/6/100

Date

Figure III.22 - Approximately 8% of the 137Cs
activity in wood is emitted into the atmospherewhen wood is burned.

Figure III.21 - Variation in the daily number of fires in Ukraine, Belarus and western Russia between
early June and late August 2010.
Source of data: FIRMS Global Fire Alerts - UN-FAO/UMD/NASAIRSN – Report on the Radiological State of the Environment in France in 2010-2011

57

Impact of the ash cloud
produced by the eruptionof the Icelandic Eyjafjöll
volcanoBetween April 14 and 16, 2010, some 70 to
80 million m3 of tephra3 are believed to havebeen projected into the atmosphere by the
Icelandic volcano (Figure III.23). Taking into
account the uranium (~ 2 ppm) and thorium
concentrations naturally present in magma
and the quantities of ash discharged, it can be
estimated that, over a period of three days,
the volcano spewed out approximately
400 metric tons of uranium and 1,300 metric tons of thorium, with a thorium/uranium
ratio of 3.3, i.e. a source term of 20 TBq4 ofuranium and 16 TBq of thorium.
Most of this was deposited on the flanks ofthe volcano itself and on adjacent land. The
rest was carried aloft and dispersed far awayfrom Iceland, over the North Atlantic andEurope.
Over France, the plume remained mainly at
an altitude between 500-1,000 m and3,000 m. The volume concentration measured in the air at ground level corresponds
to approximately 1 µBq/m3 for uranium-238
and 0.8 µBq/m 3 for thorium-232. These
results can be compared to the level of lead210 (decay chain of uranium-238), which ispermanently present in the atmosphere at anannual average level in France of about
500 µBq/m3 (varying annually between 100
and 1,600 µBq/m 3). The levels of polonium-210 in rainfall that had cleansed theatmosphere in April were between 7 and62 mBq/L (IRSN data). These levels are normal and consistent with the activity measured in the atmosphere.
For more information
As part of its radioactivity monitoring brief,
IRSN devoted particular attention to tracking
the plume of volcanic ash that passed overFrance between April 15 and 21, 2010, mainlyin the northern third of the country. In particular, polonium-210 (used as a specifictracer for volcanic plumes) and lead-210
were measured, since they are decay products of the uranium-238 chain. The volcanic
eruptions were considered to be responsible
for nearly 50% of the polonium-210 levels in

e

e

A

e

S

e

Ev nts and p cific ss ssm nts

the lower atmosphere (< 6 km), where theaverage atmospheric concentration wasapproximately 50 µBq/m3. The aerosol samplers in the OPERA-Air network, which areroutinely used to monitor radioactivity in theatmosphere (Figure III.24), did not reveal any
anomalies that might have confirmed thepresence of volcanic dust in measurable
quantities significantly higher than thisreference value, at ground level in France.

This episode temporarily grounded a large
number of aircraft in Europe but also ultimately led to different particle concentrationthresholds being established (vigilance
threshold at 200 µg/m3 or threshold for riskof engine damage from 2 mg/m3). By way ofcomparison, the concentration level atground level did not exceed a few tens ofµg/m3, i.e. it was within a range of normal
values typical of an urban pollution event.

At the same time, the Lidar 5 networks
deployed between France and Switzerland, inparticular, showed that most of the cloud had
passed over northern France at an altitude of
between 500 and 1,500-2,000 m. Because of
the dilution of the air masses, the altitude of
the ash, and its relatively low uranium andthorium content to start with, the measurement results are within the variation ranges
usually observed.

An information notice on this specific episode is available on the IRSN website at:
http://www.irsn.fr/FR/Actualites_presse/
Actualites /Pages /20100610_Nuage_
cendres_volcan_islandais_Eyjafjoll.aspx

5 – Light Detection and Ranging. Optical measuring device that uses a laser beam to determine, afterreflection of the incident signal, clouds andparticles suspended in the atmosphere.

Figure III.23 - Eruption plume of Eyjafjöll.

3 –Solid and liquid material arising from magma androcks from the volcanic vent, entrained by gases andejected with them during a volcanic eruption; data
estimated by the French Geological Survey (BRGM).
4 –1 TBq = 1012 becquerels

58

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

III.4

Figure III.24 - Very high-volume (700 m3/h) aerosol sampler in IRSN's OPERA-Air network(Puy-de-Dôme site in south-central France).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

59

MONITORING IN METROPOLITAN FRANCE AND THE OVERSEAS TERRITORIES60

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV
MONITORING IN
METROPOLITAN FRANCEAND THE OVERSEASTERRITORIES

IV.1 Atmospheric compartment
IV.2 Continental environment
IV.3 Marine and coastal environment
IV.4 Regional radiological studies© Laurent
French navy
Zylberman/Graphix-Images/IRSN

IV.5 Radiological monitoring in the overseas territories

Monitoring IN metropolitan FRANCE and THE overseas territories

IV.1 A tmosphericcompartment
The dose in air
The gamma dose equivalent rate in air("dose rate") is measured by two typesof devices:• " a c t i ve" d ev i c e s , w h e r e t h emeasurement is performed instantly insitu;• "passive" devices, where the dose is
integrated for a period of time and thenmeasured in the laboratory (Figure IV.1).
Active devices, such as those in IRSN's
Teleray remote measurement network or
EDFs network of monitors, provide
continuous monitoring and return the
results within a few minutes. Combined with
communication and information technology
devices, they form alert networks. The daily
or monthly mean measurement data fromeach monitor is sent to the French national
environmental radioactivity measurement
network (RNM) by all organizations that
perform measurements.
Passive measurements are taken by
dosimeters that remain in place over along period, generally six months, but
this can vary from one month to a full
year. After laboratory analysis, theintegrated dose measured is thenconverted to a dose equivalent rate overtime, taking the exposure time of thedosimeters into account. The data sent
to the RNM consists of the dose rates
over time, associated with a measuring
period.
More than 102,000 measurement
results of the gamma dose equivalent in
air were extracted from the RNM
database for the period January 2010 toJune 2011. The pie charts in Figure IV.2
show the number of monitoring points
a n d t h e nu m b e r o f a s s o c i a t e dmeasurements for each organization.
IRSN also manages a network ofapproximately 700 passive dosimeters.
Figure IV.3 illustrates the geographicaldistribution of all the monitoring points
for active devices. IRSN's Teleray
network covers the entire territory,
where the points were determined totarget areas with a high population

62

Figure IV.1 - Instruments used to measure the gamma dose equivalent rate in the atmosphere: on theleft, an active device (Gamma Tracer probe from the EDF network) and on the right, a passive device(radiophotoluminescent (RPL) dosimeter).

Number of monitoring points
44

65

22

48
IRSN
EDF

157

38

Number of measurements taken

360

6,577

6,423

106
French Navy
Areva

CEA
ILL

786
1,044
725

2,664

81,652

22

Andra
RhodiaFigure IV.2 - Inventory, by organization, of the number of points and environmental dosimetricmonitoring measurements in France declared to the RNM (active and passive devices).

density, as well as all the nuclear sites.
The overseas departments, regions andcommunities are also continuously
monitored and the results detailed in a
special report. The Teleray network iscurrently being modernized and

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

redeployed. Four hundred new remotemeasurement monitors are being
installed and the operation, which began
in 2011, is expected to be completed by
2015.

IV.1
The other data providers concentrate theirenvironmental monitoring within a close
perimeter of their facilities. EDF has 360
monitors distributed around its 19 nuclear
power plants (NPP) (see Focus) and theFrench Navy has 48 monitors shared between
the four naval ports; the CEA, Areva and ILL
sites generally have a few active monitors (4 inMarcoule, 4 in Saclay, 5 in La Hague, 4 in
Grenoble), while most of the passive
dosimeters are in operation.

IRSN
EDF
French Navy
Areva
CEA
ILL

0

50

100

200

300

400

Kilometers

Distribution of EDF area monitors around NPPs
The ambient gamma dose rate measuring
monitors on EDF sites are always distributed
according to the areas in the vicinity.
There are generally ten "fence" monitors,
four "1 km" monitors, four "5 km" monitors
and ten "10 km" monitors (non regulatory).
Until 1990, the ten "fence" points weremonitored by passive dosimeters.
As an example, Figure IV.4 shows the
distribution of monitors around the Civaux
nuclear power plant.

© Scan IGN

EDF • FOCUS

Figure IV.3 - Location of dose equivalent rate active measuring devices.

Fence sensors
Sensors 1 km

Sensors 5 km
Sensors 10 km

0

1,5

3

6

Kilometers

Figure IV.4 - Geographical distribution of ambient gamma dose measurement points
around the Civaux nuclear power plant (EDF).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

63

Monitoring IN metropolitan FRANCE and THE overseas territories

The passive devices are measuring
instruments specifically designed for theenvironmental monitoring of sites whose
activities do not justify the presence of awarning system. They can also be used inaddition to a warning system.
The environment of the French National
Radioactive Waste Management Agency(ANDRA) and Rhodia sites is exclusively
monitored by passive dosimeters. Both typesof devices coexist on other nuclear sites. Thisis the case on ILL, EDF, CEA and Areva sites.
Andra
Areva
CEA
ILL
RhodiaIRSN

Since 1985, IRSN has also had a network ofenvironmental monitoring dosimeters
permanently installed across the entire
territory. This network is currently being
upgraded and it is planned to phase out
thermoluminescent dosimeters (DTL) in favorof radiophotoluminescent (RPL) dosimeters;
starting in 2012.
Figure IV.5 illustrates the geographicaldistribution of all the monitoring points forpassive devices.
The average gamma dose equivalent rate
calculated from all the measurements taken
in metropolitan France by IRSN's Teleray
network was 92 nSv/h for 2010 and the firstsix months of 2011. This average was similar
to that of previous years (Figure IV.6).

0

50

100

200

300

400

Kilomètres

Figure IV.5 - Location of ambient gamma dose passive measuring devices.

Dose rate (nSv/h)

90

19
94
19
95
19
96
19
97
19
98
19
99
20
00
20
01
20
02
20
03
20
04
20
05
20
06
20
07
20
08
20
09
20
10
20
11

0

Figure IV.6 - Changes in Teleray network annual average measurements from 1994 to 2011 nSv/h.

64

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.1
Figure IV.7 illustrates the variability of thedose rate in air measured by active andpassive devices. The maps reflect therespective influences of the two contributors
to dose rates in air: terrestrial radiation
related to the geological nature of the landand cosmic radiation, which depends on
altitude.
Figure IV.8 shows that the dose rate
associated with cosmic radiation alone canreach 80 nSv/h at an altitude of 2,000 m.
The dose rate in air is higher in regions where
granitic rocks predominate (Auvergne, theAlps, Corsica, Limousin) than in sedimentarybasins characterized by low terrestrial
radiation (Paris and Aquitaine basins,
Rhône valley). Figure IV.9 illustrates theaverage calculated for each region of
metropolitan France.

0 50 100 200 300 400
Kilometers

0 50 100 200 300 400
Kilometers

Unit: nSv/h< 80
81 - 120
121 - 150
151 - 200
201 - 250

Unit: nSv/h< 60
61 - 70
71 - 80
81 - 90
91 - 110

Figure IV.7 - Map of dose rate measurement data for active devices (left) and passive
devices (right).
Dose rate (nSv/h)
250

The differences between the two maps
shown in Figure IV.7 are basically due to thelocation of the devices, with theircharacteristics playing only a relatively small
part. More specifically, certain high values
due to active devices are related to thepresence of probes installed on mountaintops with high cosmic radiation and notassociated with no passive devices.

200

150

100

50

There is little difference between themeasurements provided by both types ofdevices when they are less than 100 metersapart (Figure IV.10). One of the causes of the
few differences observed is the significant
uncertainty that can be associated with themeasurement provided by a dosimeter,
particularly when the integration time isshort (one month). The significant difference
noted in the case of measurements taken
around La Rochelle is explained by the factthat some of the dosimeters used formonitoring the Rhodia site are located within
the plant (see Chapter VII).

0

0

500

1,000

1,500

2,000

2,500

3,000

3,500

4,000

4,500

5,000

Altitude (m)Figure IV.8 - Contribution of cosmic radiation to the dose rate, depending on altitude.
Dose rate (nSv/h)90

0ce ine gne die gne gne ntre nne rse mté die nce llon usin ine ées lais oire rdie tes zur lpes
o
a
n
i
n
n
sa
r
n a
Al uita uve rma urgo reta Ce rde C -Co rma -Fra uss imo Lorr yré e-C la L Pica are e d'A e-A
A
h
e
o
t n
e
B
P
e
L
d
o
d
R
C
h
d
Aq A No Bo- Cô hôneidi as s
nc -N e- cou es- Rag
M d-P Paytsera ute Îl edo
i
s
p
F
p
r
u
Po -Al
Ba
Ha
am
ng
No
ce
Ch
La
en
ov
r
P
Figure IV.9 - Regional dose rate averages for 2010 (active devices) (nSv/h).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

65

Monitoring IN metropolitan FRANCE and THE overseas territories

The temporary interruption of data seen on
this graph indicates when the new monitoring
system for the Teleray network came into
operation and interrupted communications
between the monitors for 24 hours in
December 2010. In addition, in December
2010 and January 2011, some probes
installed on mountain tops malfunctioned, inparticular the probe on the Aiguille du Midi in
the Alps (altitude 3,800 m), where the average
dose rate was approximately 300 nSv/h.
Considering the small number of stations inthis category, the absence of data for stations
where a malfunction occurred greatly
impacted and visibly lowered the average
dose rate (Figure IV.11).
The large fluctuations observed in mountain
top measurements can be explained by theeffect of the blanket of snow which screensterrestrial radiation. Other fluctuations can be
explained by meteorological phenomena. For
example, a storm after a dry period cansuddenly bring natural atmosphericradioactivity down to the ground, causing atemporary increase in the dose rate measured.
The graph in Figure IV.12 shows that no fault
was detected over this period around nuclear
sites by any of the contributors to the
National Environmental Radioactivity
Measurement Network. Thresholds were
nevertheless sometimes exceeded, but this
could always be explained by a natural event(storm) or by planned exposure to an artificial
radioactive source (calibration, a convoy ofvehicles transporting radioactive material
passing through).

Dose rate (nSv/h)
250
200
150
100
50
0

s le
s
s
s
x
e
e
e
e
y in
tel e
le rg
le le
le
hâ evill Rose nob evil bou chel invil Petit -Isèr acla Aub Hère ranc teau alive enag huy Bâc
C
r
D
o
’
l
S
u
e
u
S
â
s
l
a
J
o
e
x Gr erqsleR Oll -la s-su
int -d -D Ch
s-l igu au
Sa ines ersle
La
H
Sa artin l-lès oisère D nayla illi
vil man
y
r
u
n
u
t
u
M
o
V
e
a
o Ro
lS
Br
nt
int t-P au
Om
Fo
Sa Sain nt-P
ia
S
ActivePassive

Figure IV.10 - Comparative analysis of measurements performed by active and passive devices (nSv/h).

Dose rate (nSv/h)
250
200
150
100
50
0
Jan
. 10
Feb
. 10
Ma
r. 1
0
Ap
r. 1
0
Ma
y1
0
Jun
. 10
Jul
. 10
Au
g. 1
0
Se
pt.
10
Oc
t. 1
0
No
v. 1
0
De
c.1
0
Jan
. 11
Feb
. 11
Ma
r.1
1
Ap
r. 1
1
Ma
y1
1
Jun
. 11

Figure IV.11 shows the relative stability of thedose rate measurements recorded by theTeleray network monitors between January2010 and June 2011 for different location
categories. These values were stablecompared with those from previous years.

SummitMetropolitan France

Nuclear sites

Île-de-France

Figure IV.11 - Changes in the average dose rate by site category for the IRSN Teleray network (nSv/h).

Dose rate (nSv/h)
160
140
120
100
80
60
40
20

Jan
. 10
Feb
. 10
Ma
r. 1
0
Ap
r. 1
0
Ma
y1
0
Jun
. 10
Jul
.10
Au
g. 1
0
Se
pt.
10
Oc
t. 1
0
No
v. 1
0
De
c. 1
0
Jan
. 11
Feb
. 11
Ma
r. 1
1
Ap
r. 1
1
Ma
y1
1
Jun
. 11

0

EDF
IRSN (probe on nuclear site)

CEA
French Navy

Areva
ILL

Figure IV.12 - Changes in dose rate, by organization, around nuclear sites (active devices) (nSv/h).

66

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.1
Atmosphericaerosols

Gravelines
Lille

La HagueBeaumont-Hague

Low-volume stations in the
OPERA-Air network
Forty-four low-volume stations were in
operation during the period covered by thisradiological report (Figure IV.14). After asampling period of 24 hours at an average
flow rate of approximately 7 to 10 m3/h,
each station's filter was measured. In weekly
groups, the filters were then measured by
gamma spectrometry in a laboratory.
If the period between the end of March 2011
and the beginning of May 2011 is excluded,
during which traces of cesium-137,
cesium-134 and iodine-131 released during
the Fukushima NPP accident were observed,
the measurements did not identify any otherartificial radionuclide and indicated that thisevent had had a fairly consistent effect acrossthe entire territory (see Chapter III).

Chooz

Charleville-Mézières

Flamanville

Cattenom

Le Vésinet
Brest

SaclayBrennilis

AlençonSaint-Laurent-des-EauxAngersChinonNogent-sur-Seine
Orsay

Strasbourg
Soulaines

Fessenheim
Dampierre-en-Burly
ValducDijon
Belleville-sur-Loire
Chalon-sur-Saône

La Rochelle

CivauxLe Bugey
Creys-MalvillePuy de Dôme
Clermont-FerrandSaint-Alban
Grenoble
Le Blayais
Bordeaux - Mérignac
Cruas
Pierrelatte et Eurodif Tricastin
GolfechMarcoule
Cadarache
Nice
Montpellier
Toulouse
Biarritz
La Seyne-sur-Mer
Very high-volume stations
Low-volume stations

Ajaccio

Figure IV.13 - Location of IRSN stations in the OPERA-Air aerosol sampling network.

© Olivier Seignette/Mikaël Lafontan/IRSN

IRSN monitors the radioactivity of
atmospheric aerosols across France by meansof two types of complementary stations(Figure IV.13) which constitute the OPERAAir (environmental radiation monitoring
network:• low-volume stations providing weekly
information about aerosol radioactivity;• very high-volume stations that quantify
the ambient background for the radionuclides
present in very low quantities in the air (forexample cesium-137). Some of these stations
also have a rainwater sampling system.

Maubeuge

Penly
PaluelFigure IV.14 - IRSN OPERA-Air low volume network.

IRSN – Report on the Radiological State of the Environment in France in 2010-201167

Monitoring IN metropolitan FRANCE and THE overseas territories

Radionuclide

Decision threshold(mBq/m3)

Actinium-228
Antimony-124
Antimony-125
Silver-108m
Silver 110m
Cesium-134
Cesium-137
Cobalt-57
Cobalt-58
Cobalt-60
Iodine-131
Manganese-54
Potassium-40
Protactinium-234m
Sodium-22
Tellurium-123m
Zinc-65
Thorium-234

0.4
0.4
0.2
0.06
0.08
0.064
0.065
0.04
0.11
0.09
0.27
0.08
2
10
0.07
0.05
0.19
0.6

Table IV.2 - Mean activity levels measured inCs, 134Cs and 131I in aerosols in the environment
in France during the period impacted byradioactive discharge from the accident at the
Fukushima nuclear power plant.
137

Radionuclide
Cesium-134
Cesium-137
Iodine-131

Mean activity(mBq/m3)
0.030 ± 0.002
0.034 ± 0.002
0.075 ± 0.003

Gamma spectrometry measurements
indicate the constant presence ofberyllium-7 and lead-210, naturally
occurring radionuclides formed
respectively under the effect of solar
radiation in the upper atmospheric layers
and the emanation of radon-222 from soil
(lead-210 is one of the long-lived
radioactive decay products of this gas).
Beryllium-7 and lead-210 concentrations

68

Activity (mBq/m3)
7
6
5
4
3
2
1
0
Jan
. 10
Feb
. 10
Ma
r. 1
0
Ap
r. 1
0
Ma
y1
0
Jun
. 10
Jul
. 10
Au
g. 1
0
Se
pt.
10
Oc
t. 1
0
No
v. 1
0
De
c. 1
0
Jan
. 11
Feb
. 11
Ma
r. 1
1
Ap
r. 1
1
Ma
y1
1

 able IV.1 - Average decision thresholds of theTdifferent artificial radionuclides identified in
atmospheric aerosols routinely sampled by
low-volume IRSN stations in the environment inFrance.

in atmospheric aerosols vary with seasonal
climate changes (Figures IV.15 and IV.16).

Figure IV.15 - Mean beryllium-7 activity measured by the low-volume stations in the IRSN OPERA-Air
network (mBq/m3).
Activity (mBq/m3)
0,7
0,6
0,5
0,4
0,3
0,2
0,1
0
Jan
. 10
Feb
. 10
Ma
r. 1
0
Ap
r. 1
0
Ma
y1
0
Jun
. 10
Jul
. 10
Au
g. 1
0
Se
pt.
10
Oc
t. 1
0
No
v. 1
0
De
c. 1
0
Jan
. 11
Feb
. 11
Ma
r. 1
1
Ap
r. 1
1
Ma
y1
1

Table IV.1 lists all the average decisionthresholds of the different artificial
radionuclides accessed via samples gatheredby these stations and the measuringconditions usually applied. The samples
taken in France further to the Fukushima
accident were analyzed for longer periods.
This resulted in the decision threshold being
lowered and cesium activity levels of
approximately 0.03 mBq/m 3 observed(Table IV.2).

Figure IV.16 - Average lead-210 activity measured by the low-volume stations in the IRSN OPERA-Air
network (mBq/m3).

Very high-volume stations in
the OPERA-Air network
The OPERA-Air network has eightstations with a flow rate of between
300 and 700 m3/h. Sampling takes placeover ten consecutive days toaccumulate a large quantity of aerosols.
In addition, advanced metrology allows
infinitesimal traces of cesium-137 to bemeasured at levels above the decisionthresholds (approximately 0.1 μBq/m3).
The stations monitored the atmosphericfallout in France from the Fukushima
accident, over its entire life. The station
at the summit of the Puy-de-Dôme in

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

central France (Figure III.23 in Chapter III)
was the first to detect traces ofcesium-137 and particulate iodine-131.
In addition to the data from otherstations located on the plain, the arrivalof air masses over France could be dated
between March 23 and 24, 2011.
The data collected by these stations
showed that unlike the fallout from the
Chernobyl accident, the increased
cesium-137 activity in the air masses
following the Fukushima accident did
not last; the activity concentration ofthis radionuclide in the air returned toits previous level in less than six months(Figure IV.17).

IV.1
This was due to the distance from theJapanese power plant and to the factthat most of the cesium deposited on
oceans could no longer give rise toresuspension phenomena liable tomaintain the prolonged persistence of
this radionuclide in the air. Moreover,the iodine-131 quickly disappeared, due
to its short radioactive half-life.
For more information
Chapter III – The Fukushima Accident

137

100

137Cs (µBq/m3)

Cs (µBq/m3)

100 000
10

10 000

1

1 000

0.1

100

0.01
Jan. 09

Rainwater

10

Since 2010, the rainwater collectedeach month (Figure IV.18) in France(Figure IV.19), apart from samples
collected near nuclear facilities, is kept,
but only analyzed in the event of an
accident.

1Jul. 09

Jan. 10

Jul. 10Jan. 11

Jul. 11

Jan. 120,11986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 2008 2010 2012
Figure IV.17 - Mean cesium-137 activity (metropolitan France) in atmospheric aerosols from 1986 to
2012 (µBq/m3).

Lille

Meuse
Seine

MoselleLe Vésinet

Brest

Strasbourg

Brennilis

Rhin
Loire

AngersVienneLoire
Rhône© P. Demail

Briançon
Dordogne

Figure IV.18 - Rainwater collector.

Apart from at the time of the Fukushimaa c c i d e n t wh e n m o n i t o ri n g wa s
intensified ( see Chapter III), therainwater collected each month was notanalyzed in 2010 and 2011.

Biarritz

Toulouse
GaronneRain water sampling stations(monthly frequency)

Montpellier

Nice

Ajaccio

Figure IV.19 - Location of rainwater collectors situated outside the influence of nuclear facilities.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

69

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

IV.2 CONTINENTAL
ENVIRONMENT
Terrestrial compartment
The radiological state of areas not affectedby the effluent released by nuclear
facilities is based on very low-levelmeasurements taken during specificstudies or radiological reports.
In addition, the departments regularly
monitor foodstuffs (at least once a year).
Since 2009, a network of plant and animal
production samplers has been rolled out
by IRSN across the whole of France withthe assistance of the decentralized unitsof the Directorate General on Food Safety( D G A L ) a n d t h e D i re c t o ra t e fo r
Competition, Consumer Rights, andProtection Against Fraud (DGCCRF) toreinforce the monitoring of a geographicalarea, where necessary.

largely predominant and varied, dependingon the department, between 32 ± 13 and68 ± 10 Bq/L for cow's milk and between
52 ± 7 and 71 ± 10 Bq/L for goat's milk.
The activity measured in sheep's milkcollected in the Alpes-Maritimes in thesoutheastern corner of France amounted
to 36.4 ± 3.9 Bq/L.
After the Fukushima accident, some milkcollected in metropolitan France between
March and May 2011 showed traces ofiodine-131, cesium-134 and cesium-137.
The results of this incident are presented
in Chapter III.
Cesium-137 and strontium-90 are alsomeasured more or less regularly in FrenchMilk
In addition to collecting milk from farms
near nuclear facilities, samples fromcooperatives or dairies are used to obtainrepresentative reference values for bovine,
caprine and ovine milk production fromthe departments in France and keep
watch over the health of the French
population.

Figure IV.20 - Preparing milk samples.

The sampling frequency, which by default
is once a year, can be increased in theevent of a radiological incident.
The radioactivity measured in milk is now
intrinsically of natural origin. During theperiod of January 2010 to May 2011, as inprevious years, potassium-40 activity was70

Note: Strontium-90 was measured on only a few
samples, as the procedure requires
prior chemical treatment that is difficult to carry out
on fresh milk. The results available for
32 departments show a range of activity levels in
metropolitan France.

© Olivier Seignette/Mikaël Lafontan/IRSN

This radiological monitoring focuses on
two of the main French agricultural
products: milk and cereals. These products
have been monitored since the beginningof the 1960s, providing records of the
fallout from atmospheric nuclear weapons
tests and the Chernobyl accident, as wellas their persistent effects. In addition,some samples of mushrooms from theareas most affected by fallout from the
Chernobyl accident are regularly analyzed
to determine their cesium-137 content.

milk. As a result, traces of strontium-90 of
between 0.022 ± 0.01 and 0.113 ±0.018 Bq/L were observed in most of thesamples analyzed (weighted average of
0.0322 ± 0.0017 Bq/L over the entire
collection period under consideration –Figure IV.21). The presence of thisradionuclide represents residual materialof the fallout from past atmosphericnuclear weapons tests. No increase in its
activity was detected in milk samples
from farms in the vicinity of nuclear
facilities.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.2

0.14

Bq/L

0.12
0.1
0.08
0.06
0.04
0.02
0

t
s
s
s
e e
e
e
e
e
e
e
e
e
e
a
de
do rèz vre gn m nn Ger rond ronn arn -Loir Jur Loir Loireôn iègies- ence u-Rh Ar alva Cor x-Sè ordo Drô Essoa e-M -et
p
G
l
G
C
v
t
u
A ro s-dDeDeute Hau Indrs-P heHa
ute Bouca
H
Cow's milkn
TarGoat's milk

Figure IV.21 - 90Sr activity levels in milk collected in French departments between January 2010
and May 2011 (Bq/L).

Similarly, the cesium-137 activity of 0.117 ±0.031 and 0.194 ± 0.05 Bq/L was respectively
measured in milk collected in 2010 in the
Cantal and Puy-de-Dôme departments insouth-central France. These traces are
attributable to earlier fallout from nuclear
tests and the Chernobyl accident. Figure IV.22
shows that in May 1986, 137Cs activity levels
reached several dozen Bq/L. Apart from these
two samples, cesium-137 activity levels inmilk collected from the departments inFrance in 2010-2011 were below the decisionthresholds (< 0.6 Bq/L).

60

Bq/L
April 26, 1986:
Chernobyl accident

50
40
30
20

Atmospheric nuclear
weapons tests

10

Cereals
Radiological monitoring of wheat in
metropolitan France is carried out with theassistance of the French National Institutefor Agricultural and Marine Products (France
AgriMer) which takes samples from 210 silos
across France. The samples are then grouped
into 21 regional blends. The results obtainedin 2010 are given in Table IV.3.
As with milk, most radioactivity in wheat
grains is of natural origin, in particularpotassium-40 activity.

1960
1961
1962
1963
1964
1965
1966
1967
1968
1969
1970
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
2005
2006
2007
2008
2009
2010

0

Finally, the tritium in the milk produced in the
Côte-d'Or in eastern France was measured(11 ± 2.3 Bq/L in milk collected on April 27,
2010 and 15 ± 2.6 Bq/L in that collected on
March 15, 2011). These activity levels wererelated to atmospheric radioactive discharge
from the CEA Valduc facility (see Chapter VI CEA Valduc Monitoring).

Significant results< DL

Figure IV.22 - Cesium-137 activity levels in milk analyzed in the Allier department (Bq/L).

As in previous years, the only artificial
radionuclide detected in wheat wasstrontium-90, which was the residue fromatmospheric fallout from atmospheric nuclear
weapons tests. Figure IV.23 illustrates the
reduction in activity of this radionuclide incereals from 1969 to the present day, in all
regions.
Regional monitoring complements themonitoring carried out around the main
nuclear facilities. Results are presented in
Chapters V and VI.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

71Monitoring IN metropolitan FRANCE and THE overseas TERRITORIESTable IV.3 - Activity levels measured in durum wheat samples (2010 harvest) – Regional mixtures (Bq/kg wet).

Specific activity (Bq/kg wet)
Region
K

40

1.8

Mn

54

Co

58

Co

90

60

Cs

Cs

134

137

Alsace115 ± 23

< 0.50< 0.64< 0.500.11 ± 0.01

< 0.48< 0.49Aquitaine

112 ± 16

< 0.50< 0.78< 0.47

0.11 ± 0.02

< 0.45< 0.47

Auvergne

106 ± 16

< 0.56< 0.76< 0.520.19 ± 0.02

< 0.49< 0.50Bourgogne

114 ± 24

< 0.56< 1.23< 0.480.19 ± 0.02

< 0.44< 0.51

Bretagne

105 ± 24

< 0.53< 0.78< 0.490.26 ± 0.03

< 0.46< 0.52Centre110 ± 24

< 0.70< 0.76< 0.51

0.12 ± 0.02

< 0.49< 0.53

Champagne-Ardenne

104 ± 23

< 0.61< 2.02< 0.51

0.12 ± 0.01

< 0.51< 0.52

Franche-Comté

95 ± 22< 0.57< 0.63< 0.460.18 ± 0.02

< 0.47< 0.51Île-de-France

109 ± 20

< 0.53< 1.29< 0.420.05 ± 0.01

< 0.44< 0.46

Languedoc-Roussillon

128 ± 27

< 0.51< 0.72< 0.510.10 ± 0.01

< 0.48< 0.56

Limousin

99 ± 24< 0.47< 0.60< 0.530.23 ± 0.04

< 0.47< 0.55Lorraine

100 ± 15

< 0.49< 0.67< 0.550.13 ± 0.02

< 0.47< 0.47Midi-Pyrénées

113 ± 24

< 0.70< 1.36< 0.510.18 ± 0.02

< 0.51< 0.51

Nord-Pas-de-Calais

108 ± 24

< 0.52< 0.64< 0.540.07 ± 0.01

< 0.46< 0.46

Basse-Normandie

105 ± 22

< 0.49< 0.70< 0.480.17 ± 0.02

< 0.58< 0.49Haute-Normandie

105 ± 23

< 0.56< 0.95< 0.420.12 ± 0.01

< 0.49< 0.49Pays de la Loire

102 ± 25

< 0.59< 0.70< 0.480.18 ± 0.02

< 0.49< 0.50

Picardie

101 ± 21

< 0.54< 0.81< 0.51

0.12 ± 0.05

< 0.47< 0.57

Poitou-Charentes

109 ± 24

< 0.62< 0.78< 0.490.16 ± 0.02

< 0.55< 0.55

Provence-Alpes-Côte-d’Azur

114 ± 24

< 0.75< 3.23< 0.580.14 ± 0.02

< 0.55< 0.54

Rhône-Alpes

114 ± 20

< 0.48< 0.77< 0.420.15 ± 0.03

< 0.39< 0.41

Bq/kg wet

1.6
1.4
1.2
1
0.8
0.6
0.4
0.2

1968
1969
1970
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
2005
2006
2007
2008
2009
2010

0
Significant results< DL

Figure IV.23 - Strontium-90 activity levels measured on wheat samples from 1969 to 2010,
in all regions (Bq/kg wet).

72

Sr

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.2
Mushrooms
Mushrooms are among the few foodstuffs
produced in France in which cesium-137
from earlier fallouts is still measured on aregular basis. In 2010, mushroom samples
were taken from areas where such fallout wasat its highest (Table IV.4).
Most of the samples contained traces ofcesium-137 that were nevertheless still
below the maximum permissible level ofradioactive contamination set at 1,250 Bq/kg
wet by Euratom Regulation No. 2218-89 ofJuly 18, 1989 modifying Regulation No.
3954-87 of December 22, 1987.

Table IV.4 - Activity levels measured in mushrooms collected in 2010 (Bq/kg wet).

Department

SpeciesCesium-137 specific activity(Bq/kg wet)

Bas-Rhin

Boletus28.8 ± 2.5

Corse-du-Sud

Mushroom(non identified species)

1.91 ± 0.37

Doubs

Chanterelle

13.9 ± 1.7

Boletus3.71 ± 0.43

Lactarius sanguifluus

121 ± 10

Amanita rubescens

0.23 ± 0.06

Boletus edilis

8.1 ± 1

Black trumpet

1.18 ± 0.21
< 0.1
0.24 ± 0.09

Puy-de-Dôme

Fawn pluteus
Delicious or lactarius
sanguifluus
Lactarius

Rhône

Black trumpet

0.37 ± 0.1

Vaucluse

Girolle6.1 ± 0.6

Drôme
Haute-Corse
Haut-Rhin

Meurthe-et-Moselle

Fukushima accident
Following the incident that occurred on
March 11, 2011 at the Fukushima nuclear
power plant in Japan, monitoring of activity
levels was increased across France fromMarch 21 to May 6, 2011.
Samples of grass, milk and leafy vegetables
were collected throughout the country,
from areas outside the influence of French
nuclear facilities, by associations,departmental laboratories and thedepartmental services of the DGAL,
DGCCRF and IRSN.
The strategy deployed during this incident
and the associated analysis results arepresented in Chapter III.

3.5 ± 0.34

Rancennes
Seine

Meuse
Croissy-sur-Seine
Croissy-sur-Seine

Apach
MoselleRhin
Vogelgrun

Loire
Les-Ponts-de-Cé
Les Ponts de Cé
VienneLoire

Aquatic compartment
Around thirty semi-automated water
samplers have been installed throughout
France to monitor rivers and streams. Water
monitoring is supplemented by an automatedremote radioactivity measuring system thatprovides continuous measurements: theHydroTeleray network (Figure IV.24). The
results of the analyses performed on samples
taken immediately downstream of nuclear
facilities are given in Chapters V and VI.

Rhône
Dordogne
Boé

Vallabrègues
Vallabrègues

GaronneIRSN HydroTeleray stations
Semi-automated water samplers

Figure IV.24 - Location of IRSN water samplers downstream of nuclear facilities and HydroTeleray
network stations.

IRSN – Report on the Radiological State of the Environment in France in 2010-201173

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIESThe water sampling network

The HydroTeleray network

For each water sampler, the water from thetank is pumped at a rate of 15 mL per hour togenerate a sample of approximately 2 L every
six days. The samples are sent once a month
to a laboratory, where the fractions of raw and0.45 μm filtered water are analyzed (Figure
IV.25).

The HydroTeleray network, set up in 1993,
provides real-time radiation monitoring ofwater from the seven major French rivers,
downstream of all nuclear facilities at
Ponts-de-Cé (Angers) on the Loire, Croissysur-Seine on the Seine, Vallabrègues (Arles)
on the Rhône, Vogelgrün on the Rhine,
Rancennes on the Meuse, Boé (Agen) on theGaronne and Apach on the Moselle (Figure
IV.24).

In addition to the water samplers andsampling points immediately downstream ofnuclear facilities (see detailed results in
Chapters V and VI), there are three IRSN
stations at distant locations:- on the Loire, downstream of the nuclear
facilities at the Ponts-de-Cé water treatment
station in the west of France;- on the Rhône, downstream of all the nuclear
facilities at the Vallabrègues dam in southern
France;- on the Seine, downstream of the nuclear
facilities at Croissy-sur-Seine to the west of
Paris.

The purpose of this network is tocontinuously ensure that the levels ofactivity of the water courses that might
result from an accident situation are
acceptable from a health point of view,
before they cross national land and sea
borders. At each station, a gamma
spectrometry measurement is performed

during an integration time of two hours fora water flow of approximately 5 m3/h.
The system consists of an NaI detector(sodium iodide) situated in a stainless steel
lead-shielded tank to reduce the natural
background (Figure IV.26). The decisionthresholds are approximately 0.5 at 1 Bq/L
for cesium-137, iodine-131 and cobalt-60.
The data is automatically analyzed, stored
and retransmitted to the concentrator on
the IRSN Le Vésinet site. An alarm can betriggered if an abnormal activity level isdetected.
In 2010 and 2011, only sporadicallydetected radionuclides were of natural
origin, including lead-214, bismuth-214
from radon-222 progeny, and potassium-40.

The analyses performed in 2010 and 2011
show that tritium is the main radionuclide
almost permanently detectable in these rivers.
The tritium activity measured in the Seine
downstream of any nuclear facility at Croissysur-Seine was approximately 12.5 ± 2.9 Bq/L
in 2010; in the water in the Rhône at
Vallabrègues, it was 7.3 ± 2.4 Bq/L and in the
Loire at Angers, 20.3 ± 2 Bq/L. The activity
levels measured are related to the liquid
discharge from the nuclear facilities locatedalong the banks of these rivers, or whose
discharge reaches their drainage basins.

Figure IV.26 - Boé HydroTeleray station (near Agen) performing real-time radiological monitoringof water from the Garonne.

Figure IV.25 - Detailed view of an IRSN water
sampler.

74

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3
IV.3 Marine andcoastalenvironment
The marine and coastal environment ismonitored by coastal sampling stations
situated along all the coasts of France. The
number of stations and their location aredetermined by the proximity of nuclear
facilities, the desire to ensure good
geographical cover and the implementationof specific study programs.
There are two types of stations:• s ampling stations influenced by discharge
from coastal nuclear facilities, whichmonitor spatial and temporal changes in theradiological state of the near-fieldenvironment;• reference stations, characterizing thebackground and any sources of radionuclide
emissions other than those from discharge
from nuclear facilities on the Frenchcoastline. They particularly monitor theradionuclides carried to their marine
environment by major rivers.
All the results from these stations are givenin this chapter and classified by coastal area:
North Sea and Channel, Atlantic andMediterranean.
As the dilution capacity of the marine
environment is greater than that of thecontinental aquatic environment, coastal
monitoring focuses more on bioindicators(seaweed, mollusks, crustaceans, fish) thatconcentrate pollutants and thus provide a
better understanding of the state of theenvironment than some direct seawatermeasurements. The analysis of certain bioindicators plays an important part in
supplying data to the food products
observatory set up in 2009 in partnershipwith the DGAL and DGCCRF. With respect tobiological matrices, the analysis of carbon-14
and organically bound tritium results issummarized in specific Focus sections.

The Channel - North Sea
coast
The radioactivity currently observed in the
Channel and North Sea marine aquatic
environment comes mainly from discharge
from spent fuel reprocessing plants at
La Hague in France and Sellafield in England.
The measurements and modeling of thedispersion of radionuclides discharged bythese facilities in the marine environment
show that the impact of this discharge is nolonger noticeable to the west of Roscoff. This
chapter therefore focuses on the results ofmeasurements performed on the samples
taken from the coastal current between
Roscoff and Dunkirk.

Sea water
Tritium in the sea water in the Channel andthe North Sea is measured at activity levels
generally similar to or greater than 5 Bq/L. It
is mainly caused by liquid effluent discharge
from the Areva site at La Hague and, to alesser extent, the EDF nuclear power plants
at Gravelines, Flamanville, Paluel and Penly.
Very low levels of residual cesium-137 datingback to Chernobyl and atmospheric nuclear
bomb tests can still be measured in seawaterby sampling and treating large volumes ofwater. The cesium-137 activity in thesewaters is just a few mBq/L (Table IV.5).

In the vicinity of nuclear power plants
The Flamanville, Paluel, Penly and Gravelines
NPPs are cooled by water from the Channel.
To improve the dilution of liquid effluent
discharge in the sea, the Flamanville, Palueland Penly NPPs discharge their effluent into
the open sea through an underwater pipe.
These outfalls dilute the discharge released
to the marine environment, but do not allow
the continuous use of sampling equipment.
To resolve this technical problem, water
samplers were installed within the outfall
structure (discharge pond or channel)
upstream of the point where effluent isdischarged to the sea.
In all cases, the activities measured at thesewater samplers provide information about
the average monthly radioactivity discharged
by the NPPs and added to the marine
environment. The design of the Gravelines
NPP outfall structure is different. Discharge
passes through a sea channel leading to thecoast, which therefore constitutes anintermediate receiving environment for thedischarge prior to its dilution in the sea. A
water sampler is installed in this channel. The
activity levels measured on these devices are
therefore greater than those that would bemeasured directly in the marine environment.

Table IV.5 - Tritium and cesium-137 activity levels in water samples from the North Sea (Bq/L).

Radionuclide

Bray-Dunes

Mers-les-Bains

Wimereux

Tritium

6.7 ± 2.5

5.9 ± 2.5

4.2 ± 0.1

Cesium-137

nm

nm0.0073 ± 0.0017

nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010-201175

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIESThe outfall structures exhibit tritium activity
levels that vary, according to their type,
between 5 and 150 Bq/L for most samples.
The measurements taken offshore indicate
values of between 5 and 20 Bq/L, dependingon the location. These values are also
impacted by discharge from the Areva site at
La Hague and by tidal currents.

80

Flamanville NPPAt Flamanville (Figure IV.27), IRSN measures
the tritium in the water of the discharge
pond at a mean activity of 35 Bq/L. The
measurements taken by the operator off the
Channel coast are correlated and are, on
average, approximately 10 Bq/L.

20

Paluel NPPAt Paluel (Figure IV.28), IRSN measures thetritium in the 0KRS/TR1 station where themean activity of the tritium is 65 Bq/L. The
measurements taken by the operator at sea
are mostly below the decision thresholds.
Only a few samples taken to the west of theoutfall exceed 20 Bq/L.
Penly NPP
At Penly (Figure IV.29), IRSN measures thetritium in water samples from the discharge
channel. The mean activity observed is
40 Bq/L. The measurements taken by theoperator at sea are all below the decisionthresholds, with the exception of one
measurement (8.3 Bq/L) carried out inJanuary 2010 on a sample in the vicinity of
Varengeville-sur-Mer.
Gravelines NPPAt Gravelines (Figure IV.30), IRSN measures
the tritium in the water of the sea channel
where the mean activity detected is 15 Bq/L.
The measurements taken by the operator at
sea are below or close to the decisionthresholds.

Bq/L

70
60
50
40
30

10
0
. 07 ct. 07 eb. 08 n. 08 pt. 08 an. 09 ay 09 pt. 09 an. 10 ay 10 pt. 10 an. 11 ay 11 pt. 11
J
J
J
Ju
Jun
F
O
M
M
M
Se
Se
Se
Se

Offshore -50 m to the west
Offshore -50 m to the south

Discharge pond

Offshore -50 m to the northOffshore - (reference)

Decision threshold

Figure IV.27 - Tritium activity measured in sea water at Flamanville (Bq/L).

140

Bq/L

120
100
80
60
40
20
0
. 07 ct. 07 eb. 08 n. 08 pt. 08 an. 09 ay 09 pt. 09 an. 10 ay 10 pt. 10 an. 11 ay 11 pt. 11
J
J
J
Ju
Jun
F
O
M
M
M
Se
Se
Se
Se

50 m west of discharge

50 m east of discharge

50 m north of discharge

OKRS/TR1 station

ref: 1 mile north cardinal buoy

Decision threshold

Figure IV.28 - Tritium activity measured in sea water at Paluel (Bq/L).

120

Bq/L

100
80
60
40
20
0
. 07 ct. 07 eb. 08 n. 08 pt. 08 an. 09 ay 09 pt. 09 an. 10 ay 10 pt. 10 an. 11 ay 11 pt. 11
J
J
J
Ju
Jun
F
O
M
M
M
Se
Se
Se
Se

Discharge channel

Varengeville Pointe d’Ailly

Decision threshold

Figure IV.29 - Tritium activity measured in sea water at Penly (Bq/L).

76

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3

30

Bq/L

25
20
15
10
5
0
. 09
Jan

9
y0
Ma

Sea channel

9
t. 0
Sep

Open sea

. 10
Jan

0
y1
Ma

0
t. 1
Sep

. 11
Jan

1
y1
Ma

1
t. 1
Sep

Decision threshold (at sea)

Figure IV.30 - Tritium activity measured in sea water at Gravelines (Bq/L).

Near the La Hague site
The waters of the Channel receive the liquid
effluents produced by the various facilities on
the La Hague plant, which, after passing
through the effluent treatment stations andinspection, are discharged into the Anse desMoulinets via an underground pipe.

35

Bq/L

30
25
20
15

Iodine-129 was detected in three samples atactivity levels of approximately 0.01 Bq/L
taken from the port of Goury and the Ansedes Moulinets, under which the liquid effluent
discharge pipe from the site passes.
Since 1983, IRSN has been analyzing the sea
water off the Pointe de Jardeheu. Since 1995,
the improvement in liquid scintillation
measuring techniques has made it possible
to detect tritium at values between thedecision threshold and 26 Bq/L (Figure IV.31).
At present, the decision threshold for tritium
using this technique is 1 Bq/L.

10
5
0
1982

1984

1987

Significant activity

1990

1993

1995

1998

2001

2004

2006

2009

2012

Decision threshold

Figure IV.31 - Tritium activity measured in sea water at Pointe de Jardeheu (Bq/L).

12

Bq/L

10

Cherbourg Naval Port

8

The tritium activity in the sea water collectedin the vicinity of the Cherbourg Naval Port
(Figure IV.32) was equivalent to that observed
around the coast of the Cotentin peninsula.

6
4
2
0Nov. 09

Jan. 10

Mar. 10 May 10

Querqueville dikeJul. 10Homet dike

Sept. 10 Nov. 10

Jan. 11Mar. 11 May 11

Decision threshold

Figure IV.32 - Tritium activity measured in sea water samples from Querqueville and Le Homet
dikes (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010-201177

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Sediments
Samples of marine sediments (mud, beachsand) were taken in 2010 and at the
beginning of 2011 at different stations along
the Channel - North Sea coast, from Roscoff
to Dunkirk. The sampling frequencies varied
from one station to another.

In general, the levels of activity measured
remained low and did not exhibit any
abnormalities. They were similar to thosemeasured in recent years. The highest values
were observed in the immediate vicinity ofthe outfall at La Hague. Further away, theactivity levels were often close to thedetection limits or the levels usually foundaway from any nuclear activity.
Cobalt-60 was almost systematicallydetected at the Penly Carteret stations withthe highest activity observed in Cherbourg
harbor (9.4 ± 0.9 Bq/kg dry). The activitiesof transuranium elements (238Pu, 239+240Pu
and 244Cm) and strontium-90 measured in
sediment samples from Cherbourg harborand found to be slightly higher than thosemeasured at other sampling points, confirm
the sensitivity of this area with respect todischarge from the La Hague site. Cobalt-60
was no longer detected west of Granville oreast of Le Tréport.
Cesium-137 was measured along the entire
coast between Roscoff and Dunkirk. The
highest cesium-137 activity levels wereobserved in the Anse des Moulinets, where
the sampling station directly affected bydischarge from the La Hague plant is located(maximum activity of 10.3 ± 1.2 Bq/kg drymeasured in April 2010). These activity
levels tended to decrease along the coast as
the distance from the discharge point
increased. A few dozen miles further on, theobserved levels were similar to thosemeasured in areas outside the influence ofany nuclear activity. The variations observed
were also related to the nature of thesediment samples taken (mud, sand), the78© AcroIn addition to the predominantly naturalradionuclides present ( 40 K, 228 Ac, 7 Be),sediment analysis indicated the presence ofartificial radionuclides (137Cs, 60Co, 90Sr, 238Pu,
239+240Pu, 241Am, 244Cm), mainly related topast and present liquid effluent discharge
from the installations at the La Hague site,
as well as liquid discharge from the
Sellafield site in England.

Figure IV.33 - Collecting sediment samples.

finest having a greater tendency to bindradionuclides.
The 60Co/137Cs activity ratio shown in Figure
IV.34 eliminates variations in 60Co and 137Cs
activity levels that are only related to theparticle size and mineralogy of the sediment.
This ratio is characteristic of the discharge
from the La Hague plant, as shown in Figure
IV.35, obtained in sediments from Cherbourg
harbor and the Seine estuary. The

discrepancy is related to the time it takes
them (about ten years) to travel between
Cherbourg and the Seine estuary. The wide
dispersion of the values observed is
explained by the short radioactive half-lifeof cobalt (5.27 years) with respect tocesium-137 (30.1 years).

Co/137Cs

60

7
6
5
4
3
2
1
0
-200

-100

0

100

200

300

Distance from the La Hague discharge pipe (positive to the east) (km)Figure IV.34 - Changes in the 60Co/137Cs activity ratio observed in sediment samples collected
between January 2010 and May 2011 along the Channel - North Sea coast.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

400

IV.3
Co/137Cs

60

10

1

0.1

0.01

19
75
19
76
19
77
19
78
19
79
19
80
19
81
19
82
19
83
19
84
19
85
19
86
19
87
19
88
19
89
19
90
19
91
19
92
19
93
19
94
19
95
19
96
19
97
19
98
19
99
20
00

0.001

Cherbourg harbor

Seine estuary

Figure IV.35 - Temporal changes in the activity ratio 60Co/137Cs observed in sediment samples from
Cherbourg harbor and the Seine estuary.

Some strontium-90 activity was observed in
the vicinity of the La Hague site, between
0.92 ± 0.17 at Sciotot and 2.9 ± 1.3 Bq/kg
dry in Cherbourg harbor.
The alpha-emitting radionuclides (241Am,
244Cm, 238Pu, 239+240Pu) follow a conventional
distribution in the Channel and the North Sea
with respect to the activities released by the
reprocessing plants at La Hague and Sellafield(Figure IV.36 to Figure IV.39). Most of theseradionuclides are no longer detected at
Roscoff and Dunkirk, or exhibit very low
levels of activity in the order of magnitude
observed in sediment samples from areas
outside the direct influence of nuclear
facilities. As with cesium, the activities oftransuranium elements in sediments dependon the abundance and nature of the finest
fraction, often rich in argillaceous minerals.
For any given site, they can vary by at least
one order of magnitude between sandy andmuddy sediments.

Am (Bq/kg dry)

241

3
2.5
2
1.5
1
0.5
0
-200

-100
0
100
200
300
Distance from the La Hague discharge pipe (positive to the east) (km)Significant results

400<Decision threshold

Figure IV.36 - Changes in americium-241 activity observed in sediment samples collected between
January 2010 and May 2011 along the Channel - North Sea coast (Bq/kg dry).
Cm (Bq/kg dry)

244

0.7
0.6
0.5
0.4
0.3
0.2
0.1
0
-200

-100
0
100
200
300
Distance from the La Hague discharge pipe (positive to the east) (km)Significant results400< Decision threshold

Figure IV.37 - Changes in 244Cm activity observed in sediment samples collected between January2010 and May 2011 along the Channel - North Sea coast (Bq/kg dry).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

79

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Pu (Bq/kg dry)

238

1

0.8

0.6

0.4

0.2

0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant results< Decision threshold

Figure IV.38 - Changes in plutonium-238 activity observed in sediment samples collected between
January 2010 and May 2011 along the Channel - North Sea coast (Bq/kg dry).
Pu (Bq/kg dry)

238+240

2.5

2

1.5

1

0.5

0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant results< Decision threshold

Figure IV.39 - Changes in 239+240Pu activity observed in sediment samples collected between
January 2010 and May 2011 along the Channel - North Sea coast (Bq/kg dry).
Pu /239+240Pu

238

In the marine environment, plutonium andamericium originate from the fallout fromatmospheric nuclear tests and discharge from
nuclear facilities. At present, most discharge
comes from spent fuel reprocessing facilities.
A study of the 238Pu/239+240Pu isotope ratio
identifies the sources of the plutonium: aratio close to 0.03 is characteristic ofatmospheric fallout; the Sellafield plant
exhibits a ratio of approximately 0.2. The
isotope ratio changes significantly in the
discharge from the La Hague plant due toburnup. Figure IV.40 shows the 238Pu/239+240Pu
cumulative ratio in the discharge from the La
Hague plant. A maximum value close to 0.7
is currently observed in the sediments at the

80

0.5

0
1960

1965

1970

1975

1980

1985

1990

1995

2000

Figure IV.40 - Changes in the 238Pu/239+240Pu cumulative ratio in discharge from the La Hague plant.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3
center of the Channel. All the isotope ratios
calculated from the measurements taken in2010 and at the beginning of 2011 (Figure
IV.41) revealed that the Cotentin coast
showed traces of past and present liquid
effluent discharge from the spent fuelreprocessing facilities at La Hague andSellafield.

Pu /239+240Pu

238

0.8
0.7
0.6
Interval for which the isotope
ratio is characteristic ofindustrial discharge

0.5
0.4
0.3

Similarly, the 241Am/239+240Pu activity ratio
observed was also characteristic of discharge
from the La Hague plant. The variation in the
241 Am/ 239+240 Pu cumulative ratio in the
discharge from the La Hague plant (Figure
IV.42) was close to 2 in many matrices,
particularly in sediments.

Characteristic Sellafield
plant discharge ratio: 0.2

0.2
0.1

Characteristic atmosphericfallout ratio: 0.03

0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Figure IV.41 - Changes in the activity ratio 238Pu/239+240Pu observed in sediment samples collected
between January 2010 and May 2011 along the Channel - North Sea coast.
241

Am/239+240Pu

2.5

2

1.5

1

0.5

0
1960

1970

1980

1990

2000

Figure IV.42 - Changes in the 241Am/239+240Pu cumulative ratio in discharge from the La Hague plant.

Seaweed© IRSNThe radioactivity present in seaweed (fucus
serratus, fucus vesiculosus, ulva, etc.) isregularly monitored by different stations
located all along the Channel - North Sea
coast, from Roscoff to Dunkirk. Apart fromthe fact that seaweed is used in the
manufacture of products for humanconsumption (alginates) or can be used as asoil additive, these organisms incorporate andconcentrate variations in the radionuclide
content of water and are therefore abiological indicator sensitive to changes in
the concentration of radioactive substancesin sea water.

Figure IV.43 - Collecting seaweed samples near the La Hague plant.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

81Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Analyses of seaweed samples taken between
January 2010 and April 2011 revealed thepresence of different artificial radionuclides(137Cs, 60Co, 129I, plutonium isotopes, 241Am,
14C, 3H) with activity levels of the same orderof magnitude as in recent years, which
fluctuated according to the stations.

Cs (Bq/kg dry)

137

0.9
0.8
0.7
0.6
0.5

As observed on sediments, the highest values
were measured at the stations closest to the
La Hague outfall, in particular in the Anse desMoulinets, which is where the samplingstation directly affected by discharge fromthe La Hague plant is located and for which
maximum values were generally observed.
Cesium-137 was detected in most of theseaweed samples. Maximum activity wasobserved at Herquemoulin (0.78 ± 0.24 (Bq/kg dry). These low levels of activity quickly
decreased as the distance from the outfall
increased and reached values similar to orless than those measured in the fucus
vesiculosus samples taken at Oléron, awayfrom any nuclear facility (Figure IV.44).
Although its activity had decreased by afactor of more than 100 in twenty years indischarge from the nuclear facilities at La
Hague, cobalt-60 was, with cesium-137, oneof the few artificial gamma-emitting
radionuclides that could now be detected in
the marine environment west of the Cotentin(up to 3.43 ± 0.43 Bq/kg dry measured in thebay of Ecalgrain in 2010, Figure IV.45). The
decrease in discharge activity levels was also
reflected in the measurements taken.
Between 1988 and 1996, the level ofcobalt-60 activity measured in the fucus
serratus samples from the Anse des Moulinets
constantly decreased from an average of
230 Bq/kg dry in 1988 to less than 10 Bq/kg
dry in 1996. From 1997 onward, the level ofactivity evened out (activity levels measured
approximately 4 to 9 Bq/kg dry). In 2010, thelevels observed in the Anse des Moulinets
confirmed this trend: they varied between 0.8± 0.08 and 2.9 ± 0.9 Bq/ kg dry. The
measurement of this radionuclide in seaweed
was mainly explained by the discharge fromthe spent fuel reprocessing facilities.
Comparatively, the impact of nuclear power
plants was negligible.

82

Activity measured at Oléron(not affected)

0.4
0.3
0.2
0.1
0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Brown alga

Fucus serratus

Fucus vesiculosus

Figure IV.44 - Changes in cesium-137 activity observed in seaweed samples collected between
January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg dry) (values below thedecision threshold are not shown on this chart).
(values below the decision threshold are not shown on this chart).
Co (Bq/kg dry)

60

4
3.5
3
2.5
2
1.5
1
0.5
0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant result (Fucus serratus)

Significant result (Ulva)< Decision threshold

Figure IV.45 - Changes in cobalt-60 activity observed in seaweed samples collected between
January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg dry).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3
Contamination of seaweed caused bydischarge from the La Hague and Sellafield
plants was clearly reflected in theiodine-129 activity levels measured (Figure
IV.46). Although less than 3.2 Bq/kg dry inseaweed samples taken west of Roscoff, theactivity levels measured from Granville to
Dunkirk reached 55 ± 11 Bq/kg dry at Pointe
de Goury.
The slight increase in americium-241 activity
levels measured in the Channel and theNorth Sea (between 0.025 ± 0.014 and
0.198 ± 0.049 Bq/kg dry) with respect tothose measured in the Atlantic (maximum of
0.026 ± 0.01 Bq/kg dry at Concarneau) could
be attributed to added concentration bydischarge from the La Hague and Sellafield
plants.
The same observation was made forplutonium-238, with its activity levels
measured in the Channel and the North Sea
varying between 0.008 ± 0.007 and 0.23 ±0.15 Bq/kg dry (in 2010, this radionuclide
was not detected in the Atlantic). Traces of
238Pu were visible as far as Wimereux (0.045± 0.018 Bq/kg dry in May 2010).

I (Bq/kg dry)

129

60
50
40
30
20
10
0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant result (Fucus serratus)
Significant result (Fucus vesiculosus)

Significant result (Ulva)< Decision threshold

Figure IV.46 - Changes in iodine-129 activity observed in seaweed samples collected between
January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg dry).
Pu (Bq/kg dry)

239+240

0.4
0.35
0.3
0.25
0.2
0.15

With respect to plutonium isotopes 239 and
240, the activity levels measured in the Ansedes Moulinets were more than ten times
higher than those observed in the Atlantic.
Figure IV.47 shows the distribution of theseradionuclides along the coast, from Roscoff
to Dunkirk. The 238Pu/239+240Pu isotope ratioof more than 0.2, confirmed that theradionuclides along the entire coastline camefrom an industrial source (Figure IV.48).

0.1
0.05
0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant result (Fucus serratus)
Significant result (Fucus vesiculosus)

Significant result (Ulva)< Decision threshold

Figure IV.47 - Changes in plutonium-239+240 activity observed in seaweed samples collected
between January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg dry).
Pu/239+240Pu

238

1.2

Interval for which
the isotope ratio
is characteristicof industrial discharge

1
0.8
0.6
0.4

Characteristic Sellafield
plant discharge ratio: 0.2

0.2
0
-200

Characteristic atmosphericfallout ratio: 0.03
-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant result (Fucus serratus)
Significant result (Fucus vesiculosus)

Significant result (Ulva)

Figure IV.48 - Changes in 238Pu/239+240Pu activity observed in seaweed samples collected
between January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg dry).

IRSN – Report on the Radiological State of the Environment in France in 2010-201183Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Mollusks

Figure IV.49 - Collecting limpet samples.

© IRSN

Cesium-137 was only occasionally detected
at activity levels close to the decisionthresholds, between 0.026 ± 0.009 Bq/kg wet
and 0.1 ± 0.06 Bq/kg wet. Similarly, of the
141 analyses carried out along the entire
Channel - North Sea coast, only two
measurements exhibited traces ofruthenium-106 in limpet samples fromstations particularly exposed to liquid
discharge from the La Hague site: at Pointe
de Goury (0.37 ± 0.16 Bq/kg wet) and Ansedes Moulinets (0.94 ± 0.5 Bq/kg wet).

© Areva / C. Dupont

Over the analysis period covered by thisradiological report, measurements were
performed on scallops, oysters, mussels andlimpets. Among the radionuclides discharged
into liquid effluents from the La Hague andSellafield sites, the analyses revealed traces offission products (137Cs, 106Ru, 60Co, 129I) andtransuranium elements (americium andplutonium) in marine fauna (Table IV.6).

Figure IV.50 - Limpets.
Table IV.6 - Mean activity levels measured in mollusk samples collected between January 2010 and April 2011 along the Channel coast (Bq/kg wet)*.

West Cotentin coast

North Cotentin coast

Radionuclide

Scallop

OysterMussel82.6 ± 3.3

65.1 ± 3

67.7 ± 3.4< 0.1

0.067 ± 0.015< 0.09< 0.09

< 0.6

< 0.7

< 0.4

< 0.6

< 0.6

I

< 0.050.066 ± 0.018

0.057 ± 0.013< 0.060.06 ± 0.018

Cs< 0.06< 0.07< 0.045< 0.07< 0.07

Other gamma-emitting RNs(125Sb, 134Cs)< 0.22< 0.24< 0.15< 0.22< 0.23Am< 0.05< 0.06< 0.038< 0.05< 0.06Pu

0.0027 ± 0.0007

0.004 ± 0.0013

0.0076 ± 0.0016

0.0027 ± 0.0008< 0.0049

Pu

0.0044 ± 0.0013

0.009 ± 0.0032

0.0215 ± 0.0032

0.0082 ± 0.0023

0.0152 ± 0.0044

940 ± 70

470 ± 41489 ± 33980 ± 80518 ± 44

OysterMusselK

62.2 ± 2.8

76.1 ± 3.8

Co< 0.08

Ru

40
60

106

129
137

241

238

239+240

C (Bq/kg C)

14* Unless otherwise stated.

84

East Cotentin coast

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3
Iodine-129 and cobalt-60 activity levels
measured in mollusk samples from the centerof the Channel were quite typical of thedischarge from the La Hague site. The highest
activity levels were measured closest to theoutfall at La Hague, but they quickly
decreased as the distance from the site
increased.
Iodine-129 was measured from Granville toAnse du Brick at activity levels of between
0.05 ± 0.022 Bq/kg wet and 1.47 ± 0.27 Bq/
kg wet with the maximum value observed in
the limpet samples from Anse des Moulinets(Figure IV.51).
The cobalt-60 activity levels observed
fluctuated between 0.068 ± 0.031 and 0.77
± 0.11 Bq/kg wet from Carteret to Barfleur(maximum observed in limpets at Siouville,
Figure IV.52). This radionuclide was also
detected in limpet samples taken near the
Paluel and Penly NPPs (0.02 ± 0.01 Bq/kg
wet at Saint-Valéry-en-Caux and Penly).
Traces of cobalt-60 from nuclear power plantdischarge added to those from spent fuelreprocessing facilities could not be excludedin the immediate vicinity of these plants(Flamanville, Paluel and Penly NPPs).
Plutonium and americium-241 activity levels
were measured on mollusks (Table IV.6).
These radionuclides were typical of the liquid
effluents from the La Hague and Sellafieldsites. The 238Pu/239+240Pu isotope ratio of morethan 0.2, revealed that these radionuclides
came from industrial sources (Figure IV.53).
The activity levels of these transuranium
elements were significantly greater than thelevels observed in the Atlantic , butnevertheless remained relatively low and in
the same order of magnitude as in recent
years.

I (Bq/kg wet)

129

1.6
1.4
1.2
1
0.8
0.6
0.4
0.2
0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant results (Limpet)< Decision threshold
Figure IV.51 - Changes in iodine-129 activity observed in mollusk samples collected between
January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg wet).
Co (Bq/kg wet)

60

0.9
0.8
0.7
0.6
0.5
0.4
0.3
0.2
0.1
0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)Significant results (Limpet)< Decision threshold

Figure IV.52 - Changes in cobalt-60 activity observed in mollusk samples collected between
January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg wet).
Pu/239+240Pu

238

1.2
Interval for which theisotope ratio is characteristicof industrial discharge

1
0.8
0.6
0.4

Characteristic Sellafield plantdischarge ratio: 0.2

0.2

Characteristic atmosphericfallout ratio: 0.03

0
-200

-100

0

100

200

300

400

Distance from the La Hague discharge pipe (positive to the east) (km)
Scallop

MusselLimpetFigure IV.53 - Changes in the 238Pu/239+240Pu activity ratio observed in mollusk samples collected
between January 2010 and April 2011 along the Channel - North Sea coast.

IRSN – Report on the Radiological State of the Environment in France in 2010-201185

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Crustaceanswet. Cobalt-60 and transuranium
elements were only occasionallydetected. Along the entire coastline,
americium could only be measured twicein the 21 analyses performed (0.0065 ±0.0025 (Bq/kg) in Carteret and 0.0057 ±0.0031 Bq/kg wet in Urville-Nacqueville).

Am, 14C) in some samples, due to liquidd i s c h a rge f ro m t h e s p e n t f u e lreprocessing plants at La Hague andSellafield (Table IV.7).

241

Between January 2010 and April 2011,
radiological analyses were performed on
crustaceans (common crabs, spider crabs,
lobsters) caught along the Channel
coasts. They revealed the presence ofartificial radionuclides (129I, 60Co, 239+240Pu,

Iodine-129 was regularly measured at
activity levels between 0.104 ±0.048 Bq/kg wet and 1.31 ± 0.22 Bq/kg

Table IV.7 - Mean activity levels measured in crustacean samples collected between January 2010 and April 2011 along the Channel coast (Bq/kg wet)*.

Near the La Hague site
Carteret harbor

Auderville
Goury

Commoncrab

Spider crab

Spider crab

Common crab

Lobster

Common crab

40K

60 ± 883 ± 1164 ± 861.3 ± 2.7

36.8 ± 1.8

60.1 ± 3

Co

< 0.1

0.144 ± 0.041

0.135 ± 0.032

0.112 ± 0.021< 0.07< 0.09

Ru

< 0.9

< 0.9

< 0.9

< 0.6

< 0.46

< 0.6

I

nm

< 0.17< 0.220.24 ± 0.032

0.291 ± 0.03

0.097 ± 0.02

Cs

< 0.1

< 0.11< 0.09< 0.07< 0.06< 0.07

Other gamma-emitting
RNs (124Sb, 125Sb, 110mAg,
134Cs, 58Co, 54Mn)< 0.98< 0.96< 1.07< 0.21< 0.17< 0.22Am

nm0.0065 ± 0.0025< 0.017< 0.06< 0.045< 0.06Pu

nm< 0.0023< 0.01< 0.0034< 0.0048< 0.0039

239+240Pu

nm< 0.0023

0.018 ± 0.008

0.0049 ± 0.0012< 0.0048< 0.0034

C (Bq/kg C)

nm

nm

nm

491 ± 31374 ± 20328 ± 25

Radionuclide

60

106

129
137

241

238

14

Near
Cherbourg naval port

West Cotentin coast

Near
Paluel NPP

Near
Penly NPP

Urville - Nacqueville
Hameau deNacqueville

Tourlaville

St-Pierre-en-Port

PaluelVasterival

Penly

Common crab

Commoncrab

Spider crab

Spider crab

Spider crab

Commoncrab

K

100 ± 1362 ± 855 ± 861 ± 858 ± 665 ± 7Co< 0.17< 0.09< 0.06< 0.05< 0.1< 0.03

Ru

< 1.4

< 0.8

nm

nm

nm

nm

I

0.25 ± 0.11

< 0.15

nm

nm

nm

nm

Cs

< 0.21< 0.09< 0.04

< 0.1

< 0.1

< 0.08Other gamma-emitting
RNs (124Sb, 125Sb, 110mAg,
134Cs, 58Co, 54Mn)< 1.85< 1.06< 0.14< 0.13< 0.13< 0.17Am

0.0057 ± 0.0031< 0.032

nm

nm

nm

nm

Pu

< 0.0031< 0.01

nm

nm

nm

nm

Pu

< 0.0046< 0.01

nm

nm

nm

nm

nm

nm

nm

nm

nm

nm

Radionuclide

40
60

106

129
137

241

238

239+240

C (Bq/kg C)

14* Unless otherwise stated.
nm: not measured
86

North Cotentin
coast

Roscoff

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3

Fish of different species were caught
between February 2010 and April 2011 in
the Channel, off Roscoff and near the main
nuclear facilities along the coast (La Hague
site, Cherbourg Naval Port, Paluel and Penly
NPPs).

one sample of plaice caught in Cherbourg
harbor in February 2010 exhibited traces ofamericium-241 (0.0033 ± 0.0027 Bq/kg
wet).

Table IV.8 shows that traces of cesium-137
were present in most samples, with lowlevels of activity between 0.06 ± 0.01 Bq/
kg wet and 0.31 ± 0.03 Bq/kg wet. They
were relatively close to those observed off
the Atlantic coast . Other artificial
radionuclides (129I, 241Am, HTO) attributable
to liquid effluent discharge from thereprocessing facilities at La Hague in France
and Sellafield in England were measured insome samples. Iodine-129 activity levels
measured in four fish caught in the vicinityof the La Hague site were between 0.035 ±0.018 Bq/kg wet and 0.68 ± 0.13 Bq/kg
wet (38 measurements in total werecarried out in the Channel over the period
in question). Similarly, of the 36 samples
analyzed along the entire coastline, only

© IRSNFish

Figure IV.54 - Dissecting a plaice before analysis.

Table IV.8 - Mean activity levels measured in samples of fish caught in the Channel between February 2010 and April 2011 (Bq/kg wet)*.

Near the La Hague site
Roscoff

Carteret

Auderville

Barfleur

Cotentinwest coast

Cotentinwest coast

Cotentinwest coast

Skate

DogfishMackerelSpotteddogfish

Fish

Fish

Fish

40

K

87 ± 1185 ± 10120 ± 1578 ± 9117.4 ± 3.3

95.1 ± 3

88.9 ± 2.8

Co< 0.022< 0.03< 0.024< 0.026< 0.09< 0.07< 0.06Ru< 0.16< 0.23< 0.17< 0.19< 0.6< 0.43< 0.38I< 0.03< 0.04< 0.032< 0.037

0.065 ± 0.009< 0.040.045 ± 0.007

Cs

0.151 ± 0.021

0.102 ± 0.03

0.086 ± 0.012

0.154 ± 0.018

0.082 ± 0.012

Other gammaemitting RNs(124Sb, 125Sb,
110mAg, 134Cs,
58Co, 54Mn)< 0.22< 0.35< 0.20< 0.24< 0.22< 0.16< 0.15Amnm

nm< 0.0027< 0.007< 0.05< 0.041< 0.04Pu

nm

nm< 0.0013< 0.0021< 0.0042< 0.0038< 0.0033

Pu

nm

nm

< 0.0013< 0.0021< 0.004< 0.0031< 0.0032

C (Bq/kg C)

252 ± 1.4358 ± 1.7

307 ± 1.4

298.5 ± 1.7

285 ± 13274 ± 24270 ± 14

HTO

< 3.6

5.3 ± 1.5< 2.9

4.1 ± 1.5

nm

nm

nm

OBT

nm

nm

1.32 ± 0.07

nm

nm

nm

nm

Radionuclide

60

106

129
137

241

238

239+24014

0.128 ± 0.019 0.122 ± 0.019* Unless otherwise stated.
nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010-201187Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Table IV.8 (continued) - Mean activity levels measured in samples of fish caught in the Channel between February 2010 and April 2011 (Bq/kg wet)*.

Near Cherbourg naval port

Near Paluel NPP

Urville- NacquevilleCherbourg

St-Pierreen-Port

WrassePlaiceSea bass

Sea bass

40K

89 ± 1192 ± 11130 ± 14Co

< 0.038< 0.038Ru< 0.31

I

Near Penly NPP
Vasterival

Penly

Le Tréport

TurbotDover sole

Dover sole

Plaice120 ± 1394 ± 9140 ± 1493 ± 997 ± 12< 0.01< 0.01< 0.02< 0.02< 0.01< 0.029< 0.31

nm

nm

nm

nm

nm

< 0.21< 0.049< 0.049

nm

nm

nm

nm

nm

< 0.041Cs

0.105 ± 0.02

0.093 ± 0.019

0.31 ± 0.03

0.28 ± 0.03

Othergammaemitting RNs(124Sb, 125Sb,
110mAg, 134Cs,
58Co, 54Mn)< 0.48< 0.55< 0.02< 0.02< 0.04< 0.08< 0.04< 0.23Am< 0.005

0.0033 ± 0.0027

nm

nm

nm

nm

nm

< 0.006Pu< 0.005< 0.004

nm

nm

nm

nm

nm

< 0.006

239+240Pu< 0.005< 0.004

nm

nm

nm

nm

nm

< 0.006

C (Bq/kg C)

414.5 ± 2

287.5 ± 1.4

nm

nm

nm

nm

nm

365.2 ± 1.7

HTO

< 3.6

< 3.5

nm

nm

nm

nm

nm

< 16

OBT

0.818 ± 0.042

nm

nm

nm

nm

nm

nm

0.46 ± 0.09

Radionuclide

60

106

129

137

241

238

14

Paluel0.08 ± 0.01 0.07 ± 0.02 0.06 ± 0.01

0.064 ± 0.027

Atlantic coast
The Atlantic coast was monitored between
Arcachon and Brest, as described below.

Sea water
Table IV.9 - Tritium and cesium-137 activity levels in water samples from the Atlantic (Bq/L).

Atlantic coastOn the Atlantic coast, tritium was measured
in concentrations significantly lower thanthose measured in the North Sea, except in
the estuaries of rivers on which NPPs arelocated (Loire and Garonne). Very low levelsof residual cesium-137 dating back to
Chernobyl and fallout from atmosphericnuclear weapons tests could still be measured
in the Atlantic Ocean at activity levels of justa few mBq/L (Table IV.9).

88

Radionuclide

Arcachon

Pornichet

Tritium

0.158 ± 0.007

6.0 ± 2.4

Cesium-137

0.0054 ± 0.0016

0.0076 ± 0.0018

nm: not measured

Brest naval port- Île Longue
No artificial radionuclide was detected in thesea water samples taken in the vicinity of the
Brest naval port during the period in question.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3
Sediments

Table IV.10 - Mean activity levels measured in sediment samples from the Atlantic coast (Bq/kg dry).

Radionuclide

Arcachon

OléronPornichetK

188 ± 14228 ± 15192 ± 11

Co

< 0.2

< 0.16< 0.12Cs< 0.150.309 ± 0.049

0.101 ± 0.028

Ac

4 ± 0.6

4.96 ± 0.48

7.7 ± 0.6

Am

< 0.1

< 0.16< 0.21Pu< 0.22< 0.11< 0.21Pu< 0.220.12 ± 0.07

0.17 ± 0.1

In 2010 and at the beginning of 2011,
samples of marine sediments were taken
every six months at Pornichet and Oléron
and annually at Arcachon (Table IV.10).

40
60

137
228

Potassium-40 was the main gamma-emitting
natural radionuclide measured at activities ofbetween 168 ± 16 and 520 ± 50 Bq/kg dry.
Cesium-137 and plutonium isotopes 239 and
240, attributable to fallout from atmosphericnuclear tests, were also observed in thesesamples. The cesium-137 concentrations
measured in the samples collected were low(maximum 3.32 ± 0.32 Bq/kg dry in Oléron),or even below the decision thresholds inArcachon. The variability observed was
mainly due to the diversity of the matrices
sampled (sand in Arcachon, mud in Oléron).
The plutonium-239+240 activity levels inmarine sediments reached 0.12 ± 0.07 Bq/kg
dry in Oléron and 0.17 ± 0.1 Bq/kg dry in
Po r n i c h e t . T h e a c t i v i t y o f t h e s etransuraniumelements remained below thedecision thresholds in Arcachon.
Brest naval port- Île Longue
Annual, quarterly, bimonthly or monthly
samples of sediments were taken from sevenstations in Brest harbor (Table IV.11).

241

238

239+240

The radioactivity measured was inherently
natural (40K, 228Ac). Among the artificial
radionuclides measured, only traces ofcesium-137 from past atmospheric fallout
were detected almost systematically in all
the samples with activity levels between 0.17
± 0.08 Bq/kg dry and 2.89 ± 0.38 Bq/kg dry.
Other artificial radionuclides wereoccasionally measured in samples from Ansed u Fre t : c o b a lt- 6 0 , s t ro n t i u m - 9 0 ,americium-241 and plutonium-239+240.
Cobalt-60 was detected occasionally inactivity levels ranging from 0.48 ± 0.17 and1.38 ± 0.24 Bq/kg dry (three of the 18 tests
conducted between January 2010 and May
2011 had measurements above the decisionthresholds). The strontium-90 activity of oneof the three samples was 7.9 ± 1.1 Bq/kg dry.

© French navy

Atlantic coast

Figure IV.55 - First sieving of sediment samples
on board the French Navy's Palingrin II near
Brest.

Table IV.11 - Mean activity levels measured in sediment samples collected in the vicinity of Brest naval port (Bq/kg dry).

Brest

Plougastel-Daoulas

CrozonRoscanvel

Saint-Annedu Portzic

Rade-AbriKéraliou

Banc
du CaroAnse
du FretBayof Roscanvel

Roscanvel
harborBeachsandMarinesediment

Beach sandMarinesediment

Marinesediment

Marinesediment

Beach sandK

415 ± 16518 ± 10461 ± 16362 ± 15

273.7 ± 3.6

304 ± 8316 ± 8Co

< 0.17< 0.22< 0.09< 0.210.194 ± 0.023< 0.14< 0.11Cs

0.45 ± 0.16

2.77 ± 0.16

0.17 ± 0.08

1.16 ± 0.24

0.655 ± 0.045

0.92 ± 0.12

0.18 ± 0.06

Ac

13.7 ± 2

23.4 ± 1.6

21.5 ± 2.7

17.3 ± 2.5

9.1 ± 0.6

17.9 ± 2.5

18.2 ± 1.7

Sr

nm

nm

nm

nm

0.43 ± 0.12

nm

nm

Am

nm

nm

nm

nm

0.2 ± 0.08

nm

nm

Pu

nm

nm

nm

nm

< 0.14

nm

nm

Pu

nm

nm

nm

nm

0.58 ± 0.17nm

nm

Radionuclide

40
60

137
228
90
241

238

239+240

nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

89

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

SeaweedTable IV.12 - Mean activity levels measured in seaweed samples from the Atlantic coast (Bq/kg dry)*.

Atlantic coast
As with sediments, the radioactivity measured
in seaweed samples from the Atlantic coast
was almost exclusively represented bypotassium-40 (between 690 ± 70 Bq/kg dry
and 1620 ± 140 Bq/kg dry) and, dependingon the stations, by a few traces of artificial
radionuclides suc h as cesium-137,
americium-241 and plutonium isotopes(Table IV.12). The presence of these artificial
radionuclides in seaweed found on Frenchcoasts was due to fallout from atmosphericnuclear weapons tests.

OléronPornichetConcarneau

Fucus
vesiculosus

Fucus
vesiculosus

Fucus
serratus

K

1060 ± 60

881 ± 50

1,090 ± 50

Co

< 0.35< 0.34< 0.47Cs

0.39 ± 0.06

0.38 ± 0.06

0.26 ± 0.06

Other gamma-emitting
RNs(106Ru, 124Sb, 125Sb, 110mAg,
134Cs, 58Co, 54Mn)

<4.8

< 4.5

< 6.1

Am

< 0.016< 0.0440.026 ± 0.01

Pu

< 0.014< 0.021< 0.015

239+240Pu

0.02 ± 0.007

0.032 ± 0.011

0.022 ± 0.008

C (Bq/kg C)

236.5 ± 0.8

241.3 ± 0.8

241.7 ± 1.7

HTO (Bq/kg wet)

< 3.8

< 4.5

< 3.5

OBT

0.216 ± 0.006

0.73 ± 0.037

nmRadionuclide

40

60

137

Brest naval port- Île Longue

238

14

* Unless otherwise stated.
nm: not measured© French navy

Samples of seaweed (fucus serratus, fucus
spiralis, fucus vesiculosus) were regularlycollected from various points in Brest harbor.
The natural radioactivity measured inseaweed was mainly due to potassium-40(1,314 ± 12 Bq / kg dry on average).
Cesium-137 was occasionally detected in
fucus vesiculosus samples from the SainteAnne du Portzic and Kéraliou stations at levels
very close to the decision thresholds (0.31 ±0.21 Bq/kg dry in March 2011 and 0.42 ±0.23 Bq/kg dry in January 2011 respectively).
The activities of artificial radionuclides
detected (134Cs, 60Co, 58Co, 54Mn) remained
below the decision thresholds (Table IV.13).

241

Figure IV.56 - Collecting seaweed samples on board the Palingrin II near Brest.

90

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3
Table IV.13 - Mean activity levels measured in seaweed samples collected in the vicinity of Brest naval port (Bq/kg dry)*.

Brest
Sainte-Anne-du-Portzic

Plougastel-Daoulas
Kéraliou

CrozonAnse du Fret

Roscanvel
Roscanvel harbor

Fucus
serratus

Fucus
vesiculosus

Fucus
serratus

Fucus
vesiculosus

Fucus
serratus

Fucus
spiralis

Fucus
vesiculosus

Fucus
serratus

K

1,440 ± 50

1,090 ± 38

1,620 ± 60 1,243 ± 44

1,445 ± 28

1,057 ± 42

1,192 ± 30

1,785 ± 43 1,231 ± 30

Co

< 0.29< 0.34< 0.31< 0.28< 0.34< 0.3< 0.26< 0.32< 0.27Cs< 0.250.31 ± 0.21

< 0.290.42 ± 0.23

< 0.31< 0.27< 0.26< 0.29< 0.26

Other
gammaemitting
RNs (134Cs,
58Co, 54Mn)< 0.55< 0.59< 0.29< 0.27< 1.42< 0.51< 0.26< 0.62< 0.54

C (Bq/kg C)

nm

nm

nm

nm

244.2 ± 1.4

nm

nm

nm

nm

Radionuclide

40
60

137

14

Fucus
vesiculosus* Unless otherwise stated.
nm: not measured

Mollusks

depending on the species and samplingstations (Table IV.14).

Atlantic coast
The radioactivity measured in molluskscaught annually or biannually along theAtlantic coast was mostly natural ( 40K,
210Po). Potassium-40 activity varied between
23.4 ± 2.7 Bq/kg wet and 60 ± 5 Bq/kg wet
and polonium-210 activity between 8.6 ±0.9 Bq/kg wet and 31.4 ± 2.5 Bq/kg wet,

Traces of americium-241 were measured inmussel samples from Oléron. Similarly,
traces of plutonium-239+240 fromatmospheric fallout from past atmospherictests were present in almost all the samples
analyzedT able IV.14 - Mean activity levels measured in mollusk samples from the Atlantic coast (Bq/kg wet)*.

Arcachon

OléronPornichetConcarneau

OysterOysterMusselMusselMusselK

26.6 ± 1.9

26 ±
2.5

50.7 ± 4.9

60 ± 540.1 ± 2.7

Co< 0.029<0.024< 0.05< 0.037< 0.04Cs< 0.048< 0.02< 0.042< 0.033< 0.035

Other
gammaemitting
RNs(106Ru, 124Sb,
125Sb, 110mAg,
134Cs, 58Co,
54Mn)< 0.46< 0.4< 0.78< 0.6< 0.68Po

31.4 ± 2.5

8.6 ±
0.9

31.2 ± 3.1

17 ± 2.4

14.1 ± 1.5

Am< 0.0027

nm

0.0024 ± 0.0016 < 0.0024< 0.002Pu< 0.0017

nm< 0.0016

Pu

0.0014 ± 0.001

nm

0.0017 ± 0.001

40

60

137

210

241

238

239+240< 0.0013< 0.0015© IRSNRadionuclide

Figure IV.57 - Weighing limpet samples.

< 0.0013 0.0014 ± 0.0009* Unless otherwise stated.
nm: not measured
IRSN – Report on the Radiological State of the Environment in France in 2010-201191

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Brest naval port- Île Longue
No gamma-emitting radionuclides ofartificial origin were detected in mollusk
samples from Brest harbor (Table IV.15).
Table IV.15 - Mean activity levels measured in mollusk samples collected in the vicinity of the Brest naval port (Bq/kg wet).

Brest

LogonnaDaoulas

Plougastel-Daoulas

Lanvéoc

CrozonPointede Lanvéoc

Anse du Fret

SaintAnne-duPortzic

Kéraliou

Banc
du CaroLimpetLimpetScallop

OysterMusselOyster

K

66.1 ± 3.2

66.5 ± 4.7

66 ± 629.4 ± 4.5

36 ± 6

Co< 0.046< 0.11< 0.14< 0.09Cs< 0.044< 0.1< 0.12Other gammaemitting RNs(134Cs, 58Co, 54Mn)< 0.09< 0.11< 0.13

Radionuclide

40

60

137

Crustaceans

Bay ofRoscanvel

Roscanvel
harborLimpetLimpetLimpet33.9 ± 1.3

71.1 ± 1.9

68.4 ± 549.4 ± 2.6< 0.1< 0.023< 0.07< 0.11< 0.042< 0.08< 0.1< 0.022< 0.06< 0.12< 0.042< 0.23< 0.4< 0.023< 0.11< 0.12< 0.09

Table IV.16 - Mean activity levels measured in crustacean samples collected in the vicinity of Brest naval
port (Bq/kg wet).

Atlantic coast
In 2010, the radioactivity measured incommon crabs caught annually in
Concarneau consisted predominantly ofpotassium-40, with specific activity of 56 ±8 Bq/kg wet.

Radionuclide

Brest naval port- Île Longue

Brest
Rade-Abri

Roscanvel
Bay of Roscanvel

Commoncrab

Spider crab

Spider crab

40K

58 ± 730.2 ± 1.6

56.4 ± 2.1

32.3 ± 1.3

Co< 0.08< 0.024< 0.08< 0.034

Cs< 0.08< 0.027< 0.08< 0.04

Other gammaemitting RNs(134Cs, 58Co, 54Mn)< 0.39< 0.026< 0.14< 0.11137

As was the case with mollusks, no gammaemitting radionuclide of artificial origin was
detected in the annual samples (Table IV.16):-common crabs from Rade-Abri;- common crabs and spider crab samples
from Anse du Fret;- spider crabs from the Bay of Roscanvel.

92

CrozonAnse du Fret

Common crab

60

The activities of other gamma-emitting
radionuclides were below the decisionthresholds of the measuring instruments
used.

Roscanvel

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3
Fish

Table IV.17 - Activity levels measured in samples of fish caught off the Atlantic coast (Bq/kg wet)*Atlantic coast

Arcachon

OléronConcarneau

Mullet

Fish

Fish

40

K

95 ± 1295 ± 12107 ± 13Co

< 0.034< 0.043< 0.033

Cs< 0.0410.045 ± 0.016

0.22 ± 0.031

Other gamma-emitting
RNs (106Ru, 124Sb, 125Sb,
110mAg, 134Cs, 58Co, 54Mn

< 0.57< 0.73< 0.57C (Bq/kg C)

238.2 ± 1.4

237.8 ± 1.4

247.2 ± 1.7

HTO

< 3.4

< 3.5

< 3.7

OBT

0.054 ± 0.005

0.0659 ± 0.0047

nmRadionuclide

In 2010, the radioactivity measured in fishcaught off the Atlantic cost consisted
predominantly of potassium-40, whose
specific activity was approximately 100 Bq kg
wet. Apart from a few traces of cesium-137
from past atmospheric fallout measured in
Oléron and Concarneau, other gammaemitting radionuclide activity was below thedecision thresholds (Table IV.17).

60

137

Brest naval port- Île Longue

14

Radiological analyses of marine fauna wereregularly performed at various points in Brest
harbor. Apart from naturally occurring
potassium-40 in all the samples, traces ofcesium-137 were detected in most fishsamples (Table IV.18). No other gammaemitting radionuclides (134Cs, 58Co, 60Co, 54Mn)
were detected.

* Unless otherwise stated.
nm: not measured

Table IV.18 - Mean activity levels measured in samples of fish caught in the vicinity of Brest naval port (Bq/kg wet).

Brest
Radionuclide

Plougastel-Daoulas

Rade-AbriGrande Digue

CongerConger

DogfishCuckoo wrasse

Dover sole40K

126 ± 1559.8 ± 2.9

108 ± 1371 ± 997 ± 12Co< 0.034< 0.09< 0.05< 0.09< 0.07Cs

0.087 ± 0.017

0.129 ± 0.039

0.095 ± 0.044

0.069 ± 0.03

< 0.06

Other gammaemitting
RNs (134Cs, 58Co, 54Mn)< 0.14< 0.08< 0.23< 0.3< 0.2360

137

Radionuclide

Bouée du Renard

Banc du Caro

CrozonRoscanvel

Anse du Fret

Bay of Roscanvel

CongerSkate

DogfishWrasseUnidentified fish

DogfishK

64.2 ± 2.8

84.2 ± 4.4

67.4 ± 1.9

83.1 ± 4.7

101.1 ± 4.5

55.7 ± 2.3

Co

< 0.1

< 0.07< 0.07< 0.07< 0.06< 0.05Cs

0.105 ± 0.03

0.09 ± 0.05

0.069 ± 0.018

0.13 ± 0.05

< 0.070.088 ± 0.033

Other gammaemitting
RNs (134Cs, 58Co, 54Mn)< 0.15< 0.15< 0.11< 0.13< 0.13< 0.0540
60

137

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

93

IRSN• FOCUS

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIESCarbon-14 in the marine and coastal environment:
Carbon-14 is one of the radioactive
isotopes of carbon. Its presence in theenvironment arises from its natural
production via the action of cosmic
neutrons on nitrogen atoms in thes t ra t o s p h e re a n d i n t h e u p p e r
troposphere and also fromanthropogenic activity (atmosphericnuclear explosions, nuclear industries).

promontory of La Hague and decreased
rapidly, as the distance from the liquid
discharge outfall at La Hague increased,t o le v e l s c lo s e t o t h e p re s e n t
background (about 240 Bq/kg ofcarbon). The activities measured off theAtlantic and Mediterranean coasts werebroadly similar to the environmental
background.

Spent fuel reprocessing plants and, to alesser extent, nuclear power plants, aret o d ay m a i n l y r e s p o n s i b l e f o ranthropogenic carbon-14 discharge inthe environment. Liquid carbon-14
discharge from the Areva plant at La
Hague in the marine environment
steadily increased between 1985 and2000 to about 10 TBq (1013 Bq) in 2000.
In 2010, it rose to 7.34 ( TBq)
(7.34×1012 Bq). In the same year, theSellafield plant in England discharged
4.4 (TBq) (4.4×1012 Bq) of 14C into themarine environment. In comparison, theannual worldwide production rate ofnatural 14C was approximately 1,540(TBq) (1.540 × 1015 Bq).

Carbon-14 in seaweed

In the environment, carbon-14 has thesame behavior as the stable isotope 12C(which represents 99% of carbon): it
follows the carbon cycle. It is therefore
found in carbon-based living tissue.

600

The impact of reprocessing plants was
mainly visible in the immediate vicinity of
the La Hague site, from Carteret to Barfleur.
The highest values were observed in Ansedes Moulinets, which is where the samplingstation directly affected by discharge fromthe site is located and for which maximum
values were generally observed (averagecarbon activity of 524 ± 29 Bq/kg measured
in fucus serratus, more than twice the levels

Carbon-14 in mollusks
Between January 2010 and April 2011, thequantification of carbon-14 in mollusks
focused on the annual, twice-yearly orquarterly sampling of limpets, mussels,
oysters and scallops.
The activity levels measured in mollusk
samples collected near the La Hague site,from Carteret to Barfleur, were almost fourtimes higher than those typically observedin a natural environment away from any
nuclear facility, reflecting the impact ofliquid discharge from spent fuelreprocessing facilities on marine aquatic
fauna (Figures IV.59 and IV.60).

C (Bq/kg carbon)

14

900
800
700
500
400
300
200

Natural radioactivity

100

Between January 2010 and April 2011,
measurements were conducted todetect this radionuclide in different
matrix samples (seaweed, mollusks,
fish) collected along the coasts ofmetropolitan France. The measurements
included both natural carbon andcarbon added as a result of the activity
levels of fuel reprocessing plants at La
Hague and Sellafield as well as from
nuclear power plants. The impact
assessment had to take the naturalcomponent into account.

usually found away from any nuclear
activity). In Roscoff, Honfleur, Wimereux
and Dunkirk, the levels observed weresimilar to the background (Figure IV.58).

0
-200

-100
0
100
200
300
400
Distance from the La Hague discharge pipe (positive to the east) (km)LimpetFigure IV.58 - Changes in carbon-14 activity observed in seaweed samples collected between
January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg of C).
C (Bq/kg carbon)

14

900
800
700
600
500
400

In general, the results showed that thetraces of 14C in living organism samples
from the Channel and the North Sea,
which are attributable to liquid
discharge from the La Hague andSellafield plants, were higher than thosefrom NPPs along the Channel coasts(Flamanville, Paluel Penly). The highest
activity levels were concentrated at the

94

300
200

Natural radioactivity

100
0
-200

-100
0
100
200
300
400
Distance from the La Hague discharge pipe (positive to the east) (km)LimpetFigure IV.59 - Changes in carbon-14 activity observed in limpet samples collected between
January 2010 and April 2011 along the Channel - North Sea coast (Bq/kg of C).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3

Dunkirk

Among the sampling stations monitored,
the highest average levels were observed at
Pointe de Goury (average carbon activity of
688 ± 37 Bq/kg in limpets).
Of the different species analyzed, oysters
exhibited the highest values. The averagecarbon levels observed reached 940 ±70 Bq/kg in oyster samples from the west
coast of the Cotentin and 980 ± 80 Bq/kg
in oysters from the east coast of Cotentin(maximum 1,160 ± 210 Bq/kg in October2010). In comparison, oyster samples fromthe Arcachon basin in 2010 showed anaverage carbon activity of 259.4 ± 1.1 Bq/
kg, comparable to the present reference
level.

250 ± 1

Close-up
Le Tréport
365.2 ± 1.7

Honfleur

Roscoff

244.9 ± 0.7

241 ± 1.4
252 ± 1.4

Brest
244.2 ± 1.4

Concarneau
241.7 ± 1.7
247.2 ± 1.7

Pornichet241.3 ± 0.8

Oléron236.5 ± 0.8
237.8 ± 1.4

Carbon-14 in crustaceans

Arcachon259.4 ± 1.1
238.2 ± 1.4

Samples of common crabs collected
quarterly near the La Hague site exhibitedcarbon-14 activity levels above the current
reference levels (on average, 491 ± 31 Bq/
kg of carbon on the west coast and 328 ±25 Bq/kg of carbon on the north coast).
Similarly, lobsters caught on the west coast
contained traces of carbon-14, due mainly
to discharge from the La Hague plant(average carbon activity measured: 374 ±20 Bq/kg).

ToulonLa Seyne-sur-Mer
239.3 ± 1.4

Auderville(Goury)Carbon-14 in fish
Radioactivity in fish is monitored annuallyat twelve sampling stations along the
French coast. Sampling is carried out more
frequently on the Cotentin coasts, closest
to the outfall at La Hague. Various species,
including plaice, mackerel, dogfish, spotted
dogfish, wrasse, mullet, Fleury skate andsea bass were analyzed (Figure IV.60).
The 14C activities measured in the Channel,
from Carteret to Le Tréport (414.5 ± 2 Bq/
kg wet in wrasses caught in UrvilleNacqueville) are generally higher than thereference levels observed away from any
nuclear facility (238.2 ± 1.4 Bq/kg wet inmullets caught in Arcachon).

238.7 ± 1.4
235.5 ± 1.4

460 ± 27688 ± 37
307 ± 1,4

Urqueville-Nacqueville
425 ± 31559 ± 39
414,5 ± 2

Querqueville
Herqueville(Anse des Moulinets)

411 ± 32

Cherbourg

524 ± 29592 ± 31347.3 ± 1.7
355 ± 2287.5 ± 1.4

Barfleur
294.8 ± 0.8
471 ± 36298.5 ± 1.7

Carteret309.4 ± 0.9
501 ± 39358 ± 1.7

Seaweed (fucus, ulva, posidonia)
Mollusks (oysters, limpets)
Fish (mullet, mackerel, dogfish, wrasse, plaice, skate, sea bass)
Figure IV.60 - Carbon-14 activity observed in marine aquatic plants, mollusks and fish caught
between January 2010 and April 2011 along the French coast (Bq/kg of carbon).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

95

IRSN • FOCUS

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

Bound tritium
Tritium is a natural and artificial radionuclide.
"Natural" tritium comes mainly from theinteraction of cosmic neutrons with nitrogenor oxygen in the air. The annual worldwide
production of natural tritium is 7.4 × 1016 Bq.
In the past, "artificial" tritium in theenvironment was mainly the result of global
fallout following atmospheric nuclear
weapons tests. These persistent traces tend
to diminish and disappear. Tritium is also
produced by most nuclear facilities. Table
IV.19 lists the main artificial sources of tritiumin the marine waters of metropolitan France.
As a hydrogen isotope, tritium is part of thecycle of this element in the naturalenvironment. It is a radionuclide, which, as
tritiated water, is highly mobile. In plants
and animals, it is found in cell water (freetritium or HTO) and also in organic matterin the form of organically bound tritium(OBT). The first fraction quickly exchanges
with the hy drogen present in theenvironment; its measurement can be used
to characterize an environment at the timeof sampling. On the other hand, boundtritium is representative of environmental
contamination throughout the formationof organic matter. The measurement oftritium bound to organic matter containedin bio-indicators is a very good indicator forassessing the impact of a nuclear facility on
its environment.
In 2010, seaweed and fish were sampled at
different stations along the French coast.
Their bound tritium activity was determinedby mass spectrometry. This particularly
efficient technique makes it possible tomeasure very low detection limits, which isuseful for environmental assessment
applications.

Table IV.19 - Tritium activity released into the marine environment in 2010 (TBq*).

Discharge activity levels (TBq*)

Nuclear facilities

Liquid discharge

Gaseous discharge

Areva La Hague

9,950

56.8

Flamanville NPP

49.3

0.68

Paluel NPP

88.6

2.11

Penly NPP

64.8

2.08

Gravelines NPP

74

3.34

Sellafield plant (England)

1,400

98

* 1 (TBq) (terabecquerel): 1,012 Bq

Bound tritium in seaweed
Samples of seaweed (fucus serratus
and fucus vesiculosus) were collectedfrom six stations on the Atlantic,
Channel and North Sea coats. The
bound tritium activity levels measured
were very low, but neverthelessrevealed additional concentration due
to liquid discharge from the spent fuelreprocessing plants at La Hague andSellafield (Figure IV.62). The impact ofthese facilities was measured from
Car teret to Dunkirk, with the
maximum activity observed in fucus
vesiculosus samples from Honfleur(1.7 ± 0.26 Bq/kg dry). This activity
was eight times higher than thatmeasured in fucus vesiculosus samples
from Oléron (0.216 ± 0.006 Bq/kgdry), which was outside the influenceof any nuclear facility.

27,00021,65017,45014,05011,350
9,150
7,350
5,950
4,800
3,850
3,100
2,500
2,025
1,630
1,315
1,060
855
690
555
445
360
290
235
190
150
125
100
80
65
50
40
0

64
62
60
58
56
54
52
50
48
46

Simulated element: Tritium
IFREMER/IRSN MARS model
calculation mesh 5.6 km
French and English annual discharges,
true wind
Date : 22/12/2002

Tritium
44 Bq/m3
-12

-10

-8

-6

-4

-2

0

2

4

6

8

10

12

Figure IV.61 - IRSN simulation of tritium dispersion over the European northwest plateau.

96

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

14

IV.3

The distribution of bound tritium activities
measured in seaweed in the Channel andthe North Sea corresponded exactly to thedispersion model of tritium released by the
La Hague and Sellafield plants, thus
confirming the industrial source of thetritium measured (Figure IV.61). The
activity observed at Pornichet (0.73 ±0.037 Bq/kg dry), three times higher thanthat measured at Oléron, indicated a slight
concentration from liquid effluent
discharge from NPPs upstream along theLoire.

Dunkirk
1.3 ± 0.6 Bq/kg dry

Close-up
Le Tréport
0.46 ± 0.09 Bq/kg wet

Honfleur
1.7 ± 0.3 Bq/kg dry

Pornichet
0.73 ± 0.04 Bq/kg dry

Bound tritium in fish
In 2010, fish were caught near Arcachon,
Oléron, Auderville, Urville-Nacqueville andLe Tréport. The tritium measured in the fishcaught in the Atlantic mainly occurs
naturally.

Oléron0.216 ± 0.006 Bq/kg dry
0.066 ± 0.005 Bq/kg wet

Arcachon
0.054 ± 0.005 Bq/kg wet

In the Channel, the levels measured at thethree sampling stations were significantly
higher than those observed in the Atlantic.
A factor of 24 was observed between
mullet caught at Arcachon and mackerelcaught at Auderville, which is a station
particularly exposed to liquid discharge
from the La Hague site (Figure IV.62).
Although differences between species canbe observed, the discrepancy mainly
indicated added tritium concentration of
the marine environment by the reprocessing
plants. This impact must nevertheless beweighted, as the levels recorded are
extremely low.

Auderville (Goury)
1.32 ± 0.07 Bq/kg dry

Urqueville-Nacqueville
0.82 ± 0.04 Bq/kg dry

Barfleur
1.27 ± 0.04 Bq/kg drySaint-Georges-de-la-Rivière
1.46 ± 0.05 Bq/kg dry

Seaweed(fucus)
Fish (mullet, mackerel, dogfish, wrasse, plaice, skate, sea bass)
Figure IV.62 - Bound tritium activity observed in seaweed and fish samples collected between
January 2010 and April 2011 along the Channel, North Sea and Atlantic coasts (Bq/kg dry forseaweed, Bq/kg wet for fish).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

97

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIESThe Mediterranean coast
Sea water
Following the reorganization of IRSN'smonitoring strategy in the marine
environment in 2009, monthly samplingof seawater by the Regional HealthAgencies came to a halt. The quantity ofsamples collected (10 to 20 liters) did notreach satisfactory decision thresholds. A
test sample of a large volume of sea water(500 liters) was taken from Toulon harborin 2010. The dissolved cesium-137 was
measured by gamma spectrometry at an
activity concentration of 0.0015 ±0.00015 Bq /L . These large-volume
samples were then taken at some of themarine stations in IRSN's monitoring
network.

to their ability to accumulate thecontaminants present in coastal waters andfish were chosen due to their higher trophic
level (thus highlighting a biomagnification
phenomenon).
The 2010 results highlighted the following
points:• The levels of artificial radionuclides in the
coastal area were still very low, often withactivities close to the decision thresholdsof the best analytical techniques.
• Only cesium-137 was regularly detectedby direct gamma spectrometry in samples
with values less than 0.02 Bq/kg wet formussels and less than 0.1 Bq/kg wet forfish (Figures IV.63 and IV.64).

Toulon military port

Cs (Bq/kg ash)

137

100

Tritium activity (5.8 Bq/L) greater thanthat usually measured was occasionallydetected in Toulon harbor during themonth of A pril 2010. Additional
measurements were planned for 2011 to
confirm this result and, if appropriate, toidentify the source. No other artificial
radionuclide was measured between
January 2010 and June 2011.

10

1

Sediments
0,1

Toulon military port
Among the quarterly analyses ofsediment samples, cesium-137 wasoccasionally measured at between 5.12
± 0.52 Bq/kg dry and 8.59 ± 0.57 Bq/kg
dry. Traces of plutonium-239+240(0.059 ± 0.038 Bq/kg dry) were also
detected. These radionuclides weremainly the result of past atmosphericfallout. No other artificial radionuclide
was measured in sediments.

91 992 993 994 995 996 997 998 999 000 001 002 003 004 005 006 007 008 009 010
1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2
Significant activity

19

Figure IV.63 - Changes in cesium-137 activity in mussels along the Mediterranean coast from 1992 to2010 (Bq/kg ash).
137

100

Cs (Bq/kg ash)

10

Aquatic fauna
Mediterranean coast
IRSN monitors the French Mediterraneanmarine environment by taking bimonthly
samples of mussels (from eight stations)and fish (from four stations). The stations
are distributed to ensure full geographicalcoverage of the French Mediterranean coast.
Mussels were selected as a bioindicator due

98

1

0,1

9
0
5
8
6
4
9
7
4
2
7
0
5
3
8
1
6
199 199 199 199 199 199 200 200 200 200 200 200 200 200 200 200 201
Significant activity
Figure IV.64 - Changes in cesium-137 activity in fish along the Mediterranean coast from 1994 to2010 (Bq/kg ash).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.3

This stabilization reflected a balance
between contribution to the coastal
environment, bioaccumulation inorganisms and sedimentary processes(storage, partial remobilization). In fish,
this decrease was less pronounced andcesium-137 activity levels in fish are now
stabilizing at levels three to four times
higher than those measured in mussels.
This is due to the fact that fish are higher
up the food chain and that they actively
retain cesium in their muscles as achemical analog of potassium. As the
distribution of cesium-137 had been
ecologically stabilized, the developmentof activity levels over the next few years,
unless there is a significant newdischarge, should reflect the radioactive
decay of this element (half-life = 30
years).
Cobalt-60 from discharge from nuclear
facilities was occasionally detected atvery low levels (0.5 Bq/kg ash) in mussel
samples collected west of the mouth of
the Rhône, reflecting the impact of thecontribution from rivers on this stretch ofcoastline.
Due to the relative importance of tritiumand carbon-14 discharge from nuclear
facilities, these two radionuclides wereperiodically measured in mussels and fish
for all the stations. Levels of tritium inorganisms were very low and less than
1 Bq/kg dry, except for stations near themouth of the Rhône and at Toulon,reflecting a slight local impact of tritium
discharge from nuclear facilities in the
Rhône region. The level distribution ofcarbon-14 was very even, with a meanvalue of 235 Bq/kg of carbon.
In 2010, plutonium isotopes wereanalyzed by alpha spectrometry on
samples of mussels recorded since 1986
for two stations: Faraman, near themouth of the Rhône and Nice, outside
the influence of the contribution fromthe Rhône (Figure IV.65). These new
results indicated that the Nice station
was clearly affected by the fallout fromthe Chernobyl accident in May 1986 andby fallout from weapons tests until them i d - 1 9 9 0 s . T h e i s o t o p i c ra t i o(238Pu/239+240Pu) for this station varied
between 0.05 and 0.03, confirming thesource of this contribution. The Faraman
station also showed added concentrationfrom atmospheric fallout, contributions
from the Rhône and discharge from thefuel reprocessing facility at Marcoule, asconfirmed by the change in isotopic ratio
from 0.3 to 0.06 over the period inquestion. Since the early 2000s, these
two stations have shown similar, stable
activity values of plutonium-239+240 of
between 1 and 1.5 mBq/kg wet. Despite
the limited number of measurements,
this time series reflected the changes inthese elements in the coastal marine
environment of the Mediterranean.
239+240

Pu (mBq/kg ash)

500

400

300

200

100

0

198
4
198
5
198
6
198
7
198
8
198
9
199
0
199
1
199
2
199
3
199
4
199
5
199
6
199
7
199
8
199
9
200
0
200
1
200
2
200
3
200
4
200
5
200
6
200
7
200
8
200
9

Changing activity levels in mussels inrecent years showed that levels werestabilizing, following a sharp decline in
the 1990s.

Faraman

Nice

Figure IV.65 - Changes in plutonium isotope activity (239+240Pu) in mussel samples from Faraman(mouth of the Rhône) and Nice between 1986 and 2008 (mBq/kg ash).

Toulon military port
Apart from the observations made on
samples along the entire coastline, noartificial radionuclide activity above thedecision thresholds was measured insamples of seaweed, mollusks and fishfrom Toulon harbor.

IRSN – Report on the Radiological State of the Environment in France in 2010-201199

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

IV.4 REGIONAL
RADIOLOGICALSTUDIES
Current objectives andstudies
The purpose of regional radiologicalreports is to establish, over a wide area
(several departments), an up-to-datebaseline of the levels of radioactivity incertain environmental compartments,
especially agricultural and livestock
production typical of the area inquestion. This baseline must take into
account the radiological "background"
related to natural radioactivity and theresidual material of past atmosphericfallout (nuclear weapons tests and theChernobyl accident), and the influence ofpresent or past discharge from nuclear
facilities in this area. In the event of an
accidental release, this baseline would be
used as a basis for comparison and help
guide the deployment of more intensive
post-accident monitoring.
Developing regional radiological studies
first requires an examination of allavailable data, including that acquired by
IRSN from continuous monitoring or
previous radioecological studies. Thisknowledge is then completed or verified
through specific sampling and analyses.
These reports should therefore increase
the radiological knowledge of ourenvironment both spatially and throughthe diversification of samples, analyses
and radionuclides detected. In addition,
IRSN is using the most efficient methodsof collecting, processing and analyzing
samples to compile this reference state.
Members of the Local Information
Commissions (CLI), local governments
and authorities, are invited to participate
in these reports, in particular by applying
their knowledge of the area during thedevelopment of sampling strategies andwhen results are presented. They will
receive the reports published for eachstudy.
Depending on the complexity of the area,
it takes three to four years to complete
studies, from beginning to delivery. A
report should be updated about every
five to seven years.

100

After the first exploratory regional
radiological study conducted in the Loire
valley between 2008 and 2010 (see
Focus and IRSN reports), the strategy was
improved and, generally speaking, thecontent of reports currently in progressincreased: Rhône Valley: (2009-2012),
Southwest (2009-2012) and Northeast(2010-2013).

Sampling and analysis
strategy
The reports take into account the locationof nuclear facilities, distinguishing between
potentially affected areas (ZI) and distantareas that may be considered, undernormal operating conditions, to be outside
their influence (non-affected areas: ZNI).
In a terrestrial environment, the potentiallyaffected area (ZI) does not usually exceed
a few kilometers. However, it cansometimes be more extensive, such as in
Marcoule, where the influence of
atmospheric discharge of tritium can beseen beyond this distance. Non-affectedareas (ZNI) are intentionally defined as
being much further away than the distancetaken into account for the potentiallyaffected area, typically more than 15 to 20
km from each facility, in places that are
therefore not normally subject to regularmonitoring.
The sampling plan for a terrestrial
environment includes several categories:• p roduction that is predominantly
agricultural in terms of surface area,
quantities or economic value; in thiscategory, produce common to theSouthwest and Rhône Valley reports
consists, for example, of orchard fruits,wine, vegetables and regional livestock
products;• s ymbolically impor tant or evenemblematic production, such as olive oil,registered designation of origin (AOC)
walnuts, chestnuts and rice from the
Rhône valley, or garlic, honey, hazelnuts or
duck from the southwest;• s amples of the same type as thosecollected systematically during IRSN's
regular monitoring activities (leaf lettuces
or milk, etc.) that allow the area understudy to be compared with existing
records;• plants or animals characteristic of natural

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

ecosystems: mushrooms, game, wild
berries, etc., depending on sampling
possibilities;• s p e c i f i c i n d i c a t o rs o f c e r t a i nradionuclides: tree leaves for tritium,
mosses for atmospheric plutonium.
In an aquatic environment, the potentiallyaffected areas are those locateddownstream of nuclear facilities, with nonaffected areas being theoretically locatedupstream. However, the succession offacilities along major rivers (e.g. the Rhône)makes it more difficult to determine suchareas, as upstream of a facility corresponds
to downstream of the previous one. The
samples consist of water, radiologicalindicators such as sediments, aquaticplants or filter-feeding mollusks (corbiculaein the Rhône) and foodstuffs (fish, mussels).
In the atmospheric environment, artificial
radioactivity levels are relatively wellknown throughout the areas considered.
However, in the context of these studies,equipment that is more efficient than thatused for routine monitoring around nuclear
facilities (low-level OPERA-Air station, see
Chapter IV.1) can be deployed under theprevailing winds of the site of interest.
Various analyses were performed using thebest available technology on the mostappropriate samples to quantify the levelsof the main natural and artificial
radionuclides present in measurable
quantities in the environment: analyses offree and bound tritium, carbon-14, gamma
spectrometry, radiochemistry and alphaand beta spectrometry for plutonium
isotopes and strontium-90, ICP-MS for
uranium isotopes, etc.

Rhône Valley regional
study
The Rhône Valley radiological study beganin mid-2009 and was completed in 2012.
This report was the subject of two
methodological presentation reports
related to the terrestrial environment(IRSN-SESURE 2010-01) and the aquatic
environment (IRSN-SESURE 2011-34). It
covers the municipalities bordering the
Rhône, from upstream of the Creys-Malvillesite to the Camargue.

IV.4
Additional specific points of special interest(emblematic produce) although outlying,were also considered. This area is marked byseveral nuclear facilities: the four NPPs in
operation (Bugey, St. Alban, Cruas andTricastin), the Creys-Malville reactor (being
dismantled), the other facilities at the
Tricastin-Pierrelatte complex and those on
the Marcoule site.

A specific sampling and analysis plan wasdeveloped for the area around Marcoule, withthe main aim of examining tritium, which isthe dominant radionuclide in atmosphericdischarge from this center. Samples of poplar
leaves were collected from fourteen points,
at increasing distances from the site, firstalong a north-south, then an east-west anda south-east-north-west axis, to measure thetritium.
As the Rhône aquatic environment is covered
quite thoroughly as part of IRSN's regularmonitoring activities (water samplers,
observatory station at Arles on the Rhône)and studies are regularly conducted by IRSN
in other contexts, the few additional samples
taken were from generally non-typical areas.
Samples of water, suspended matter and fish
were therefore collected upstream anddownstream of each facility. In addition,
rarely sampled filter feeders were collected
downstream of the NPPs and Marcoule(Figure IV.67).

Poplarleaves 3H 14C

Lyon

Saint-Étienne

Le Bugey

Saint-Alban

Creys-Malville

Wine
Pears, apples, plums
Cow's milk
Meat
Leaf lettuce
Grapes, wine
Corn

Grapes, wine
Leaf lettuce
Tomatoes, peppers
Cow's milk
Grenoble
Ce Grenoble

RomansPoplarleaves 3H 14C

Valence
Poplarleaves 3H 14C

Poplarleaves 3H 14C

Cruas

Le Tricastin

Specificsampling

Marcoule

AvignonPoplarleaves 3H 14C
Nimes
Arles

Spe
sam cific
plingFigures IV.66 and IV.67 show the sampling
plans respectively selected for the terrestrial
and aquatic environments. In a terrestrial
environment, the sampling strategy ofaffected and unaffected production is definedby:• mapping tools (analysis of land use by ageographical information system);• statistical data published by the French
Regional Directorates for Food, Agriculture
and Forestry (Agreste statistical database);• local contacts established during sampling
campaigns, who make it possible to adjust
theoretical data (sometimes obsolete) tothe reality on the ground.

Pears, apples, plums
Meat
Cow's milk
Wine

Poplarleaves 3H 14C

Olive oil
Meat
Herbs (thyme)
Goat's cheese
Apricots, nectarines
Zucchini, tomatoes
Camargue rice

Cow's milk
Leaf lettuce
Meat

Wine
Goat's cheese
Honey
Walnuts
Apricots, peaches
Chestnuts
Zucchini, tomatoes
Wine
Goat's cheese
Meat
GarlicPeaches or nectarines
Zucchini or tomatoes
Eggs
Meat
Goat's milk
Leaf lettuce

Peaches or nectarines
Goat's milk
Meat
Thyme
Tomatoes or peppers
GarlicZucchini, tomatoes
Goat's cheese
Thyme
Meat
GarlicHoney
Goat's milk
Leaf lettuce
Thyme
Grapes
030 km

ZNI foodstuffs
ZI foodstuffs
Poplar leaves 3H 14C

Figure IV.66 - Location of sampling areas and distribution of samples taken in the Rhône Valley study(ZI: affected area, ZNI: non-affected area)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

101

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

A few specific points will be added to thesesamples to determine the impact of the main
tributaries that dilute and possibly also carryradionuclides (for example, the Isère, which
carries the discharge from the FBFC plant at
Romans-sur-Isère and the CEA's Grenoble
center). Finally, the study of the impact ofliquid discharge from hospital radiotherapy orradiodiagnostics departments located along
the river will be the subject of a subsequent
additional section.
A high-volume atmospheric aerosol samplingstation has been in operation under theprevailing winds of the Tricastin site since thebeginning of 2012. The filters will be analyzed
by gamma spectrometry (137Cs, 60Co, etc.),alpha spectometry (plutonium isotopes inparticular) and by ICP-MS for uranium
isotopes.

Génissiat
Le Fier
Creys-Malville
Bugey

L’Ain

Saône
Lyon

St Alban

CEA Grenoble

FBFC

Isère
Valence

La Drôme
Cruas

L’Ardèche
Tricastin

Marcoule

Cadarache

Durance

Le GardVallabrègues
Petit Rhône

Arles
SORA

Scheduled sampling
Mollusks
Fish
PlantsWater + SM
Sediments

Rhône
Tributaries
Water samplers
Annual upstream/downstream monitoring
Decennial upstream/downstream monitoring

Data acquired

Figure IV.67 - Location of samples in the aquatic environment.

102

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IV.4
D

Southwest regional study

CNPE de Chinon

The Southwest radiological study began at
the end of May 2009 and was completed in2012. It covered a vast area of four
administrative regions (Poitou-Charentes,
Limousin, Aquitaine, Midi-Pyrénées) andtwenty departments, bordered to the northby the Loire, to the east by the Massif Central,
to the south by the Pyrenees and to the west
by 700 km of Atlantic coastline.
The potential sources of radiological exposure
were the liquid and atmospheric discharge
from the three NPPs in operation (Le Blayais,
Golfech and Civaux), liquid discharge fromthe nuclear medicine departments of about
fifteen major cities (Pau, Bayonne, Tarbes,
Bordeaux, Toulouse, Agen, Poitiers, Limoges,etc.), uranium-bearing areas, areas affectedby former mining sites and other old
industrial sites (residue foundry, gas
production, etc.). The sampling and analysis
strategy used for the Southwest report, didnot, however, cover the former mining areas,
which will be the subject of specific studies.
Figure IV.68 shows the sampling plan in aterrestrial environment.
A high-volume atmospheric aerosol samplingstation, similar to those in the low-volume
OPER-Air network, was installed in 2011
under the prevailing winds of the Golfech
NPP in collaboration with the operator(Figure IV.69). The first samples were filteredin September 2011. They were measured by
low-background gamma spectrometry. In
addition, a specific campaign for measuringtritium in atmospheric water vapor was
carried out in 2012.

CNPE de Civaux
Le Clain

La Vienne
CNPE du Blayais

La Dordogne
Le Lot

La Garonne

CNPE de Golfech

Le Tarn

L'Adour

La Garonne

La NiveGavede PauNuclear power plants
Dairy product sampling
Meat sampling (game, beef, chicken, duck)
Fruit and vegetable sampling
Wine and juice sampling
Honey sampling
Oak leaf sampling
Main rivers
South-West "regional finding"Figure IV.68 - Sampling in the terrestrial compartment within the context of the Southwest regional
study.

Figure IV.69 - OPERA-Air (300 m3/h) sampler installed under the prevailing winds of the Golfech NPP.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

103

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIESIn relation to the aquatic environment, thesampling points on major rivers (Vienna,
Garonne, Adour) and their tributaries wereidentified during this report, taking into
account the NPPs, the IRSN's regularmonitoring installations (in particular, water
samplers on the Garonne and the Vienne), theindustrial facilities included in ANDRA's
national inventory of radioactive materials
and waste, major urban centers with nuclear
medicine departments and the proximity ofuranium-bearing areas (Figure IV.70).
Depending on the proximity of the facilities
and the diversity of the environments, thesampling focused on surface water, sediments(Figure IV.71) and aquatic plants (Figure
IV.72). The samples were systematicallyanalyzed by gamma spectrometry. Additional
analyses were carried out, depending on thefacilities located on the rivers: tritium,
carbon-14, uranium, thorium, etc.

CNPE de Chinon

CNPE de Civaux
Le Clain

La Vienne

CNPE de Blayais

La Dordogne
Le Lot

La Garonne

CNPE de Golfech

L'Adour

In the case of the specific study of discharge
from nuclear medicine centers, samples wereanalyzed by gamma spectrometry as soon as
possible to detect short-lived radionuclides
characteristic of this activity (iodine-131,
metastable technetium-99).

Le Tarn

La Garonne

La NiveGavede PauNuclear power plants
Nuclear medicine departments
Sediment sampling
Aquatic plant sampling
Water sampling
Oyster and mussel sampling
Main rivers
South-West "regional finding"

In total, 164 samples were collected
specifically for the southwest radiologicalreport (Table IV.22).

Figure IV.71 - Sediment sampling in the Adour estuary, downstream ofBayonne, within the context of the Southwest regional study.

© Leprieur/IRSN© Mechenet/IRSN

Figure IV.70 - Sampling in the aquatic compartment in the context of the Southwest regional report.

Figure IV.72 - Jussie sampling in the Adour within thecontext of the Southwest regional study.

Table IV.20 - Number of samples taken within the context of the Southwest study.

Aquatic compartment

104

Terrestrial compartment

Water

Plants and seaweed

Sediment

Fruits and vegetables

Animals

Tree leaves

Dairy products

Wines

10

26

30

46

27

13

6

6

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IV.4
Northeast regional study
The area covered by the Northeast
radiological study includes thirteen
departments that have four sites that impact
the activity concentrations of theirenvironments: the CEA's Valduc center, theChooz, Cattenom and Fessenheim NPPs andseventeen hospital facilities (Figure IV.73).
This assessment began in 2010 with theidentification of the radionuclides to be taken
into account, the collection of previously
acquired data and the identification of theresults to be supplemented or updated.
Essentially based on several thousand itemsof existing monitoring data or specificprevious or concomitant studies conductedby IRSN, this study was also supported by
170 additional samples and about 300
analyses to extend the general summary
report to be published. The sampling
campaigns and analyses were conducted atintervals during 2011 and 2012 and thisstudy was completed in 2013.

Chooz
BELGIUMLUXEMBOURG
08
Cattenom
GERMANY
57
55
54

67

Morvilliers
Soulaines
88
52
Fessenheim

68
90

70
Valduc21

GERMANY
25

39

Selected facilities
Nuclear power plants
Deterrence force center
Medical facility
Waste disposal site
Area covered by the Northeast study
Department
Figure IV.73 - Facilities involving radionuclides in the area covered by the Northeast study.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

105

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIES

IV.5 Radiologicalmonitoring in
THE overseas
TERRITORIESApart from French Polynesia, which is
specifically monitored by IRSN (see Focus on
monitoring radioactivity in French Polynesia)
due to the past history of nuclear tests
conducted on two French Pacific atolls(Mururoa and Fangataufa), the Frenchoverseas departments, regions andcommunities are outside the influence ofFrench nuclear facilities, but may,nevertheless, be exposed to the effects offoreign nuclear facilities.

to cause an increase in the ambient dose ratethat could be detected by the measuring
devices used, given the natural background of
gamma radiation of terrestrial, atmosphericand cosmic origin.
In 2010 and 2011, no abnormal measurement
relative to an accidental radiological event
was detected by the IRSN Teleray network
probes installed in Saint-Pierre-et Miquelon,
Guadeloupe (Figure IV.74), Martinique, French
Guiana, La Réunion, New Caledonia andFrench Polynesia.

As such, IRSN's monitoring redeployment
plan is intended, in the medium term, tocover only these areas, through the use oftelemetry devices and by collecting samplesof bio-indicators from areas not affected bya particular event. These areas will also be
subject to periodic radiological reports, in thesame way as all the regions of metropolitan
France. IRSN began specific studies in
Reunion and New Caledonia in 2012.
Between March and May 2011, these
territories were more intensively monitored
to track and assess the impact of thedamaged Fukushima plant. These monitoring
results are presented in Chapter III.

Atmosphericcompartment
To assess the impact of release from the
Fukushima accident on the ambient doserate, IRSN intensified its vigilance withrespect to real-time measurements from theTeleray network, particularly for areas
thought to be the first in the path ofcontaminated air masses (in particular SaintPierre-et-Miquelon) and for this purpose
installed passive dosimeters (RPL) at various
points across the area to obtain integrated
measurements of the external radiation dose
during the period of exposure tocontaminated air masses.
However, the predictions of concentrations
in air in France (metropolitan and overseas),
obtained from cesium-137 simulations
performed by Météo-France, the Frenchnational meteorological service, showed
levels that were too low (around 1 mBq/m3)

106

Figure IV.74 - New-generation Teleray probe installed in Saint-Claude, Guadeloupe.

Terrestrial compartment
Milk
Samples of cow's milk were collectedannually in Martinique, French Guiana andRéunion (Table IV.21). As in metropolitan
France, the radioactivity measured in 2010
and early 2011 in milk was mainly due tonatural potassium-40. The activity levels

observed fluctuated between 37 ± 8 Bq/L
and 52.9 ± 4.9 Bq/L, depending on thesource. Artificial cesium-137 was measured
in the sample taken in French Guiana (0.31 ±0.08 Bq/L). The presence of traces of thisradionuclide can be explained by past fallout
from previous atmospheric weapons tests.
No other artificial activity was measured inmilk samples from overseas regions.

Table IV.21 - Activity measured in cow's milk samples in 2010 and early 2011 in French overseas
departments and regions (Bq/L).

Radionuclide

Martinique

French Guiana

RéunionK

47.6 ± 3.9

52.9 ± 4.9

37 ± 8

I

< 0.2

< 1.2

<1

Cs

< 0.08< 0.08< 0.29Cs< 0.1

0.31 ± 0.08

< 0.34Srnm

nm< 0.018

40

131
134
137
90

nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IRSN • FOCUS

IV.5
Monitoring in French Polynesia

Figure IV.75 - Map of the French Polynesian archipelagoes and IRSN's sampling sites.

Since 1962, IRSN has been monitoring
radiological activity in French Polynesia(Figure IV.75), with the exception of the
Mururoa and Fangataufa atolls, whereradiological monitoring comes under theauthority of the French Ministry of Defense
via the nuclear test center monitoring
dep ar tment (DSCEN) of the Arms
Procurement Agency (DGA) responsible forthis task in collaboration with the French
Alternative Energies and Atomic Energy
Commission.
IRSN's monitoring involves taking regularsamples of various kinds from different
environments (air, water, soil, etc.) withwhich the population may be in contact, as
well as local foodstuffs.
In 2010, 54 samples were taken from thephysical environment (air, water andsediments) and 200 from the biologicalenvironment (deep-sea fish - Figure IV.76,
lagoon fish and other products, terrestrial
samples such as vegetables, fruit, meat,
milk, various drinks). The food samples
were representative of the diet of

Figure IV.76 - Mahi-mahi (or dolphin fish) caught off the coast of Tahiti.

Polynesians living in the five archipelagoesof the territory.
All these samples had two objectives:• t o discover the levels of artificial
radioactivity in all the different
environments and main foodstuffs;• to assess the dosimetric impact of thisenvironmental situation: for ingested
doses, all the samples representative of
the Polynesian diet were taken into
account. For external exposure andinhalation, the dose was estimated on thebasis of measurements of the physicalenvironment.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011107

Monitoring IN metropolitan FRANCE and THE overseas TERRITORIESIRSN • FOCUS

Focus continued

Main results

Activity (Bq/kg wet)
10

The radioactivity measurements (gamma
spectrometr y for cesium-137 andcobalt-60, measurement of alpha emittersfor Pu isotopes and beta emitters forstrontium-90) cover most of the range ofartificial radionuclides likely to be detected
in Polynesia. Almost all the samples taken
were measured in IRSN's Environmental
Study and Surveillance Laboratory (LESE) in
Vairao on the island of Tahiti.
The levels measured in 2010 did not differ
from those obtained in previous years; thefew variations observed were due tosignificant natural variability. Cesium-137
was the most frequently detected element.
The maximum values detected in 2010
were less than 0.5 Bq/kg wet for fish andten times lower for other lagoon products.
The maximum value detected in theterrestrial environment was 1.8 Bq/kg wet
for papaya in Rangiroa, 3.3 Bq/kg wet forpork and 8.8 Bq/kg wet for beef in Tahiti.

1

0.10

0.01
1980

1985
Cs in lagoon fish

137

1990

1995

The decline observed above can be
explained by the radioactive decay ofcobalt and cesium since the end of
atmospheric testing.

For more information
Assessment of radioactivity monitoring in
French Polynesia in 2010 and monitoringof the impact of the Fukushima accident
o n Fr e n c h Po l y n e s i a a n d N e w
Caledonia from March to May 2011 - DEI/SESURE report 2011-40
http://environnement.irsn.fr

108

2005

Figure IV.77 - Concentration of cesium-137 and cobalt-60 in lagoon products (all islands)(Bq/kg wet).

Where cobalt-60 and plutonium activity
levels were detected, they were extremely
low (Figure IV.77):• cobalt-60 was only detected three times
in 2010, in giant clam samples fromTubuai, Hao and Rangiroa;• plutonium isotopes, 238Pu and 239+240Pu,
w ere only detected, at ver y low
concentrations, in five giant clam samples(two from Tubuai, two from Hao and one
from Tahiti) out of the 26 samples
analyzed.

After a steady fall in radioactivity levels
since the French atmospheric tests came toan end in 1974, the radiological state
observed in 2010 has been stable in recent
years, and is now very low.

2000

Co in giant clams

60

IRSN – Report on the Radiological State of the Environment in France in 2010-20112010© IRSN

IV.5

Figure IV.78 - Sampling sediments from a river using a Berthois cone.
IRSN – Report on the Radiological State of the Environment in France in 2010-2011109

Monitoring of Nuclear Fuel Cycle Facilities

110

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V
Monitoringof Nuclear
Fuel Cycle
Facilities
V.1 Environmental monitoring near
nuclear sites
V.2 Environmental monitoring aroundformer mining sites
V.3 Environmental monitoring of industries in the front
end of the nuclear fuel cycle
V.4 Environmental monitoring of nuclear power plants
V.5 Monitoring of industries in the back end of
the nuclear fuel cycle
V.6 Monitoring of waste disposal facilities

Monitoring of Nuclear Fuel Cycle Facilities

V.1 Environmental
monitoringnear nuclear
sites
Until 2001, when the last operating uranium
mine closed, France was the only country tohave all industries of the fuel cycle on its territory, covering the following stages:• extraction of uranium from mines;• concentration and conversion of uranium
compounds;• isotopic enrichment in uranium-235;• fabrication and assembly of fuel1;• use of fuel in nuclear power plant (NPP);• p rocessing spent fuel unloaded fromreactors;• processing and disposal of waste.
The French nuclear fuel cycle is considered“closed” or “semi-open” because part of spent
fuel is processed and reused. The environments of all the fuel cycle sites (Figure V.1)
are systematically monitored by the plant
operators from the commissioning of plants
and throughout their service lives, according
to a program monitored by ASN, the French
Nuclear Safety Authority.
The monitoring programs implemented
around the fuel cycle plants take account of
the type of plant being monitored and of its
discharge. These programs also vary according
to the geographical environment of themonitored plant and meet the objectives
specified in Chapter I.
It should be noted that:1 - The results from the French national
environmental radioactivity measurement network (RNM) database used inthis chapter cover the period fromJanuary 1, 2010 to June 30, 2011.
2 - The results of the regular monitoring of
the plants impacted by the fallout inFrance from the Fukushima accident arepresented separately in order to avoid
interfering with the results obtained
outside this period.
3 - The results of the monitoring of themarine and coastal compartment(sea water, sediments, aquatic faunaand flora) in the vicinity of nuclear
facilities are presented in Chapter IV(Marine and coastal environment).

Gravelines

PaluelCSM
La Hague
Flamanville

Cattenom

Meuse
Seine

Moselle
CSFMA
Rhin
CSFTA
Fessenheim

Nogent-sur-seine
Brennilis

Loire
ChinonSaint-Laurent-des-Eaux
Dampierre-en-Burly
Belleville-sur-Loire
VienneCivauxLoire
Le Bugey
Creys MalvilleSaint-Alban
Rhône

Le Blayais
Dordogne
GolfechPierrelatte
Tricastin
Marcoule

Romans-sur-Isère
Cruas-Meysse
TricastinPhénixGaronneMalvési

Uranium conversion (Comurhex Malvési and Pierrelatte)
Uranium enrichment (Eurodif Tricastin)
Fuel assembly fabrication (FBFC Romans-sur-Isère)
Nuclear power plants (EDF, 22 sites of which 19 in operation)
Processing of spent fuel unloaded from reactors and recycling (Areva La Hague)and R&D in these fields (CEA Marcoule)Surface disposal of radioactive waste(ANDRA, CSM, CSFMA and CSFTA waste disposal facilities)F igure V.1 - Main fuel cycle plants in France(excluding former mining operations, shown on the map in Section V.2)

4 - I n order to be able to use all the
results transmitted to the RNM database and produce understandable summary information while minimizing thenumber of units of measurement, IRSN
has in some cases applied conversion
factors to the raw results (Bq/kg wet<-> Bq/kg dry, for example).

1 – The fuel may be a mixed oxide fuel (MOX fuel),
i.e. consisting of a mixture of uranium
and plutonium oxides produced by reprocessing.

112

Chooz

Penly

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.2
V.2 Environmental
monitoringaround former
mining sites
In France, uranium was mined on an industrial scale for nearly 50 years. Many former
mining sites (Figure V.2) are now under the
responsibility of Areva. IRSN has undertaken
an exhaustive inventory of all the former uranium ore prospecting, mining and processing
sites as part of a program called MIMAUSA(memory and impact of the uranium mines:summary and archives) at the request of the
Ministry of Ecology. All available data isaccessible through a map interface on the IRSN
website (http://mimausa.irsn.fr).
Uranium ore prospecting, mining and processing activities and the disposal of processing tailings involved some 230 sites in France,
located in 25 departments. The sizes of thesesites and the quantities of ore mined vary
greatly, ranging from simple survey sites tomajor plants that produced several thousand
metric tons of uranium. Mining and processing of uranium ore generated two types ofmaterial or waste: waste rock and processing
tailings.
• Waste rock, rock excavated to access theore, differs from the other rock in the areas
concerned only by its location close to orebearing areas. It is generally richer in uranium than the neighboring rocks, withuranium contents ranging from a few tens toa few hundred g/t, with a total activity froma few Bq to a few tens of Bq/g. The waste
rock was stored in dumps at the mines, usedin the construction of processing tailings disposal facilities, or used in the rehabilitation of
the sites. Some has also been reused in public
works.
• Processing tailings are industrial waste
obtained after processing the uranium ore.
They differ from the initial rock by physical (crushing) and mineralogical alterations
caused by the chemical treatments. Their
total activity, all radionuclides combined,
is approximately a hundred to several hundred Bq/g. Consequently they are categorized as low- and very-low-level long-lived
radioactive waste. More than 50 million
metric tons of tailings are currently stored
in 17 disposal facilities on 16 sites. Afterthey were closed down, all the sites were

Bretagne

AlsaceGuérande

Château-Chinon
VendéeBenaize

AllierCreuseGartempe

LacourCrouzille
Corrèze

Saint-Symphorien
Saône-et-Loire
Forez
AmbertMaurienne

CantalAquitaine
AveyronLozèreLodèvePaca

Mining areas subject to statutory radiological monitoring of the environment
Other mining areas
Figure V.2 - Locations of French mining areas (Mimausa program)rehabilitated to make them safe, reduce
their radiological impact and re-integratethem into the surrounding landscape.
Underground mine works were partially
backfilled and then flooded. Tunnel
entrances were blocked up and shafts weresealed. Open pit mines were flooded, creating artificial lakes, or backfilled with waste
rock, or used as disposal sites for processing
tailings.

uranium ore processing talings are comparedwith those of various types of rock or ore in
Table V.1.

All the radionuclides initially present in theore are found in the tailings except the uranium, most of which has been extracted andconcentrated in the form of “yellow cake”.
They include in particular all the decay products of uranium-238, such as 230Th (half-life:of 7,000 years) and 226Ra (half-life of
1,600 years). The specific activity levels of the able V.1 - Radioactivity levels observed in several major rock types, oresTand mining tailings (Bq/g)

Uranium ores
Mine tailings
Waste rocks
Granitic rocks
Basalts and certain sedimentary rocks

Radium activity
10 - 70
10 - 700.05 - 5
0.04 - 0.3
0.0003 - 0.03

Total activity
180 - 900
100 - 700
1 - 100
0.7 - 60.005 - 0.5

IRSN – Report on the Radiological State of the Environment in France in 2010-2011113

Monitoring of Nuclear Fuel Cycle Facilities

The management of uranium ore processing tailings is subject to the regulations on environmentally regulated
facilities (ICPE). These tailings are apotential source of environmental contamination and of exposure to radioactivity as they may lead to radon release,
and, above all, because of their leachingby rainwater or runoff water. At somemining sites, the characteristics of thecollected water means that it requires
treatment before it can be discharged
into the environment.
Areva is still operating a number of water
treatment plants. Despite treatment, thepermitted water discharge from certain
sites may result in an increase in the radioactivity in downstream watercourses,
and in the deposition of sediments that
may contain high levels of uranium on
the beds or banks of bodies of water. In
order to be able to assess the radiologicalimpact of the disposal sites for these tailings on populations and verify the effectiveness of the measures implemented by
Areva, checks on the outlet water before
discharge and monitoring of the various
compartments of the environment(including the air) are required by prefectorial order for each disposal site.
In addition to the monitoring by Areva,
which meets the regulatory requirements
and is often reinforced by the company,
checks are made by the Regional Directorates for the Environment, Town andCountry planning and Housing (DREAL),
including unannounced inspections withsampling for analysis. These periodic
measurement campaigns are also conducted by several bodies, including IRSN.
These measurements may be made following questions from the public, elected
representatives, local or national associations, or in response to requests from theauthorities. In addition to these periodic
measurements, IRSN carries out regularmonitoring of the environment aroundsome of the leading former mining sites
in terms of tonnage of uranium mined orof ore tailings in disposal facilities. This
monitoring focuses essentially on theaquatic environment and external
exposure.
This chapter covers only the results ofwater monitoring (surface water, groundwater). Air measurements are covered in

114

Chapter IV (Atmospheric compartment).
Over the period analyzed in this report,
nearly 1,300 measurements were madeon water samples collected by IRSN andAreva (Figure V.3) around former Frenchmining sites subject to regulatory environmental monitoring.
999

283

Areva NC
IRSN
F igure V.3 - Breakdown of the number of water
samples by providers of mining site
monitoring data

Bertholène mining site
(Aveyron mining area)
Located in southern France, Bertholène
was the site underground mines and an
open pit mine from 1977 to 1994. The ore
was processed by static leaching, generating the tailings now stored on the site.
The facilities have been dismantled andthe site, which has a water treatment
plant, is being rehabilitated.
The radium-226 measurement results at
the water monitoring points on this mining site in 2010 varied between the decision threshold (< 0.01 Bq /L) and amaximum value of 0.07 Bq/L for the analyzed ground water. These activity levels
are equivalent to the natural background.
The significant values of uranium-238,
between 141 and 247 µg/L, showed an
influence of the mining site on the receiving environment, which has natural levelsof approximately a few µg/L.

Rophin mining site
(Ambert mining area)
The Rophin mining site, in Lachaux (central France), was worked undergroundfrom 1949 and 1955 and its uranium ore

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

processing plant operated from 1950 to1955. The solid tailings from processing
are stored on the site. The facilities havebeen dismantled and the site has beenrehabilitated.
Of the five surface water monitoring
points, only the activity levels ofradium-226 (1.94 Bq/L) and uranium-238(251 µg /L) at one sampling point at
Lachaux showed that they were affectedby the mining site. Activity levels ofradium-226 (between 0.02 Bq/L and 0.12
Bq/L) and uranium-238 (between < 5 and6 µg/L) at the other monitoring points
were equivalent to the natural background of this site.

Saint-Pierre mining site
(Cantal mining area)
In operation from 1958 to 1981, theSaint-Pierre mining site included an open
pit mine and a uranium processing andconcentration plant. The tailings are
stored on the site. The installations havebeen dismantled and the site has beenrehabilitated.
The radium-226 activity levels measured
in surface water samples from the twomonitoring points varied between thedecision threshold (< 0.01 Bq/L) and amaximum value of 0.22 Bq/L. These
activities are moderate, and most ofthem are linked with the naturally highbackground in this uranium-bearing
area. Nevertheless, the maximum values
are evidence of added concentration levels related to past activity of the site.
The measured uranium concentrations(weight /volume), between 4 and52 µg/L at one monitoring point andbetween 75 and 489 µg/L at the other,confirm this observation.

Bernardan mining site
(Benaize mining area)
Société des mines de Jouac owned adozen sites worked in the Benaize mining
area at Jouac, Cromac, Saint-LégerMagnazeix and Mailhac-sur-Benaize incentral France. The uranium ore wasworked in open pit mines (quarries) or
underground mines, depending on thecharacteristics of the deposits.

© Noak/Le bar Floréal/IRSN

V.2

Figure V.4 - Pond for drain water from the uranium mine tailings disposal facility at the Bessines-sur-Gartempe site

The Bernardan mining site was the largest of these sites. It was operated as anopen pit mine (1978-1987) and anunderground mine (1983-2001). The
site accommodated experimental static
heap leaching facilities (1978-1987)
and an ore processing plant (19792001). Mining of deposits ended on May
30, 2001 and the processing plant was
shut down in December 2001 and thendismantled. The installations were dismantled and the site, which has a water
treatment plant, has been rehabilitated.
In 2010, the radium-226 measurement
results at the six surface water monitoring points of this mining site varied
between the decision threshold (< 0.01
Bq/L) and 0.08 Bq/L. These activity levels are equivalent to the natural background. The uranium concentrations(weight /volume), near 30 µg/L, werehigher than those generally observed insurface water in similar geological contexts not influenced by mining.

Crouzille mining area
(central France)
From 1948 to 1995, the Crouzille mining
division worked a series of granitic uranium-bearing deposits which produced
23,324 metric tons of uranium. The ore
was extracted by open pit mining fordeposits close to the surface and by
underground mining for deep deposits.
The area comprises 24 mining sites
located within the boundaries of four concessions. Between 1958 and 1993, all themined ore was processed at the Bessinessur-Gartempe processing plant (FigureV.4). The site, now rehabilitated, accommodates the center for research and fol-

low-up of former mining activities(CESAAM) and a depleted uranium storage facility.
The surface of the area occupied by themining sites of the Crouzille mining division can be divided into drainage basinson the basis of its hydrological characteristics. The major drainage basins in termsof the number of sites are those of the
Gartempe (9 sites), the Vincou (2 sites),
the Ritord (5 sites) and the Couze (4 sites
not discussed below). The Couze, theRitord and the Vincou are all left-banktributaries of the Gartempe. The largest
mining sites in terms of the geographic
extent of the works and their production
are at Bessines (SIB) on the Gartempe,
Fanay-Augères on the Ritord andMargnac-Pény on the Vincou.

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115

Monitoring of Nuclear Fuel Cycle Facilities

Vincou drainage basin
The Vincou flows from the monts
d'Ambazac hills through the Crouzille division. This stream is notable with regard

to the study and the understanding ofradioactivity in the vicinity of the mining
sites, as it flows through several mining
sectors at Margnac (Figure V.5).

LegendWater sampling points
Main former mining sites
Continental waters
Meadows
Forests
FarmlandIndustrial areas
Built-up areas
A20 highway

Figure V.5 - Main rivers and mining areas of the Vincou and Ritord drainage basins© IRSN

Downstream of Crouzille Pond (Figure V.6), IRSN
has been collecting water samples from the Vincou since 1966. The samples have been used forhistorical monitoring of radioactivity during thedifferent phases of operation of the mines.

Figure V.6 - Crouzille Pond

116

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

The operating and subsequent monitoring
phases of the site can be observed in the grossalpha activity and the radium-226 activity of
the water samples from the Vincou (FigureV.7). During the operating period of the mining
sites (1948-1995), the average annual grossalpha activity varied between 1 and 11 Bq/L
according to the industrial operations on thesites and to the improvement in effluent
treatment techniques. The maximum value
measured was 33 Bq/L in June 1978. Since
the shutdown of the mine in 1995, theaverage annual gross alpha activity has notV.2
exceeded 1.13 Bq/L and has decreased steadily to reach 0.45 Bq/L in 2010. Radium-226
activity was close to 0.1 Bq/L.

12

226

Gross alpha (Bq/L)

Ra (Bq/L)

0.6

10These observations agree with those obtainedin 2010 by Areva at the water monitoring
points on the Vincou downstream of Crouzille
Pond (radium-226 activity between 0.02 and0.14 Bq/L). The maximum uranium-238 level inthe water of the Vincou downstream of all themining sites (point VIN B – see Figure V.5) was
24 µg/L. These values are slightly higher thanthose generally observed in surface water in similar geological contexts not influenced by mining. They are similar to the results obtained atpoint CTM B1 (Figure V.5) in a stream receiving
water from the Châtenet Maussant site whichflows into the Vincou.

0.7

0.5

8

0.4
6

0.3

4

0.2

2

0.1

0
1970

0

Gross alpha

1980

1990

2000

2010

Radium-226

F igure V.7 - Gross alpha and radium-226 activity levels in water downstream of the Vincou basin
mining sites – IRSN data (Bq/L)

Ritord drainage basin
Le Gouillet Pond feeds a small stream, theRitord (Figures V.5 and V.8), which receives
discharge from five mining outlets over a
distance of five kilometers. The stream
receives discharge from the main outlet of
the Fanay-Augères site and then secondary
discharge from other mining sites (Vénachat,etc.). It flows into Saint-Pardoux Lake, an
artificial lake created in 1976 on the river
Couze.

© IRSN

Overall, no difference is observed between
measurements made on the Ritord upstreamof all the sites (outlet from Le Gouillet Pond)
and the point downstream of all the mining
sites (where the Ritord flows into SaintPardoux Lake). Activities of approximately
0.1 Bq/L of radium-226 and 5 µg/L of uranium-238 were measured in 2010. Only thegross alpha measurements showed activity
levels, close to 0.4 Bq/L, higher than theguideline values recommended by the publichealth code for water intended for humanconsumption (0.1 Bq/L).
Figure V.8 - The Ritord at Razès, between Le Gouillet Pond and Saint-Pardoux Lake

Lower down the drainage basin, the mining
signature was observed in the water flowing
into the natural environment immediately
downstream of the Vénachat mining site(0.2 Bq/L of radium-226 and between 15 and32 µg/L of uranium-238 at points VENB and
VEN3), with a maximum gross alpha activityof 1.05 Bq/L measured at point VENB in
2010. However, additional concentrations in
the water of the stream could no longer beobserved where the Ritord flows into SaintPardoux Lake.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011117

Monitoring of Nuclear Fuel Cycle Facilities

Gartempe drainage basin
With a length of 206 km and a drainage basincovering an area of 3,922 km2, the Gartempeis the main tributary of the river Creuse. Its
source is near the small village of Lépinas in
the Creuse department, and it receives waterfrom various mining sites (including Puy
Teigneux, Puy de l’Age and Bellezane) and fromthe Bessines industrial site (Figure V.9). Thesesites are subject to monitoring of the radiological quality of surface water and ground water
carried out by Areva.

LegendWater sampling points
Bessines industrial site
Main former mining sites
Continental waters
Meadows
Forests
FarmlandIndustrial areas
Built-up areas
A20 highway

Figure V.9 - Main rivers and mining areas of the Gartempe drainage basin and Areva sampling point locations

The activity levels measured at the dozen
ground water monitoring points showed no
added uranium concentrations (between
the decision threshold at 0.5 µg/L and 6µg/L). A natural level of radium-226 wasobserved in all samples, ranging from 0.1 to
0.3 Bq/L. The gross alpha activity levels (0.16
and 0.37 Bq/L) and gross beta activity levels (1.6 and 1.9 Bq/L) at points PTS 42 andPTS 43 were slightly higher than the reference values recommended by the publichealth code for water intended for humanconsumption (gross alpha 0.1 Bq/L and grossbeta 1 Bq/L).

118

The water discharged from the uranium ore
tailings disposal sites (Le Brugeaud and Lavaugrasse on the Bessines industrial site,
Bellezane, Montmassacrot), undergoes
radium insolubilization treatment, and had
low concentrations of radium-226 (approximately 0.1 Bq/L). The uranium-238 content of the surface water samples
collected from the receiving stream immediately downstream of the Bellezane site (point
BZN 2) was between 187 and 375 µg/L, indicating added concentrations in discharge inthis stream with its low flow rate and consequent low dilution factor. The radium-226

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

and uranium activity levels measured in thewater of the Gartempe upstream (point VIL)
and downstream (point SIB B) of the Bessines
industrial site were equivalent to the natural
background. The impact of this site and themining sites of this drainage basin on thewater of the Gartempe consequently cannot be quantified because of the dilution of
the discharge (the annual average flow rateof the Gartempe is about 30,000 m3/h
upstream of the mining sites).

IRSN • FOCUS

V.2
The joint expert group (GEP) on the Limousin uranium mines
The joint expert group (GEP) on the
Limousin uranium mines submitted its
final report (Figure V.10) to the Ministerof Sustainable Development and to the
Chairman of ASN on September 15,
2010. The report provides the first interdisciplinary assessment throwing lighton a complex matter: the legacy of uranium mining in France. This legacy
involves 230 sites in 12 regions and 25
departments. It is associated with anumber of issues, including the ore processing tailings disposal facilities andtheir future, the risks related to the reuseof waste rock, the accumulation ofradionuclides in the sediments of watercourses downstream of the sites, andthe possibility of radon transfer from thesites to inhabited areas. Members of the
public are often in direct contact withthese sites, raising questions regularly,
and the sites are still sources of potentially significant exposure for the public.
Among the various actions undertakenby the public authorities to deal withthese issues and answer these questions, the setting-up of the GEP by the
Ministers of Sustainable Development,
Industry and Health in 2006 was a completely original initiative. The many
competencies brought together in thegroup meant that it could explore thedifferent technical facets of the topic. The
group also and above all was notable ininvolving members from different backgrounds and with different outlooks inlong-term work. Experts from publicbodies (including IRSN and InVS), theacademic world, Areva, regulatory
authorities and foreign bodies, but also
from local and national associations,were brought together to take a critical look at the monitoring of the rehabilitated mining sites and clarify forthe authorities and the operator the
management options to be implemented for the long term. As a public
expert, IRSN played a critical role insetting up and completing this novel
approach, for example by running thescientific secretariat of the GEP andco-chairing its four working groups.
In its work, the GEP conducted a methodological analysis based on the in-F igure V.10 - Final report of the joint expert
group (GEP) on the Limousin uranium mines

depth assessment of the situation of anumber of Limousin sites. This analysis
led the GEP to emphasize a movement
towards openness and progress ,increasingly taking account of the concerns raised by the associations, but also
to stress the need to pursue the work
already undertaken in greater depth andmore systematically, in order to cover all
the sites and situations and ensure thelong-term continuity of the approach initiated by public authorities. The aim isboth to make progress in the managementof the current impacts and to anticipate
future impacts, by taking possible changes
in the sites into account more systematically. To this end it has put forward a number of recommendations, grouped into 15
major recommendations and organizedaround six priorities:• institutional viewpoint and the regulatory framework for post-uranium
mining;• knowledge of the sites and the needfor studies and research to plan their
future;• assessment of the radiological andchemical impacts on population andon the environment;• measures for upgrading monitoring;• r obustness of rehabilitations overthe long term;• i nformation and participation of
local bodies and communities.
Among its various recommendations,
the GEP has emphasized the importanceof informing the public and encouraging
its participation in the implementation ofrehabilitation work on former uranium
mining sites. It has therefore recommended that the collection and release of
information on the location and otherdetails of these sites should be continued,
along with site monitoring activities. In
particular, it called for extension of thework undertaken through the Mimausa
program to summarize and archive thememories and the impact of the uranium
mines.
With regard to the current regulatory
monitoring of the mining sites, it considered that the systems deployed for monitoring discharge sources, transfers to theenvironment and potential impacts did
not always appear appropriate in view of
the needs and the prioritization of theissues. For example, the GEP consideredthat it was necessary to reinforce the

Focus (continued)
IRSN – Report on the Radiological State of the Environment in France in 2010-2011

119Monitoring of Nuclear Fuel Cycle Facilities

IRSN • FOCUS

Focus (continued)

measurements made downstream of the main
waste rock dumps, in the potential accumulation areas for substances released by thesites (measurements on the sediments, forexample) or in farm wells located within
their area of influence. It also called for continuation of the work on obtaining knowledgeof water circulation on the scale of a site andon assessment of the ecotoxicity of the substances contained in mine discharge.
The group also noted that the monitoring currently in place was mainly focused on exposure

Bois Noirs
Limouzat mining site
(Forez mining area)
Located at Saint-Priest-la-Prugne in southcentral France, the Forez mining division sitecovers an area of 88 hectares, of which 18 hectares are occupied by a water-filled storagebasin and 3 hectares are the site of former
processing plants. It was worked as an open
pit mine and an underground mine between
1955 and 1980. It included an ore processing
and separation plant which was in operationfrom 1960 to 1980. Ore processing tailings
are stored under water in the basin, behind ahomogeneous earth dam, located on the river
Besbre, the course of which was diverted by acanal. Part of the tailings were reused tobackfill the underground mine workings. The
facilities were dismantled in 1981 and demolished in 2006. The site, which has a water
treatment plant, has been rehabilitated.
The radium-226 measurement results at theten surface water monitoring points of thismining site in 2010 varied between thedecision threshold (< 0.01 Bq/L) and
0.16 Bq/L. These activities are equivalent orclose to the natural background. The uranium
contents (between < 0.5 µg/L and 8 µg/L)
were in the range of values observed in waterin contact with uranium-bearing rocks,
except for water collected by drain no. 40,
located upstream of the Besbre discharge, on
the right bank. Samples from this drain had
uranium contents greater than background(between 107 and 165 µg/L), indicating
additional concentrations related to thesite's mining activities.

120

indicators and, in certain cases, would benefit
from being supplemented by monitoring
focused on these effects (monitoring of the ecosystems).
The GEP stressed the importance of ensuring
the quality and the credibility of monitoringby further reinforcing joint acquisition,
checking and accessibility of data. For this itemphasized the importance of the sitechecks conducted by authorities, including
through unannounced inspections, andinvited IRSN to take account of the impacts

Bosc mining site
(Lodève mining area)
In 1975, the first ore was mined from theunderground mine of the main site of
Mas Lavayre in southern France (LeBosc). The open pit mines at Mas d’Alarybegan operation in 1978, and continued
until 1984. Between 1989 and 1992,
other small mines were also in operation(Rabéjac, La Plane, Puech Bouissou). From1994 to 1997, only the Mas Lavayre
underground mine was still being operated. The plant was dismantled in 1999
and rehabilitation works were completed in 2001.
The main site is now home to a teamtasked with monitoring the environment
and treating water from the mine(completely flooded) and therehabilitated quarries containing

associated with the former uranium mining
sites when rolling out its new monitoring
strategy. With the aim of giving visibility to themonitoring of the sites and promoting theaccessibility of results, the GEP suggested
that marking of field measurement points andtheir identification in documents be
improved, and also that access to data,
including via Internet, be facilitated, emphasizing in this context the considerable progress represented by the creation of thenational environmental radioactivity measurement network (RNM).

processed ore tailings. Areva monitors
the surface water of the drainage system
around the mining site. Water samples
are collected from the Riviéral stream
draining the whole of the industrial
area and the cap of the disposal facility
for the plant dismantling waste, from
the Mas d’Alary stream draining the wholeof the mining area and the cap of theprocessing tailings disposal facility, andfrom the river Lergue upstream anddownstream of the discharge point.
The results of the uranium-238 measurements for the two streams draining
water from the mining area showed
added concentrations due to mining
activity (between 530 µg /L and
1,930 µg /L). In the Lergue, the uranium content upstream and downstream of discharge was equivalent to
the natural background (between < 0.5
and 10 µg /L). The activity levels of able V.2 - Minimum and maximum activity levels measured in the surface water and groundTwater samples collected in 2010 on the Mas Lavayre site and in its close environment(in Bq/L for 226Ra and µg/L for 238U)

Water typeRiver water
Stream water

Ground water

Sampling point
Lergue (upstream)
Lergue (downstream)Mas d’Alary stream
Riviéral stream
Piezo Hydro 34
Piezo P37
Piezo PZ 1
Piezo PZ 2
Piezo PZ 3
Piezo PZ 4
Piezo PZ 6
Piezo PZ 7
Piezo PZ 8
Piezo PZ FS

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Ra (Bq/L)

226< 0.01 - 0.08
0.02 - 0.06
0.03 - 0.09
0.05 - 0.23
0.89 - 1.17
0.26 - 0.30
0.01 - 0.06
0.03 - 0.04
0.03 - 0.07
0.04 - 0.05
0.04 - 0.08
0.01
0.61 - 0.62
0.35 - 0.62

U (µg/L)238< 0.5 - 1
3 -10
833 - 1,930
530 - 760
3 -14
3,090 - 3,240
162 - 188
19
6 - 30371 - 368
1,250 - 2,030
11,100111 - 135
73,000 - 164,000

V.3
radium-226 in the surface water varied between < 0.01 and 0.23 Bq/L.
These concentrations are in the range ofvalues observed for water in contact withuranium-bearing rocks. Ground water
quality is monitored by Areva using ten
piezometers located at various points
over the whole site. The radium-226 anduranium-238 measurements on thewater samples show a substantial effecton the site ground water. The highest
radium-226 activities were observed atpoints Hydro 34 and PZ 8 locatedbetween the mining area and the area
west of the Lergue (between 0.61 and1.17 Bq/L). The highest uranium-238
contents were observed at point PZ FS(between 73,000 and 164,000 µg/L),
located near the dismantling materials t o r a g e f a c i l i t y. P o i n t s PZ7(11,100 µg/L), P37 (3240 µg/L) and PZ
6 (2030 µg/L) also showed high uranium-238 contents due to the past mining activities of the site (Table V.2).

Gueugnon site (Saône-etLoire mining area)
In 1954, a uranium ore processing plant
was built at Gueugnon in the Saône-et-Loire
department in east-central France. Operating from 1955 to 1980, the plant produced nearly 10,000 metric tons ofuranium before it was dismantled in 19801981. A disposal facility for waste and tailings
generated by the operation of the plant wasalso opened in 1955. Converted from disused
sand pits, it now contains 225,000 metric tonsof ore processing tailings and plant dismantling waste, and is monitored by Areva.
Since 1981, works and rehabilitation havebeen carried out on the areas of the former
plant and the disposal facility. As part of thisprogram, in 2010 Areva carried out rehabilitation work at the former plant and aroundthe disposal facility, including the laying ofspecial surfacing on the south car park of theJean-Laville stadium. Following these works,
in 2010 IRSN was commissioned by the
Directorate General for Risk Prevention (DGPR)
to determine whether the dose rates in the
rehabilitated areas were at a level equivalent
to that of the surrounding natural environment(further information at www.irsn.fr).
Surface water and ground water samples
were monitored at six sampling points. Only

one piezometer showed ra d i u m - 2 2 6(0.4 Bq/L) and uranium (836 µg/L) levels
substantially higher than the surrounding
background. The surface water showed
activity levels of radium-226 (between
0.02 and 0.08 Bq/L) and uranium (between< 0.5 and 9 µg/L) equivalent to the natural
background.

Bauzot mining site
(Saône-et-Loiremining area)
The Bauzot site, located at Issy-l’Évêque,also in the Saône-et-Loire department,
consisted of an underground uraniummine, an open pit mine and a low-levelindustrial waste disposal facility. It was inoperation from 1950 to 1985. The pit of
the open pit mine was backfilled, and thedisposal facility was covered with a layerof impermeable material and a layer of
topsoil. The site was then rehabilitated
and fenced off.
Surface water (river, lake, waste water) andground water are sampled by Areva tomonitor the disposal facility. The
radium-226 and uranium-238 measurements made in 2010 on the samples generally showed added concentration levels
related to past activities of the site.
The highest radium-226 activity levels
were close to or slightly greater than 1
Bq/L, and the highest uranium content was
greater than 2,000 µg/L at the “fosse” sampling point. The other points showed uranium contents close to 100 µg/L, greaterthan the surrounding background.

Vendée mining area
The Vendée mining area in western France
was in operation from 1954 to 1990. Until
1991, an ore processing plant was also
located on the Écarpière site. Rehabilitation
work was carried out on the site from 1989
to 1996. The Écarpière site is now the baseof an Areva team tasked with environmental monitoring of 25 sites operated by
the Vendée mining division and 18 former
mining sites in Brittany.
IRSN monitoring of surface water samples
from the vicinity of the Écarpière site has notrevealed any anomalies with regard to the uranium and radium-226 concentrations.

V.3 Environmental
monitoringof industries in
the front end of
the nuclear
fuel cycle
The processing and concentration plants
located close to the mines mainly produced uranates (containing approximately
70% uranium) and in some cases oxides(containing up to 80% uranium). Today,U O 2 l o w - e n ri c h e d t o 3 - 5 % uranium-235 is the end material of pressurized water reactor (PWR) fuel. In thecurrent plants, enrichment is carried out
on an ultrapure chemical compound, uranium hexafluoride (UF6), obtained by conversion of mining concentrates.
In France, two Comurhex (Areva group)
plants work in series to produce UF4 andUF6. At Malvesi, in southwest France, theore concentrates are converted to UF4. At
Pierrelatte, in the Rhone valley, the second Comurhex plant converts the UF4 to
UF6.
The uranium is then transferred to the
George Besse enrichment plant operated
by Eurodif (also at Pierrelatte) in theform of solid UF6. The three isotopes ofuranium present in the natural state (uranium-234, -235 and -238) are separated
selectively by passing UF6 gas throughporous membranes (gaseous diffusion
barrier). The lighter isotopes pass throughthe barrier more easily than the heavier
ones, so the process produces selective
and progressive enrichment. Uranium
enrichment technology is changing fromgaseous diffusion to centrifugation,offering higher performance, and theGeorges Besse plant is to be replaced bya new facility. The Société d'Enrichissement du Tricastin (SET) is the owner ofthis project and the operator of the
Georges Besse II plant, where production will increase gradually until 2016.
After enrichment, the UF6 is delivered to
the Franco-Belgian Fuel Fabrication (FBFC)
plant at Romans-sur-Isère, which converts
it to uranium oxide (UO2), pelletizes it(production of UO2 pellets), then fabricates the fuel assemblies for light water
nuclear power plants.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

121

Monitoring of Nuclear Fuel Cycle Facilities

Comurhex plantat Malvési
Based 3 km north of Narbonne in southern France since 1959 (Figure V.11), theComurhex Malvési plant produces 14,000
metric tons of uranium tetrafluoride(UF4) each year, a quarter of worldwide
production, from uranium concentrates(yellow cake).

The industrial process used leads to uranium discharge into the air via stacks on
the site and into the Tauran canalthrough the liquid waste dischargepipe. Between 1960 and 1980, the site
also used uranium recovered from irradiated nuclear fuel processing activities at
the Marcoule plant (southern France).
Waste produced during this period, with
contents including plutonium, ameri-

LegendMain roads
Highways
Water
Forest and farmland
Built-up areas andbusiness parks

Figure V.11 - Geographical location of the Comurhex Malvési site
295

Comurhex Malvési
IRSN

388

175

508

Continental aquatic
Terrestrial

Figure V.12 - Comurhex Malvési site: breakdown of the number of samples by data provider
and per compartment

122

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

cium-241 and technetium-99, wasstored in ponds on the plant site and is
still there.
Lastly, since the plant was opened,changes in the outfall have been madeand different events have occurred(discharge outlet pond overflows,
flooding due to poor weather).

V.3
Atmospheric compartment

Activity(mBq/m3)

15

Atmospheric aerosols
In the environment of the Comurhex Malvési
plant, atmospheric aerosol monitoring has
not detected any artificial radionuclides, as
shown by the tracking of gross alpha andbeta activity levels (Table V.3, Figures V.13
and V.14).
 able V.3 - Activity levels measured in atmospherT
ic aerosol samples collected in the environmentof the Comurhex Malvési plant (mBq/m3)

Radionuclide typeRadionuclide

Mean
activity(mBq/m3)Alpha
activity

0.055 ± 0.001

Beta
activity

0.39 ± 0.01

Gross
activity
indices

10

5

0
0
0
0
0
0
0
Jan.1 Feb.1 Mar.1 Apr.1 May1 Jun.1

Measurement < Decision threshold

Jul.10 Aug.10 Sept.10 Oct.10 Nov.10 Dec.10

Date
Significant measurement (> DT)F igure V.13 - Time plot of gross alpha activity in atmospheric aerosol samples collectedin the vicinity of the Comurhex Malvési facility (mBq/m3)
Activity (mBq/m3)

8
7
6
5

Only two unusual values were observed, inthe sample from October 25 to November 2,
2010: 12.56 ± 6.66 mBq/m3 for the grossalpha activity and 7.14 ± 1.78 mBq/m3 forthe gross beta activity. No particular event
was recorded during this period at the
Comurhex plant.

Terrestrial compartment
Terrestrial flora
Terrestrial plants are sampled regularly inthe area potentially affected by discharge,
i.e. to the east of the plant, and in the areas
not potentially affected.
Among the plant samples, cypress leaves
showed the highest activities of uranium
isotopes (Table V.4). In this bioindicator, the235U/238U isotope ratio expressed by weight(0.68 ± 0.02%), which is significantly lower
than the ratio measured in naturally occurring uranium (235U/238U = 0.72%), indicates
depletion of 235U. This means that the
predominant source of the uranium
measured in these plants is uranium discharged by the Malvési plant.
In the sampled foodstuffs (wheat ears
and lettuce leaves), the uranium isotope activity levels were generally lower
than in the cypress leaves, but werehighly variable. In these matrices, the235U/ 238U isotope ratio expressed byweight is similar to the ratio measured

4
3
2
1
0
0
0
0
0
0
0
0
0
0
0
0
0
Jan.1 Feb.1 Mar.1 Apr.1 May 1 Jun.1 Jul. 1 Aug.1 Sept.1 Oct. 1 Nov. 1 Dec. 1

Date
Significant measurement (> DT)

Measurement < DTF igure V.14 - Time plot of gross beta activity in atmospheric aerosol samples collectedin the vicinity of the Comurhex Malvési facility (mBq/m3)
 able V.4 - Uranium isotope activity levels in cypress leaf samples collected in the environment ofT
the Malvési site in 2011 (Bq/kg dry)Station

Type

234

235

236

238

235U/238U
by weight (%)

Malvési East

Cypress
leaves34 ± 41.6 ± 0.1

< 0.0237 ± 30.68 ± 0.02

UU

i n n a t u ra l ly o c c u r ri n g u ra n i u m(235U/238U = 0.72%).
In the terrestrial environment, analyses
by IRSN in 2007 (Étude radioécologiquede l’environnement du site de Malvési –report IRSN/DEI/SESURE 2008-20)
emphasized the effect on cypress leaves(Figure V.15) and wheat ears of uranium
from atmospheric discharge through thestack, and for 230Th, 241Am and the plutonium isotopes, the source of which was
diffuse releases from the site ponds.
The results obtained by ASN during aUUradiological inspection conducted in June
2011 in the environment of the
Comurhex plant show a decrease inconcentration levels in the terrestrial
environment (and in the aquatic environment) by discharge from this facility. In the terrestrial environment, theeffect on cypress needles and foodstuffs(wheat and lettuce) of uranium discharged into the atmosphere by theplant decreased compared with 2007,
when the previous radioecologicalstudy was carried out by IRSN. In addition, these matrices show, over the

IRSN – Report on the Radiological State of the Environment in France in 2010-2011123Monitoring of Nuclear Fuel Cycle Facilities

same period, a greater decrease in concentration levels radionuclides fromstorage ponds (plutonium isotopes) or
settling ponds (230Th) on the site.
Farm produce and foodstuffs
Fruit and vegetables
The impact of the atmospheric discharge
from the Malvési site decreases very rapidly
away from the prevailing wind direction andwith distance from the plant. Fruit and vegetables grown more than 4 km from the site
showed uranium-234 and 238 activity levels
compatible with a natural origin (Table V.5).
The average activity levels measured in
France, except for plants from uraniumbearing areas, are around a few millibecquerels per kilogram of wet matter, withsignificant variability depending on soil type.

Aquatic compartment
The Malvési site is located in the 6,000 km2
drainage basin of the river Aude. The hydrology near the site is characterized by a major
system of irrigation canals fed by the Aude,
which flows through an alluvial plain. The following irrigation canals are located near thesite:• Robine canal, which runs almost 1.7 km to
the east of the plant;• Cadariège canal and its feeders flowing
into the Mayral stream;• Tauran canal, which is to the east of theplant, also flows into the Mayral.
Measurements in water samples from the Tauran canals showed a gross alpha activity in theregion of 0.15 Bq/L in 2009-2010 (Figure V.16).
IRSN has been measuring gross alpha activity
in the Cadariège canal since 1975. In thewater of this canal, the gross alpha activity iscorrelated with the uranium concentration(w/v) (Figure V.17).

1,000

Bq.kg-1
Decay products of 238U

100

10

1

<0.05

<0.04

0.1

134
Cs
Cs 241Am
Man-made radionuclides
2007
2011

Be

7

137

235
234
230
U
Ac
Th
Th 226Ra
Naturally occurring radionuclides

228

Pb

214

Pb

210

F igure V.15 - Comparison of the specific activity levels of the main artificial and natural gammaemitting radionuclides in cypress leaves in 2007 and 2011 (Bq/kg)
Table V.5 - Activity levels measured in fruit and vegetables grown in the vicinity of the Comurhex
Malvési site (Bq/kg wet)

Location

4 km to the west, under thesecondary prevailing winds

Radionuclide
210Pb
226Ra
234U
235U
238U

Lettuce< 0.560.029 ± 0.009
0.04 ± 0.01
< 0.008
0.018 ± 0.006

0.45

9.5 km to the northwest, outside
the area of influence of theprevailing winds
Peach< 0.62< 0.0043< 0.0086< 0.0052< 0.0074

Bq/L

0.40
0.35
0.30
0.25
0.20
0.15
0.10
0

Nov. 09

Jan. 10Significant activity

Mar. 10

May 10Jul. 10

Sept. 10

Nov. 10Jan. 11Mar. 11

Decision threshold

Figure V.16 - Gross alpha activity measured in the Tauran canal (Bq/L)

Gross alpha activity (Bq/L)

Uranium (µg/L)

100

10,000

10

1,000

1

100

0,1

10

0.01
5
7
9
1
3
5
7
9
1
3
5
7
9
1
3
5
8
197 197 197 198 198 198 198 198 199 199 199 199 199 200 200 200 200
Gross alphaUranium
Figure V.17 - Gross alpha activity (Bq/L) and uranium concentration (µg/L) measured in the Cadariège canal (IRSN measurements)

124

IRSN – Report on the Radiological State of the Environment in France in 2010-20111

V.3
Grouped monitoring of
the Areva Tricastin
facilities
Since the 1960s the Tricastin industrial site
has accommodated several activities related
to the fabrication of nuclear fuel (by compa-

nies such as Comurhex, Eurodif, FBFC, Socatri)and use (by companies such as Areva, CEA,
EDF). This section presents the results ofspecific monitoring of facilities operated by
Areva (Comurhex, Eurodif, SET, Socatri andAreva NC), industries in the front end andback end of the nuclear fuel cycle (FigureV.18). The results of monitoring of nuclear

LegendWater
Forest and farmland
Built-up areas andbusiness parks
kilometers

power plants, including the Tricastin NPP,
are given in section V.4.
Comurhex Pierrelatte plant
The Comurhex Pierrelatte plant converts
uranium tetrafluoride (UF 4) to uranium
hexafluoride (UF6), a transformation step
between the mining of ore and the enrichment of uranium.
Eurodif Production plant
The Eurodif Production plant is also known
as the Georges Besse plant. Since 1982,
using a gaseous diffusion process, it has
produced uranium enriched in uranium-235
to a level sufficient for use in nuclear
reactors.
Areva Pierrelatte plant
The Areva Pierrelatte site is involved inseveral industrial steps of the nuclear energy
cycle, and in particular in uranium chemistry. This plant also carries out other work:
maintenance of uranium transport containers, and dismantling of gaseous diffusion
plants.
SET Georges Besse II plant
The Société d’Enrichissement du Tricastin(SET), part of the Areva group, operates the
new centrifugation uranium enrichment
plant on the Tricastin nuclear site. Inaugurated in 2010, it will gradually replace theEurodif plant.
Socatri plant
Socatri is a uranium purification and recovery facility. It deals with maintenance anddismantling of nuclear equipment, and thetreatment of liquid effluents and nuclear
waste.

Figure V.18 - Geographical location of the Tricastin nuclear site

41,8362,084

32,746

10,919255
Areva Tricastin
IRSN

Continental aquatic
Terrestrial
AtmosphericFigure V.19 - Tricastin nuclear site: breakdown of the number of samples by data provider
and by compartment

IRSN – Report on the Radiological State of the Environment in France in 2010-2011125

Monitoring of Nuclear Fuel Cycle Facilities

Atmospheric compartment
Atmospheric aerosols
In the environment of the Tricastin site,
atmospheric aerosols are monitored daily bymeasuring gross alpha and beta activity levels, by gamma spectrometry measurement,
and by additional analyses if an anomaly isobserved.
Uranium isotope activity levels above thecustomary values have been measured insamples collected by Areva and IRSN at
Pierrelatte (Table V.6). This occasional anomaly was due to an incident that occurred on
August 1, 2010, involving uranium releasethrough the gaseous effluent outlet of plant
W on the Areva site (this plant is specialized
in the deconversion of depleted uranium
hexafluoride (UF6)).
This event was reported by Areva to ASN on
August 3, 2010.
Table V.6 - Activity measured
in the sample collected between
August 1 and August 2, 2010 by an IRSN
monitoring station at
Pierrelatte (mBq/m3)

Radionuclide

Activity (mBq/m3)

Uranium-234

0.14 ± 0.05

Uranium-235

0.011 ± 0.009

Uranium-236< 0.0064

Uranium-238

0.83 ± 0.2

In a check by Areva, an abnormal gross alphaactivity value was observed in an aerosol
sample collected at Bollène between February 3 and 4, 2010 (1.7 ± 0.5 mBq/m3). Additional investigations by spectrometry led tothe conclusion that this unusual value was
not due to artificial radionuclides (absenceof plutonium isotopes and normal activity
levels of uranium isotopes) (Table V.7).

Other than these observations, no abnormal
activity was detected (Figures V.20 andV.21).
Activity (mBq/m3)

2

1.5

1

0.5

0
Apr. 10Jan. 10

Jul. 10

Measurement < DT

Jan. 11

Apr. 11Significant measurement (> DT)

Figure V.20 - Time plot of gross alpha activity in atmospheric aerosol samples collectedin the environment of the Tricastin site (mBq/m3)

Activity (mBq/m3)
4

3

2

1

0

Jan. 10

Jul. 10

Apr. 10

Measurement < DT

Oct. 10Jan. 11

Apr. 11Significant measurement (> DT)F igure V.21 - Time plot of gross beta activity in atmospheric aerosol samples collected in
the environment of the Tricastin site (mBq/m3)

 able V.7 - Activity measured in the sample collected between February 3 and 4, 2010
Tby one of the Areva monitoring stations at Bollène (mBq/m3)

126

Oct. 10

Radionuclide

Activity (mBq/m3)

Radionuclide

Activity (mBq/m3)

Plutonium-238< 0.063

Uranium-234

0.098

Plutonium-239< 0.0081

Uranium-235< 0.012

Plutonium-240< 0.0081

Uranium-238

0.021

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.3
An increase in gross beta activity was also
observed between the end of March and theend of April 2011 (Table V.8). This increase isattributed to the presence of artificial radionuclides linked with atmospheric fallout fromthe Fukushima accident.
For more information
Chapter III – Fukushima accident
Gases sampled by bubblers
Atmospheric tritium collectors are installed
to the north (Pierrelatte) and south(Bollène) of the Tricastin site, along the axisof the prevailing winds. Tritium in the form ofwater vapor was measured in 20% of the
air samples at values between 0.19 and0.87 Bq/m3 (Figure V.22). The mean activityof all the samples, taking decision thresholds
into account, was approximately 0.15 Bq/m3.

 able V.8 - Gross alpha and beta activity levels of atmospheric aerosols collectedTin the environment of the Tricastin site (mBq/m3)

Facility

Radionuclide

Mean activity (mBq/m3)

Areva NC Pierrelatte
Comurhex PierrelatteEurodif Production
Société d’enrichissement du Tricastin
SocatriGrossalpha activity

0.011 ± 0.001

Grossbeta activity

0.25 ± 0.01
0.54 ± 0.01** Measurements taken during the period of the nuclear accident at the Fukushima nuclear power plant
between March 22 and May 6, 2011.

1.2

Bq/m3

1.0
0.8

Rainwater

0.6

The rainwater collected near the Tricastin
NPP had tritium activity levels between thedecision thresholds and 7.8 Bq/L between
2009 and 2011 (Figure V.23).

0.4
0.2
0.0
10 Jun. 10
May

Bollene

1
1
1
0
1
0
0
1
0
0
0
Jul. 1 Aug. 1 Sept. 1 Oct. 1 Nov. 1 Dec. 1 Jan. 1 Feb. 1 Mar. 1 Apr. 1 May 1

Pierrelatte

Decision thresholdFigure V.22 - Activity of tritium in the form of water vapor in ambient air (Bq/m3)

12

Bq/L

10
8
6
4
2
0
0
0
9
Jul. 10Jan. 10
Mar. 1
May 1
Nov. 0Significant activity
Decision threshold0
Sept. 10Nov. 1

Jan. 111
May 1

Figure V.23 - Tritium activity in rainwater collected in the vicinity of the Tricastin site
(Bq/L)IRSN – Report on the Radiological State of the Environment in France in 2010-2011

127Monitoring of Nuclear Fuel Cycle Facilities

Terrestrial compartment
The terrestrial environnement of the Tricastinsite is subject to regular monitoring consisting of sampling grasses and plant produce
under and away from the areas of influenceof the prevailing winds.

 able V.9 - Mean activity levels measured in grass samples collected in the vicinity ofT
the Tricastin site (Bq/kg dry)*Radionuclide

La Garde-Adhemar
4 km north of the site,
outside the area ofinfluence

Lamotte-du-Rhône
4 km south of the site,
under the prevailing winds

Cs

< 1.6

< 1.6

Pu

< 0.005< 0.006Pu< 0.005< 0.006Am< 0.0075< 0.011U

0.5 ± 0.12

0.6 ± 0.14

U

< 0.18< 0.27238

U< 0.350.3 ± 0.14

HTO (Bq/kg wet)

< 2.2

< 2.5

C (Bq/kg C)

235.2 ± 1

234.8 ± 1.1

137
238

Terrestrial flora

239+240

Six-monthy grass samples are collected in
the vicinity of the Tricastin site on a northsouth axis. Uranium was measured in mostof the samples, with the same ranges ofactivity levels as those of grasses collectedaway from the potential effect of discharge(Table V.9). Activity levels of plutonium,
americium and free tritium remained below
decision thresholds. Similarly, the artificial
gamma-emitting radionuclides (137Cs, 134Cs,
131I, 54Mn, 58Co, 60Co, etc.) were not detectedby the measuring instruments used.
Carbon-14 results did not differ from theactivity levels measured in the same matrices in areas outside the influence of discharge from nuclear plants.
Farm produce and foodstuffs

241

234
235

14

* Unless otherwise indicatedTable V.10 - Mean activity levels measured in maize samples collected around the Tricastin site (Bq/kg dry)*Radionuclide

Pierrelatte
2.5 km north of the site,
outside the area of influence

Bollène
1.5 km south of the site,
under the prevailing winds

U (mg/kg dry)

< 0.006< 0.0021

U< 0.023< 0.008U< 0.015< 0.008U< 0.015< 0.008U< 0.015< 0.008U< 0.015< 0.008232

Cereals
The analysis results for uranium by weightand isotopes were lower than the decisionthresholds in all three maize samples collected
in 2010 near the Tricastin site (Table V.10).

234

No artificial gamma-emitting radionuclide
was detected in the wheat sample collected
at Chantemerle-lès-Grignan, about 12 km
northeast of the Tricastin site. Uranium
isotope analysis was not performed on thissample.

* Unless otherwise indicatedLeafy vegetables
In 2010, a lettuce sample collected 4 km
northwest of the Tricastin complex, in anarea located outside the influence of gaseousdischarge, was subjected to radiological analyses. The results showed that the major
activity was due to naturally occurring potassium-40 (Table V.11). Traces of uranium were
measured, giving activity levels similar to
those that can be observed in the naturalenvironment. Cesium-137, measured at a specific activity of 0.078 ± 0.036 Bq/kg wet,comes from persistent effects of the Chernobyl accident.

 able V.11 - Mean activity levels easured in the lettuce sample collectedTat Pierrelatte (Bq/kg wet)

235
236
238

Radionuclide

LettuceCs

0.078 ± 0.036

40K

99 ± 13

Other gamma-emitting RNs(124Sb, 125Sb, 110mAg, 134Cs, 58Co,
60Co, 54Mn, 106Ru, 131I)

<1

HTO

2.8 ± 1.8

U

0.06 ± 0.008

U

0.0033 ± 0.0015

U

0.06 ± 0.008

137

234
235
238

128

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.3
Continental aquaticcompartment
Surface water
The right-bank counter-ditch (Figure V.25),
which runs along the edge of the Tricastin
site, is intended to collect runoff water anddrain losses from the Donzère-Mondragon
canal. The counter-ditch collects water fromthe left bank through three different siphonscombined with a division box which divides
the water between the counter-ditch and thestarting point of the Gaffière stream.

0.16

Bq/L

0.14
0.12
0.10
0.08
0.06

The Gaffière flows north to south and crosses
the eastern part of the Tricastin site, with aspreading area in the middle forming a pond.
Immediately downstream of the site, theGaffière flows alongside the Trop Long pond,
where an overflow has been built in the leftbank for flood control. The Gaffière continues
alongside the Trop Long past this overflow
and joins the Mayre Girarde stream to form
the Lauzon.

0.04

The Donzère-Mondragon canal is a diversion
canal for the river Rhône running for 24 km
between Donzère and Mondragon. Locatedto the east of the Rhône, the canal
improves navigation on the river, controls theflow and supplies cooling water to the Tricastin nuclear site.

Uranium-238 concentrations in the water of
the Gaffière are observed on the Tricastin site
(0.13 Bq/L) and downstream of the site (0.06
Bq/L). The upstream part of the Gaffière
and the Donzère-Mondragon canal haveactivity levels of approximately 0.015 Bq/L
(Figure V.24).

0.02
0
9
Feb. 0

9
May 0

9
9
Aug. 0 Nov. 0

Donzère canal
Gaffière-Amont Tricastin

0Feb. 1

0
May 1

0
0
Aug. 1 Nov. 1

1
Feb. 1

1May 1

1Aug. 1

Gaffière-Aval Tricastin
Gaffière (on the site)© IRSNFigure V.24 - Uranium-238 activity in water from the Gaffière and the
Donzère-Mondragon canal (Bq/L)

Figure V.25 - Right-bank counter-ditch upstream of the Tricastin nuclear site

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

129

Monitoring of Nuclear Fuel Cycle Facilities

not detected by the measuring instruments used.

Sediment samples are collected regularly
from the watercourses located in thevicinity of the Tricastin nuclear complex
for radiological analyses. Sampling takes
place annually at five sampling stations:
two upstream of the site (Gaffière andDonzère-Mondragon canal -Figure V.26)
and three downstream (Gaffière, Lauzon
and Donzère-Mondragon canal).
The activity levels of cesium-137, the only
artificial radionuclide measured in all thesediment samples, showed no difference
between samples taken upstream anddownstream of the site (Table V.12). The
presence of cesium-137 can be linked toatmospheric fallout from nuclear weapons
testing and from the Chernobyl accident;
the variation of activity levels measured
in the different samples can be explainedby mineralogy and physical characteristics, in particular the granulometry, ofthe sediments. Other gamma-emitting
artificial radionuclides ( 124 Sb, 125 Sb,
110mAg, 134Cs, 58Co, 60Co, 54Mn, 106Ru) were

Sediment sampling downstream of thesite in the Gaffière showed uranium concentrations more than three times
higher than those measured upstream,
resulting from current discharge ofreprocessed uranium by the site. Despite

the dilution, the uranium concentrationis still high in the Lauzon, 3.5 km downstream of the nuclear complex.
The detection of traces of americium
and plutonium downstream of theGaffière can be linked to past nuclear
operations at the Tricastin site.

© IRSN

Sediments

Figure V.26 - Sediment sampling in the Donzère-Mondragon canal upstream of the Tricastin nuclear
site

Table V.12 - Mean activity levels measured in freshwater environment sediments in the vicinity of the Tricastin site (Bq/kg dry)*Donzère-Mondragon canalRadionuclide

Gaffière

3.2 km upstream of
Tricastin

5 km downstreamof Tricastin

1.5 km upstream of
Tricastin

100 m downstreamof Tricastin

3.5 km downstreamof Tricastin

Cs

nm2.07 ± 0.43

2.8 ± 0.6

6.8 ± 2.4

4.5 ± 0.9

I

nm

< 4.3

< 4.3

<5

< 4.9

137

131

K

31 ± 647 ± 8310 ± 5076 ± 10106 ± 15Pb

nm

51 ± 31

nm

nm

nm

Other gamma-emitting RNs (124Sb, 125Sb,
110mAg, 134Cs, 58Co, 60Co,
54Mn, 106Ru)

nm

< 19

< 17

< 21

< 21

Sr

nm

< 18

nm

nm

nm

Am

nm

< 0.15< 0.0170.29 ± 0.12

< 0.017

40
210

90
241

Pu

nm

< 0.16< 0.11

0.11 ± 0.07

< 0.15Pu

nm< 0.16< 0.11

0.11 ± 0.07

< 0.16

Calculated U content** (mg/kg dry)

nm

0.93 ± 0.11

0.62 ± 0.07

1.97 ± 0.2

1.83 ± 0.19

U

nm12.2 ± 1.3

7.7 ± 0.9

27.1 ± 2.7

24.1 ± 2.4Unm

0.8 ± 0.17

0.51 ± 0.13

2.18 ± 0.31

1.94 ± 0.29

U

nm11.5 ± 1.3

7.6 ± 0.8

24.2 ± 2.4

22.5 ± 2.3

238239+240

234
235
238

* Unless otherwise indicated** U by content calculated from the measured uranium isotopes
nm: not measured

130

LauzonIRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.3
Continental aquatic fauna able V.13 - Mean uranium concentrations measured in fish caughtTin the environment close to the Tricastin site (mg/kg wet)

In 2010, uranium was measured in fishcaught upstream and downstream of the
Tricastin nuclear site. The analysis results
were below decision thresholds (Table V.13).
Additional analyses were performed oneels caught in the Donzère-Mondragon
canal, downstream of the Tricastin complex.
The eels showed activity levels of the isotopes uranium-234 and -238 compatible
with a natural origin (Table V.14).
Added concentrations of carbon-14
were also observed in these samples. Thiscan be attributed to liquid discharge fromthe nuclear power plants in the Rhône valley (Section V.4).
Continental aquatic flora
Four pondweed samples are collected
every six months in the vicinity of the
Tricastin nuclear complex: two upstream ofthe site and two downstream in the
Gaffière and the Donzère-Mondragon
canal. One sample is also collected once a
year from the Lauzon, downstream ofwaste discharge from the Tricastin site
(Table V.15).
Analysis of these aquatic phanerogams
shows activity of approximately 620 Bq/kg
dry, due mainly to potassium-40. Traces ofcesium-137 from atmospheric fallout from
nuclear weapons testing and the Chernobyl
accident are detected both upstream anddownstream of the site. The presence of
iodine-131 observed in the sample fromupstream of the Tricastin site can be attributed to discharge from nuclear medicine
services, which use this radionuclide fordiagnosis or radiotherapy. Other gammaemitting radionuclides investigated (124Sb,
125Sb, 110mAg, 134Cs, 58Co, 60Co, 54Mn, 106Ru) inthe various watercourses upstream anddownstream of the Tricastin site were notdetected by the measuring instruments
used.
The isotopic uranium activities measured
were significantly higher downstream of thesite than upstream, and result from dischargeof reprocessed uranium by the site. These differences were greater in plants collectedfrom the Gaffière, which receives this discharge.

Donzère canal
3.2 kmupstreamDonzère canal
5 km
downstream

Gaffière
100 m
downstream

Lauzon
3.5 kmdownstream

Eel< 0.007< 0.006< 0.0046< 0.0035

Chub< 0.008

Not sampled< 0.007< 0.009 able V.14 - Specific activity levels measured in eels caught downstream of the Tricastin site in the
T
Donzère-Mondragon canal (Bq/kg wet)Radionuclide

ActivityC

128 ± 42

Cs

< 0.1

K

65 ± 13

Sr< 0.045

U< 0.01

U

0.01 ± 0.01

U

< 0.01U< 0.01

238

U

0.02 ± 0.01

Other gamma-emitting RNs (125Sb, 144Ce, 134Cs,
58Co, 60Co, 129I, 54Mn, 95Nb, 106Ru, 95Zr, 233Pa)

< 0.8

14
137

40
90

232
234
235
236

The aquatic plant samples collected downstream of the site from the Donzère-Mondragon canal and from the Gaffière
showed traces of activity levels of americium and plutonium slightly higher than
the activity levels measured in the
upstream sample in the canal, suggesting a mild impact from the site's discharge.

Lastly, traces of carbon-14 were observedin all the aquatic plants collected
upstream and downstream of the Tricastin complex (Table V.15). These can be
attributed to liquid discharge from thenuclear power plants of the Rhône valley.

The free tritium activity measured in theplants collected from the Donzère-Mondragon canal in November 2010, around
6 Bq/kg wet upstream and downstream of
the Tricastin complex, indicates slight contamination of the water of the Rhône byliquid discharge from the nuclear facilities
located upstream (Bugey, Saint-Alban and
Cruas NPPs in particular). The tritium
activity in plants collected at the sametime from the Gaffière, fed by the canal,
was 3.6 ± 1.8 Bq/kg wet. In June 2010,
the observed concentration level was
lower: the activity measured upstream of
the Tricastin site was 1.9 ± 1.6 Bq/kg wet.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011131

Monitoring of Nuclear Fuel Cycle Facilities

 able V.15 - Mean activity levels measured in the aquatic phanerogams (pondweed) collected from surface water nearT
the Tricastin site (Bq/kg dry)*Donzère-Mondragon canal

Gaffière

LauzonRadionuclide

5 km
upstream of Tricastin

5 km
downstream of
Tricastin

1.5 kmupstream of
Tricastin

100 m
downstream of
Tricastin

3.5 kmdownstream of
Tricastin

Cs

< 1.1

1.44 ± 0.46

1.7 ± 0.6

< 2.4

nm

131

I

6.5 ± 1.4

<9

<7

<9

nm

40

K

570 ± 60

420 ± 60680 ± 70820 ± 100

nm

Other gamma-emitting RNs(124Sb, 125Sb, 110mAg, 134Cs,
58Co, 60Co, 54Mn, 106Ru)

< 18

< 17

< 25

< 36

nm

Pu

< 0.015< 0.024nm< 0.026nm

Pu

0.015 ± 0.006

0.049 ± 0.021

nm

0.027 ± 0.011

nm

Am

0.018 ± 0.009

0.026 ± 0.019

nm

0.063 ± 0.022

nm

90

Sr

nm

< 0.31nm

nm

nm

U content (mg/kg dry)

1.05 ± 0.21
(3.2 km upstream of site)

0.76 ± 0.16

nm

1.49 ± 0.23

0.64 ± 0.13

U

4.22 ± 0.29

8.8 ± 0.8

10 ± 0.7

23.5 ± 1.6

nmU0.31 ± 0.041

0.59 ± 0.11

0.73 ± 0.09

2.61 ± 0.22

nm

238

U

3.85 ± 0.26

8.8 ± 0.8

9.7 ± 0.6

20.3 ± 1.4

nm

HTO (Bq/kg wet)

3.8 ± 1.2

6.2 ± 1.7nm

3.8 ± 1.3nm

C (Bq/kg C)

251.4 ± 1.2

267.2 ± 1.7

nm258.7 ± 1.4

nm

137

238

239+240
241

234
235

14

* Unless otherwise indicated
nm: not measured

Ground water
50

Ground water flows in the sandy gravel
alluvium of the Rhône. The alluvium is someten meters thick and highly permeable. The
aquifer is bounded at its base by an impermeable marl layer. The ground water is drainedby many streams and by the Rhône river.
The flow is from northeast to southwest, andfrom east to west at the site.
The piezometers at and near the Tricastinsite showed an average uranium concentration of 2.2 µg/L (Figure V.27). A number ofindividual points occasionally showed concentrations greater than 30 µg/L.

µg/L

45
40
35
30
25
20
15
10
5
0
Dec. 09

Feb. 10

Apr. 10Jun. 10

Jul. 10

Sept. 10

Nov. 10Jan. 11Mar. 11

May 11

Figure V.27 - Uranium concentration in the ground water sampled at and near the Tricastin site (µg/L)

132

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.3
FBFC plantat Romans-sur-Isère
Located south of Lyon in the Rhône valley (Figure V.28), FBFC at Romans-surIsère operates two basic nuclear
installations: the research reactor fuelfabrication unit (INB 63) and the PWR
reactor nuclear fuel fabrication unit (INB

98). The site also accommodates anenvironmentally regulated facility (ICPE
6 bis), the “Cavities” facility, where specific components of the LHC (Large
Hadron Collider), such as cavities andcollimators, are manufactured for theEuropean Organization for Nuclear
Research (CERN).

LegendDepartment
Municipalities
Highways
Main roads
Business park
Built-up area
Wine and fruit
Meadows
ForestWater

F igure V.28 - Geographical location of the FBFC Romans-sur-Isère site

3,727

2,944

571

212
FBFC

AtmosphericContinental aquatic
Terrestrial

Figure V.29 - FBFC Romans-sur-Isère plant: breakdown of the number of samples
by data provider and by compartment

IRSN – Report on the Radiological State of the Environment in France in 2010-2011133

Monitoring of Nuclear Fuel Cycle Facilities

Atmospheric compartment
Atmospheric aerosols
In the environment of the FBFC site at
Romans-sur-Isère, atmospheric aerosols
are monitored (Figure V.30) daily bydetermination of the gross alpha andbeta activity levels (Table V.16) followedby additional analyses if an anomaly isobserved, by systematic detection ofradionuclides using gamma spectrometry , and by analyses using inductively
coupled plasma mass spectrometry(uranium isotope measurement).

Facility
FBFC Romans-sur-Isère

Radionuclide

Mean activity (mBq/m3)

Gross alpha activity

0.047 ± 0.001

Gross beta activity

0.60 ± 0.01

 able V.17 - Uranium isotopes measured in atmospheric aerosols collectedTin the environment of the FBFC Romans-sur-Isère site (mBq/m3)

Facility

FBFC Romans-sur-Isère

Radionuclide

Mean activity (mBq/m3)

Uranium-234

0.015 ± 0.001

Uranium-235

0.00040 ± 0.00002

Uranium-236

0.00032 ± 0.00002

Uranium-238

0.0015 ± 0.0001

Other than this observation, no otherabnormal value of gross beta activity or
gross alpha activity was obtained. The
gamma spectrometry and mass spectrometry analyses showed that, apartfrom naturally occurring radionuclides,
no artificial radionuclide was detected in
the environment. In particular, theresults of the uranium isotope measurements showed activities compatible
with natural origin (Table V.17).

© Areva/Y. Geoffray

These checks showed a significant
level of niobium-95 in aerosols collected
between January 1 and 31, 2010 at
Romans-sur-Isère (0.034 ± 0.018 mBq/m3). However, given the uncertainty
associated with this measurement andthe absence of any significant measurement for zirconium-95 (parent of niobium-95), the actual presence of tracesof niobium-95 is highly unlikely.

 able V.16 - Gross alpha and beta activity of atmospheric aerosols collectedTin the environment of the FBFC Romans-sur-Isère site (mBq/m3)

F igure V.30 - Recovery of the filter used for sampling atmospheric aerosols on the FBFC Romans-sur-Isère site

134

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.3
Terrestrial compartment
Any radioactive element content due toatmospheric discharge from the nuclear
facilities of the FBFC plant at Romans-surIsère is determined following plant sampling
campaigns, monthly at four points on the site
and annually at fourteen points around thesite. The plants (Austrian pine, oak, mulberry,plane, grasses, mosses and cereals) are chosen according to their capacity to fix discharged substances and how representative
they are in the environment of the nuclear
site (Table V.18).
In general, the southern area of the FBFC
Romans site, directly under the prevailingwinds, showed the highest uranium concentrations, indicating a slight impact on theimmediate environment of the facility (FigureV.31). At distances greater than a few hundred meters, measurements in and outside
areas influenced by the prevailing winds
showed similar and very low values.

mg/kg dry
0.2
0.18
0.16
0.14
0.12
0.1
0.08
0.06
0.04
0.02
0
3/3/103/5/103/7/102/9/102/11/10
1/1/102/1/11
4/3/11
East
North
South
West
Figure V.31 - Uranium concentration in pine needles collected on the FBFC Romans-sur-Isère site
(mg/kg dry)

 able V.18 - Mean uranium concentrations measured in terrestrial plants collected in the vicinity of the FBFC
T
Romans-sur-Isère site (mg/kg dry)

Sampling locality
Pine needles

Oak leaves

Mulberry leaves

Grass

Terrestrial moss

Cereals

North

East

South

West

Distance

On siteOn site (northeast)

On siteOn sitemg/kg dry

0.0152 ± 0.0004

0.0189 ± 0.0005

0.0782 ± 0.0021

0.01685 ± 0.00045

Distance

750 m

1,000 m

500 m

ns

mg/kg dry

0.011 ± 0.0022

0.006 ± 0.0012

0.026 ± 0.0049

nsDistance

ns

ns

ns

750 m

mg/kg dry

ns

ns

ns

0.00219 ± 0.00042

Distance

200 m

200 m (southeast)

750 m

1,200 mmg/kg dry

< 0.0020.011 ± 0.0011< 0.004< 0.001

Distance

750 m

1,000 m

1,250 mns

mg/kg dry

0.237 ± 0.047

0.38 ± 0.08

0.198 ± 0.04

ns

Distance

1,200 m

200 m (southeast)

2,000 mns

mg/kg dry

0.003 ± 0.0006< 0.0020.004 ± 0.0008

ns

ns: sampling not specified in the monitoring plan

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

135

Monitoring of Nuclear Fuel Cycle Facilities

Continental aquaticcompartment

Romans and directed towards the municipal
treatment plant under a discharge agreement.

Surface water

The uranium concentrations measured in thewater of the Isère above the Pizançon dam orin downtown Romans were low, approximately 1.5 to 2 µg/L.

Discharge from the FBFC Romans-sur-Isère
plant are governed by the order of June 22,2000, which defines the nature and characteristics of the liquid radioactive discharge.
The water discharge includes industrial andchemical water potentially contaminated byuranium (nuclear workshop floor washingwater, process water, laundry water, etc.) andother liquid waste from chemical processes
collected around the site's treatment plant.
After physical-chemical treatment to trap
suspended solids, this liquid waste is discharged into the Isère. Rainwater and domestic wastewater are drained off by thedomestic wastewater system of the town of

Sediments, fauna and flora
The impact of liquid discharge on the natural aquatic environment is monitored byannual sampling and measuring of fish,
aquatic moss, aquatic plants and sedimentsfrom the Isère, at various points upstream
and downstream of the outfall. The main
measurement results for 2010 are given in
Table V.19.
The measured samples had uranium-234
and -238 activity levels of the same order ofmagnitude for each matrix and isotope ratios(235U/238U) compatible with natural sources.
The lack of difference between upstream anddownstream samples means that any impactof liquid discharge from the site on the environment is too small to be quantified. The
uranium measured comes from natural erosion. The Isère carries away about 16 metrictons of suspended solids annually.
Traces of uranium-236, a radionuclide characteristic of discharge from the FBFC site,were nevertheless observed in all fish caught
in the Isère.

Table V.19 - Activity levels measured in the sediments, aquatic flora and fauna of the Isère.

Upstream
Outfall 1.5 km

Upstream
Outfall
250 m

Downstream
Outfall 2.5 km

Downstream
Outfall 6 km

Downstream
Outfall 9 km

Upstream
Pizançon dam

Pizançon
dam

Downtown
RomansDownstream
Romans treatment
plant

BeaumontMonteux
dam

Cs

2 ± 0.9ns

2.1 ± 0.8

2.6 ± 0.9

ns

U

< 0.8

ns

< 0.67< 0.54ns

U

0.004 ± 0.001

ns

0.0027 ± 0.0008

0.0027 ± 0.0006

nsU< 0.008ns< 0.0074< 0.0054

ns

U

0.047 ± 0.01

ns

0.054 ± 0.012

0.054 ± 0.013

ns

Cs

ns

< 0.47

ns

ns

< 1.2

U

ns

< 8.4

ns

ns

< 2.8

U

ns

0.62 ± 0.13

ns

ns

0.31 ± 0.047

Uns< 0.022ns

ns< 0.022U

ns

16.4 ± 3.5nsns

5.6 ± 1.1Cs

3.5 ± 2.1

ns

4 ± 1.5

3.3 ± 2ns

U

20.2 ± 4.5

ns15.8 ± 4

75 ± 14ns

U

0.88 ± 0.16

ns

0.66 ± 0.13

4.2 ± 0.9

nsU

< 0.07ns< 0.062< 0.073ns

U

18.7 ± 3.7

ns12.3 ± 2.5

84 ± 17

ns

Cs

0.093 ± 0.039

ns

0.1 ± 0.035

0.056 ± 0.025

nsU< 0.12ns< 0.13< 0.11ns

U

0.000067 ± 0.000019

ns

0.000061 ± 0.000019

0.00006 ± 0.000011

nsU< 0.0012

ns< 0.0013< 0.0012

ns

U

0.00043 ± 0.00006

ns

0.00031 ± 0.00006

0.00068 ± 0.00008

ns

Radionuclide

137

234

Reed
(Bq/kg dry)

235
236
238
137

Commonwater moss
(Bq/kg dry)

234
235
236
238
137

234

Sediment(Bq/kg dry)

235
236
238
137

234

Fish
(Bq/kg wet)

235
236
238

ns: sampling not specified in the monitoring plan

136

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.3
SICN Annecy
Established in 1957, the Société Industriellede Combustible Nucléaire (SICN) at Annecy
in eastern France produced fuel for graphitemoderated gas-cooled reactors (GCR). SICN
(part of the Areva group) fabricated this fueluntil 1990, using natural and reprocesseduranium. It also manufactured metal parts on
an industrial scale for non-GCR nuclear fuelelements. In 2002, following its final withdrawal from the nuclear market that led tothe termination of its aluminum metallurgy
business, the SICN Annecy plant was
renamed Gemma. The site now focuses
exclusively on mechanical and machining
subcontracting for sectors including aircraft,electronics and mechanical engineering.
Areva monitors radioactivity in the groundwater on the SICN Annecy site. In piezometerno. 3, the measured uranium concentrations
were close to the ambient background(between 3 and 10 µg/L). In contrast, the uranium concentration averaged approximately
80 µg/L in the water of piezometer 2, and 20µg/L in piezometer 1, with a maximum valueof 100 µg/L measured in February 2010
(Figure V.33). The uranium levels measured in piezometers 1 and 2 indicate addedconcentrations in ground water related topast operations on the SICN Annecy site.

15

15

SICN Annecy Areva

Continental aquatic

Figure V.32 - SICN Annecy: breakdown of the number of samples by data provider
and by compartment.

120

µg/L

100
80
60
40
20
0

SICN Veurey-Voroize
Located at Veurey-Voroize in eastern France,
this SICN site was set up in 1960 as a
backup to the Annecy site. It consists of
two nuclear facilities (a nuclear fuel fabrication plant and a pelletizing unit) that wereshut down in the early 2000s. The endof-operation procedures were carried out
between 2000 and end-2005. Permits forthe dismantling operations were approved in
February 2006, allowing dismantling to begin.

Jan. 10

Mar. 10

May 10Jul. 10

Sept. 10

Nov. 10Jan. 11Mar. 11

Pz1
Pz2
Pz3
F igure V.33 - Uranium concentrations in ground water samples collected on the SICN siteat Annecy (µg/L)

99

95

SICN Veurey-Voroise Areva

4

Continental aquatic
Terrestrial

Figure V.34 - SICN Veurey-Voroize: breakdown of the number of samples by data provider
and by compartment.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011137

Monitoring of Nuclear Fuel Cycle Facilities

Surface waterand ground water
Water samples are taken from the Isère
downstream, opposite and upsteam of thedischarge pipe of two basic nuclear installations (INB) no. 65 and no. 90. The measured
uranium concentration, of approximately 2 µg/L,
is equivalent to the background of the Isère.
Many piezometers at various locations on thesite are used for radiological monitoring of
the ground water. The uranium content inthese piezometers varies between 10 and239 µg/L. Dry wells installed during the rehabilitation of the site for rainwater drainage
facilitate infiltration into the ground water.

The ground water is closely connected to theIsère, which is its outlet. The operator has
identified, around an area named S6 at thesouthern boundary of the site, a localizedzone of uranium contamination (about 2 g/kg) between the ground level and the groundwater (23 m). At piezometer Pz6, the uranium
content of the ground water increased steadily from 94 µg/L in January 2010 to 239 µg/L
in January 2011, then started to decrease in
April 2011 to 222 µg/L (Figure V.35).
The measurements made by the operator
have confirmed this decrease, to 209 µg/L in
the third quarter of 2011 and then 194 µg/L
in the fourth quarter. This sampling point islocated in the immediate vicinity of dry well

µg/L
300
250

PP2, which has a history of additional uranium concentrations from runoff water fromtarred surfaces, themselves marked by thepassage of handling equipment. As part of
the Veurey site INB cleanup project, between
September and December 2011 these tarredsurfaces in the vicinity of PP2 were
removed and PP2 was cleaned. This cleaning operation, by removal of the drain,
involved work likely to modify the soil structure and consequently temporarily increase
the diffusion of uranium concentrations in
the ground water in the vicinity of point Pz6.
Sediments
No significant difference was observed
between upstream and downstream sediments of the SICN nuclear site (Table V.20).
The uranium content was slightly higher
opposite the discharge pipe, 2.6 ± 0.26 mg/
kg dry compared with 1.4 ± 0.14 mg/kg dry
upstream of the site.

200

Aquatic flora150

In 2010, as part of the annual sampling program, four aquatic phanerogam samples werecollected upstream and downstream of the
SICN Veurey-Voroize site: three from theIsère (reeds on the bank closest to the outfall) and one from the Ruisset (mixture of
reeds from the bank and aquatic phanerogams immersed on the river bed). The uranium concentration measured in the Isère
downstream of the site was lower than theconcentration upstream (Table V.20). The
impact of discharge from the SICN VeureyVoroize nuclear facility on the aquatic flora
is not detectable.

100
50
0
Oct. 09

Jan. 10

May 10Aug. 10

Nov. 10

Feb. 11

Jun. 11F igure V.35 - Uranium concentrations in ground water samples collected at point Pz6 on the SICN
Veurey-Voroize site (µg/L)

Table V.20 - Mean uranium concentrations measured in the vicinity of the SICN Veurey-Voroize site (mg/kg dry)

Isère

138

RuissetUpstream of thedischarge pipe

Opposite thedischarge pipe

Downstream of thedischarge pipe

Downstream of the site

Immersed andnon-immersed aquatic
phanerogams

8.8 ± 0.9

6.1 ± 0.6

3.6 ± 0.36

11 ± 1.1

Sediments

1.4 ± 0.14

2.6 ± 0.26

1.8 ± 0.18

1 ± 0.1

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4

V.4 Environmental
monitoring of
nuclearpower plants
The French nuclear power plant fleet
consists of 58 pressurized water reactors(PWR) in operation, located at 19 nuclear
power plants (NPP) operated by EDF.
They are all located close to a watercourse or on the coast , because water
is essential as a coolant for the satisfactory operation of PWRs. In addition tothese operating reactors, nine reactors(GCR, FNR and PWR) are being dismantled and one reactor (EPR) is under construction (Figure V.36).
An example of the regulatory obligations
applicable to the operator of a nuclear
power plant with regard to environmental monitoring is given in Chapter I (Table
I.6).
To facilitate the presentation of the sites
and the analysis of the results, the NPPs
are grouped by drainage basin (e.g.
Rhône, Loire) or by geographical region(NPPs of northeastern France).

Gravelines

Chooz

Penly
PaluelCattenom

Flamanville

Meuse
Seine

MoselleNogent-sur-Seine

Rhin
Brennilis

Saint-Laurent-des-Eaux Dampierre-en-Burly
Loire

Fessenheim

Belleville-sur-Loire

ChinonCivauxLe Bugey

VienneLoire

Le Blayais

Saint-Alban

Creys-Malville

900 MWe reactor
Dordogne

1,300 MWe reactor
1,450 MWe reactor
1,600 MWe reactor (EPR under construction)

Cruas-Meysse
Tricastin

GolfechRhône

Marcoule-Phénix

GaronneReactor being dismantled(GCR, PWR, FNR)

Figure V.36 - Location and type of French NPPs

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

139

Monitoring of Nuclear Fuel Cycle Facilities

Monitoringof nuclear power
plants of the Loiredrainage basin© EDF/MédiathèqueThere are five nuclear power plants in the
Loire drainage basin (Figure V.37): four on thebanks of the Loire (Belleville-sur-Loire,
Dampierre-en-Burly, Saint-Laurent-des-Eauxand Chinon) and one on the Vienne (Civaux).

Figure V.38 - Saint-Laurent-des-Eaux NPP

LoiretOrléans
SartheDampierre-en-BurlySaint-Laurent-des-Eaux
Gien

AngersMaine-et-Loire

NantesBelleville-sur-Loire
Cher

Indre-et-Loire
ChinonVienneVendéeLoir-et-Cher

ChinoneLoir
La

La Loire

Blois

Tours

Deux-Sèvres

La Vienne

Loire-Atlantique

Indre

Poitiers
CivauxHaute-Vienne
Belleville-sur-Loire
CreuseCharente

Nuclear power plants
Major urban centers
RiversDepartments
Figure V.37 - NPP locations in the Loire drainage basin

140

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Civaux NPP

3,447

949

3,031

241

1,124

Located south of Poitiers on the left bank of
the river Vienne in western France, the Civaux
power plant has two 1450 MW pressurized water reactors put into service in1997 and 1999.

EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.39 - Breakdown of the number of samples by data provider and by environment for the
Civaux NPP

Belleville-sur-Loire
NPP

2,651

923

2,812

207

488

The Belleville nuclear power plant is locatedon the left bank of the Loire, about 100 km
upstream of Orléans in north-central France.
It has two 1300 MW pressurized water reactors, put into service in 1987 and 1988.

EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.40 - Breakdown of the number of samples by data provider and by environment for the
Belleville-sur-Loire NPP

Dampierre-en-Burly
NPP

2,442

917

2,811

131

417

The Dampierre-en-Burly nuclear power plant
is located on the Loire downstream fromBelleville, 45 km upstream of Orléans. It has
four 900 MW reactors, all put into service in1980 and 1981.

EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.41 - Breakdown of the number of samples by data provider and by environment for theDampierre-en-Burly NPP

IRSN – Report on the Radiological State of the Environment in France in 2010-2011141Monitoring of Nuclear Fuel Cycle Facilities

Saint-Laurent-des-Eaux
NPP

2,832

907

2,984

552

203

The Saint-Laurent-des-Eaux nuclear power
plant (Figure V.38) is located on the left bank of
the Loire between Blois (30 km) and Orléans(24 km). It has two 900 MW pressurizedwater reactors (B1 and B2), put into service in
1981. Two other reactors, (GCR A1 and A2), putinto service in 1969 and 1971, were shut down
permanently in 1990 and 1992.

Chinon NPP
The Chinon nuclear power plant is located inwest-central France. It has four 900 MW
pressurized water reactors, put into service
in 1982, 1983, 1986 and 1987. It also has
three GCR reactors being dismantled (ChinonA, built from 1956 to 1966), an irradiatedmaterials workshop and a storage facility for
new fuel intended for French nuclear power
plants.

EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.42 - Breakdown of the number of samples by data provider and by environment for theSaint-Laurent-des-Eaux NPP

3,164

1,126

1,034

3,055

Atmospheric compartment
Atmospheric aerosols
Apart from the observations recorded during
the period of the Fukushima accident, monitoring of the gross beta activity did not reveal
any abnormal value (Figure V.44). The gamma
spectrometry measurements showed that,apart from naturally occurring radionuclides(7Be, 210Pb), no artificial gamma-emitting
radionuclide could be measured above thedecision thresholds of the instruments used.
Significant levels of cesium-134, cesium-137
and iodine-131 were observed by gamma
spectrometry between the end of March2011 and the beginning of May 2011 (Table
V.21). These observations can be attributed
to radioactive fallout on French territory fromthe accident at the Fukushima nuclear plantin Japan. During this same period, an increasein the beta activity index was also recorded(Table V.22). This short-term rise was related
essentially to the presence of artificial
radionuclides in the air after the Fukushima
accident.

For more information
Chapter III – Fukushima accident

201
EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.43 - Breakdown of the number of samples by data provider and by environment for the
Chinon NPP

Activity (mBq/m3)

Fukushima accident

Jan.-10

Jul.-10
Oct.-10Jan.-11
Apr.-10
Measurement < DT
Significant measurement (> DT)

Apr.-11

Figure V.44 - Time plot of the gross beta activity in atmospheric aerosol samples
collected in the environment of the Loire drainage basin NPPs (mBq/m3)

142

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
 able V.21 - Radionuclides measured in aerosols from the environment of the Loire drainage basin
T
NPPs during the period of the accident at the Fukushima nuclear plant(March 22 to May 6, 2011) (mBq/m3)

Plant
Belleville-sur-Loire,
Chinon,Civaux,Dampierre-en-Burly,
and Saint-Laurent-des-Eaux
NPPs

Radionuclide

Mean activity (mBq/m3)

Cesium-134

0.034 ± 0.008

Cesium-137

0.050 ± 0.008

Iodine-131

0.42 ± 0.05

Rainwater

 able V.22 - Gross beta activity in atmospheric aerosol samples collected in the environmentTof the Loire drainage basin NPPs (mBq/m3).

In rainwater collected near the NPPs of theLoire drainage basin, two significant tritium
measurements were recorded at Civaux
and Chinon (Figure V.45), at levels very close
to the decision thresholds for this radionuclide. These activity levels can be related togaseous discharge from the NPPs concerned.

Plant

Mean activity (mBq/m3)

Belleville-sur-Loire NPP

0.29 ± 0.01
0.53 ± 0.02*

Chinon NPP

0.26 ± 0.01
0.64 ± 0.02*
0.35 ± 0.01
0.65 ± 0.02*

Gross beta
activity

Civaux NPP

Gases sampled by bubblers
Tritium and carbon-14 measurements in
atmospheric samples from the environment in the immediate vicinity of nuclear
sites did not show values higher than thedecision levels at any of the NPPs in the
Loire drainage basin.

Radionuclide

Dampierre NPP

0.28 ± 0.01
0.52 ± 0.02*

Saint-Laurent-des-Eaux NPP

0.34 ± 0.01
0.75 ± 0.02** Measurements made from March 22 to May 6, 2011 during the period of the accident at the Fukushima
nuclear plant

30

Bq/L

25
20
15
10
5
0
Nov. 09

Jan.10Mar.10 May10

Significant activity Chinon

Jul. 10 Sept. 10

Nov. 10Significant activity Civaux

Jan. 11Mar. 11 May11

Decision threshold

Figure V.45 - Tritium activity in rainwater collected in the vicinity of the Loiredrainage basin NPPs (the decision thresholds are averaged for all
the NPPs – IRSN and EDF data) (Bq/L)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

143

Monitoring of Nuclear Fuel Cycle Facilities

Terrestrial compartment

Farm produce and foodstuffs

Terrestrial flora

Milk
All the results showed that the radioactivity
measured in milk was mainly due to naturally
occurring potassium-40, with mean activity
concentrations between 46.8 ± 1.5 Bq/L
and 54.7 ± 1.9 Bq/L. No artificial gammaemitting radionuclide was detected above
the decision thresholds of the instruments
used. The free tritium measurements werealso below the decision thresholds.

Grass samples were collected monthly in
two municipalities located near the
nuclear power plants. Under normal circumstances, gamma spectrometry analysis results
for most samples did not reveal traces ofartificial radioactivity attributable to discharge from the power plants. Only one
grass sample, collected in the vicinity of
the Civaux plant, showed significant
cesium-137 activity (1.7 ± 0.47 Bq/kg dry
on January 8, 2010) out of the 34 samples
collected around this site between January2010 and June 2011.
At the beginning of April 2011, traces ofiodine-131 and cesium-134 and -137 weredetected near the Civaux NPP. Traces ofiodine-131 were also measured near the Chinon nuclear plant. These activity levels werea consequence of releases following theaccident at the Fukushima plant in Japanon March 11, 2011.
For more information
Chapter III – Fukushima accident
Soil

In the 32 analyses performed, only one significant strontium-90 measurement wasobserved in milk collected in the vicinity of
the Belleville NPP. The measured activity ofthis radionuclide (0.4 ± 0.35 Bq/L) is low andcan be attributed to past fallout from atmospheric nuclear weapons testing.
Cereals
Gamma-emitting radionuclides discharged or
likely to be discharged by the NPPs were notdetected in the wheat samples collected near
the sites.

Leafy vegetables
In 2010, lettuce samples were collected near
Belleville, Chinon and Civaux NPPs. The radioactivity in these samples was due mainly tonaturally occurring potassium-40, whichshowed activity levels varying between 80 ±8 Bq/kg and 190 ± 20 Bq/kg wet according
to the geographical sector.
The specific activity of carbon-14 measured
near the Civaux plant was 232 ± 1.3 Bq/kg
of carbon. This activity is similar to the measurements taken in areas not affected by discharge from the NPPs.
Traces of cesium-137 close to the decisionthresholds were detected in nearly all samples (activity levels between 0.02 and0.04 Bq/kg wet). These activities can be
attributed to fallout from the Chernobyl accident in 1986.
The specific activity levels of the other artificial radionuclides (110mAg, 60Co, HTO, etc.)
likely to be discharged by these NPPs
remained below the decision thresholds(Table V.24).

Table V.24 - Activity levels measured in lettuce collected near the Loire drainage basin NPPs (Bq/kg wet*).

Cesium-137 was measured in all the soil
samples collected near the Civaux, Belleville,
Saint-Laurent-des-Eaux and Chinon NPPs, at
activity levels between 2 ± 0.15 Bq/kg dry
and 9.1 ± 0.12 Bq/kg dry.
These activity levels (Table V.23) were due
mainly to past atmospheric fallout (theChernobyl accident in particular).

Radionuclide

Civaux NPP

Belleville-sur-Loire
NPP

ChinonNPP

K

91 ± 7101 ± 17134 ± 9Cs

0.023 ± 0.004

0.04 ± 0.007

0.023 ± 0.005

Other gamma-emitting RNs(54Mn, 58Co, 60Co, 110mAg,
134Cs)< 0.024< 0.029nm

C (Bq/kg carbon)

232 ± 1.3

nm

nm

HTO

<9

nm

nm

40
137

14

* Unless otherwise indicated able V.23 - Cesium-137 activity levels measured in soil in the vicinity of the Civaux NPP
T(Bq/kg dry)

Sampling locality

Leignes-sur-Fontaine

Lhommaize

Sillars

Distance from theCivaux NPP

8.5 km under the
primary prevailingwinds

5.5 km under thesecondary prevailingwinds

12 km, outside thearea of influence

Cs activity(Bq/kg dry)

9.1 ± 1.1

5.3 ± 0.49

3.7 ± 0.6

137

144

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Wine
The analyses performed on red wine produced in the vicinity of the Chinon plant did
not detect artificial gamma-emitting radionuclides above the decision thresholdsof the instruments used. Only naturally
occurring potassium-40 was measured,at a mean activity concentration of
36 ± 2.7 Bq/L.

V.4
Continental aquaticcompartment

The river Vienne, which has its source in
the Massif Central, flows for 400 kilometers to join the Loire. Its average widthis 100 meters in the last part of its
course. Notably, it is joined by a verylarge number of streams and small
rivers, and its main tributaries are theCreuse and the Clain. Some of thesemany tributaries are affected by former
mining sites.
Surface water
The Loire
The tritium discharged into the Loire by
the four NPPs can be detected almost
constantly. They discharge total tritium
activity of 160 TBq/year in liquid form,
17% of the liquid discharge of tritiumby the EDF fleet. The Saint-Laurent-desEaux NPP coordinates the discharge of
all the NPPs discharging into the river.
Unless a waiver is agreed, two tank discharges cannot be carried out at thesame time.

m3/s

900
800
700
600
500
400
300
200
100
0

2004

2005

2006

2007

2008

2009

2010

Figure V.46 - Flow rate of the Loire at Orléans – source: Banque Hydro (m3/s)

160

Bq/L

140
120
100
80
60
40
20
0
19
72
19
74
19
76
19
78
19
80
19
82
19
84
19
86
19
88
19
90
19
92
19
94
19
96
19
98
20
00
20
02
20
04
20
06
20
08
20
10

The nuclear plants in the Loire drainage
basin are located on two rivers: the Loireand its tributary, the Vienne. The first NPP
on the banks of the Loire is locatedabout 500 km downstream of its source,
at a point where the river curves to thewest, its bed broadening considerablyacross the plain to reach an averagewidth of 300 meters; shifting shoals ofsand and pebbles appear. The large areaof the drainage basin, the influence ofthe oceanic climate in its western andnorthern part, and the flat relief result inhigh variations of the flow rates, withsudden floods. A dam was built at Villerest, 235 km upstream of Belleville-surLoire, to limit the major floods to
8,500 m3/s and to maintain a minimum
flow rate in low water periods. The average annual flow rate of the Loire is 350
m3/s at Orléans and 900 m 3/s at its
mouth (Figure V.46).

Saint-Laurent

Belleville

ChinonDampierre

Figure V.47 - Tritium activity downstream of the Loire NPPs (Bq/L)

explained by the consultation on discharge and renewal of the water intake
and discharge permits, which resulted insmoothing of the activity levels measured in the Loire from 1999.

The time plot of the tritium activity
measured by IRSN since the 1970s
shows the decrease in tritium activity
discharged by nuclear plants into theenvironment in the Loire, but with amarked accumulation effect at Chinon
up to 2000 (Figure V.47). This can be

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

145

Monitoring of Nuclear Fuel Cycle Facilities

Seasonal effects can be observed, with higher
activity levels at low water and lower activity levels during winter flood periods (FigureV.48). However, this natural effect issmoothed by the procedure for liquid waste
discharge from the NPPs, which determines
the maximum activity flow rate at the maindischarge points for a 24-hour average flowrate Q (in L/s) of the Loire. Thus, for tritium,
this value is 80 x Q for the Dampierre-enBurly NPP.
The severe climatic conditions in May-June
2011, with a substantial rainfall deficit, led
to increased tritium activity in the river to alevel that had not been observed since1996. However, these activity levels
remained compliant with the discharge
permits applicable to nuclear power plant
operators.
Other than tritium, strontium-90 was the
only radionuclide detected in the vicinity of
the Chinon and Saint-Laurent-des-Eaux NPPs,
with activity levels close to the decisionthresholds (Figure V.49). These measurements were made in the past because of theuse of the GCR system at Saint-Laurentdes-Eaux and Chinon A. There are also spentgraphite storage silos on the Saint-Laurentdes-Eaux site. However, the strontium-90
activity levels measured here can be linked
to atmospheric fallout from nuclear weapons
testing.
The Vienne
Discharge from the Civaux NPP are monitored
by means of automated sampling of theVienne river. Since 2001, an increase in tritium activity has been observed in water samples collected downstream of the NPP, withthe annual mean rising from about 9 Bq/L in
2000 to 27 Bq/L in 2010 (Figure V.50).

140
120
100
80
60
40
20
0

1
1
0
1
0
0
0
9
9
8
9
8
8
8
9
.0
g.1
y 0 ug. 0 ov. 0 eb. 0 ay 0 ug. 0 ov. 0 eb. 1 ay 1 ug. 1 ov. 1 eb. 1 ay 1
Feb Ma
F
F
F
Au
M
A
A
M
M
N
N
A
N
Significant activity (> DT)
Figure V.48 - Tritium activity downstream of the Dampierre NPP, illustrating the cyclic nature of the measured
activity levels
Bq/L
0.008

0.007
0.006
0.005
0.004
0.003
0.002
0.001
0
Nov. 09 Dec. 09

Jan. 10 Feb.10 Mar. 10 Apr. 10 May 10 Jun. 10

Significant activity (> DT)

Jul. 10 Aug. 10 Sept. 10

Decision threshold

Figure V.49 - Strontium activity in water samples collected from the Loire (Bq/L)

Bq/L

30
25
20
15
10
5
0

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010
CivauxFigure V.50 - Mean annual tritium activity in the Vienne river downstream of the Civaux NPP (Bq/L)

Ground water60

The ground water samples collected in thevicinity of the NPPs located on the banks of
the Loire had additional concentrations oftritium at an activity of about 10 Bq/L, witha maximum value of 49 Bq/L measured at
Dampierre-en-Burly in July 2010. There did
not appear to be any variability or changing trend over time (Figure V.51).

Bq/L

Bq/L

50
40
30
20
10
0
1
1
1
0
0
0
0
0
0
0
0
0
0
0
0 -10
.
.-1
r.-1 r.-1 ay-1 Jun-1 Jul.-1 Jul.-1 ug.-1 pt.-1 ct.-1 ov.-1 ec.-1 an.-1 eb.-1 ar.-1
Jan Feb Ma Ap
J
F
M
A
M
O
D
O
Se
Significant activity (> DT)
Decision threshold

Figure V.51 - Tritium activity in ground water under or near the Loire NPPs (Bq/L)

146

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Sediments
Analysis results for sediments sampled
upstream and downstream of theBelleville-sur-Loire, Chinon and Civaux
NPPs did not show significant differences
between the upstream and downstream
stations (Table V.25). An increase incesium-137 activity levels was observed
along the course of the Loire: 5.6 ± 0.8
Bq/kg dry upstream of the Belleville-surLoire plant and 9.6 ± 1.2 Bq/kg dry
downstream of Chinon. However, theseresults do not allow a distinction to bemade between the activity attributable to
NPP discharge and the activity related topersistent traces of fallout from the
Chernobyl accident.

In 2010, cobalt-60 was detected in one of
the two samples collected downstream of
the Civaux plant at a specific activity of
0.68 ± 0.35 Bq/kg dry. This low level ofradioactivity can be attributed to the permitted routine discharge from the NPP.
Other gamma-emitting artificial radionuclides likely to be discharged by the NPPs
were not detected by the measuring
instruments used.
Continental aquatic fauna
In 2010, analyses were performed on fishcaught upstream and/or downstream of thefollowing four NPPs: Belleville-sur-Loire, SaintLaurent-des-Eaux, Chinon and Civaux.

Among the gamma-emitting artificial radionuclides discharged or likely to be discharged
by the NPPs, only cesium-137 was measured
in all samples, at mean specific activity levels of between 0.033 ± 0.018 and 0.283 ±0.037 Bq/kg wet (Table V.26). No significant difference in activity was observed
between areas upstream and downstreamof the plants. This observation may berelated to the seasonal movements or
migration of fish during their lives. In contrast, analyses performed on fish caught
downstream of the Saint-Laurent-des-Eaux
NPP detected small quantities of tritium(activity close to the decision threshold),
attributable to the routine discharge fromthis plant, and carbon-14 at an activity of
350 ± 1.7 Bq/kg carbon, higher than the
background (235 Bq/kg carbon).

Table V.25 - Mean activity levels measured in sediment samples from the freshwater environment of the Loire drainage basin NPPs (Bq/kg dry)

Belleville-sur-Loire NPPRadionuclide

Chinon NPP

Civaux NPP

2.5 kmupstream
La-Celle-surLoire

5.5 kmdownstream
Beaulieusur-Loire

15 km
upstream
Bréhémont

5 km
downstream
Savignyen-Véron

10 km
downstream
Varennessur-Loire

2.5 kmupstream
Civaux

6 km
downstream
Valdivienne

Cs

5.6 ± 0.8

5.4 ± 0.9

6.7 ± 1.5

6.1 ± 0.7

9.6 ± 1.2

10 ± 0.8

9 ± 1.1

Co< 0.12< 0.13nm

nm

nm< 0.140.23 ± 0.0840K980 ± 140

1,000 ± 100

620 ± 90660 ± 90770 ± 110710 ± 70660 ± 70

Other gammaemitting RNs(54Mn, 58Co,
110mAg, 134Cs)< 0.68< 0.65nm

nm

nm< 0.81

< 0.6

137
60

nm: not measured
Table V.26 - Mean activity levels measured in fish caught in the Loire drainage basin NPPs (Bq/kg wet*).

Belleville-sur-Loire NPPSaintLaurent-des-Eaux
NPP

Chinon NPP

Civaux NPP

Common carp

FishCommon carp

Common carp

Radionuclide

12.5 kmdownstream
Châtillonsur-Loire

16 km
downstream
Fontainesen-Sologne

8 km
upstream
Rigny Usse

4 km
downstream
Chouzesur-Loire

7 km
upstream
Lussacles-Châteaux0.033 ± 0.018 0.039 ± 0.028

0.062 ± 0.015

0.045 ± 0.021

0.065 ± 0.021

0.283 ± 0.037 0.236 ± 0.026

1 km
upstream
Sury-prèsLéré
Cs

137

4 km
downstream
Valdivienne

40K

150 ± 20140 ± 2090 ± 11140 ± 20150 ± 20165 ± 14118 ± 9Other gammaemitting RNs(54Mn, 58Co, 60Co,
110mAg, 134Cs)< 0.31< 0.21< 0.23nm

nm< 0.13

< 0.1

HTO

nm

nm

5.4 ± 1.5

nm

nm

nm

nm

C (Bq/kg
carbon)nm

nm350.3 ± 1.7

nm

nm

nm

nm

14

* Unless otherwise indicated
nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010-2011147

Monitoring of Nuclear Fuel Cycle Facilities

Continental aquatic flora
In 2010, gamma spectrometry analyses were
performed on aquatic phanerogam samples
collected upstream and downstream of theBelleville-sur-Loire, Chinon and Civaux NPPs.
Artificial radionuclides (110mAg, 58Co, 60Co)
were measured at levels close to the decision thresholds downstream of the Civaux
NPP (Table V.27). They were not detected
upstream of the site, and indicate slight
added concentrations in the aquatic environment due to the liquid waste discharge
from this plant. Cesium-137 was measured
upstream and downstream of the site at
specific activity levels of 0.445 ± 0.038 Bq/
kg wet and 0.328 ± 0.045 Bq/kg wet,respectively.

The cesium-137 activity levels at the NPPs
located on the banks of the Loire varied considerably, although overall the values measured downstream of the plants were slightly
higher than the values obtained in the
upstream samples. However, the possible
contribution by the NPPs to the radioactive
cesium in the aquatic environment cannot
be distinguished from the main sources ofadded environmental concentration in France(fallout from Chernobyl and from atmospheric nuclear weapons testing).

Table V.27 - Mean activity levels measured in aquatic phanerogam samples at the Belleville-sur-Loire, Chinon and Civaux NPPs (Bq/kg dry)

Belleville-sur-Loire NPP

Chinon NPP
Reed canary
grass
15 km
upstream
Bréhémont

Reed canary
grass
11 km
downstream
Varennessur-Loire

Reed canary
grass
13 km
downstream
ParnayAquatic
ranunculus
2.5 kmupstream
CivauxAquatic
ranunculus
6.5 kmdownstream
Valdivienne< 0.04nm

nm

nm< 0.035

0.067 ± 0.017< 0.046< 0.043

nm

nm

nm

< 0.032< 0.0310.232 ± 0.037

0.11 ± 0.06

0.5 ± 0.06

0.56 ± 0.07

0.53 ± 0.07

1.01 ± 0.13

0.445 ± 0.038

0.328 ± 0.045

Co< 0.048< 0.23< 0.048

nm

nm

nm

< 0.046

0.047 ± 0.016

Co< 0.046< 0.058< 0.055

nm

nm

nm

< 0.0420.095 ± 0.042

Mn< 0.056< 0.064< 0.063

nm

nm

nm

< 0.05< 0.05K

920 ± 130

1,210 ± 200

1,220 ± 240

620 ± 70940 ± 130870 ± 130900 ± 90804 ± 47

Pondweed

15 km
upstream
Cosne
Cours-sur-Loire

Reed canarygrass
2.5 kmupstream
La Cellesur-Loire

11 km
downstream
Ousson-surLoireAg< 0.037< 0.061Cs< 0.032

Cs

PondweedRadionuclide

110m

134

137

58

60

54

40

nm: not measured

148

Civaux NPP

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Monitoringof nuclear power
plants in northeast France
There are three nuclear power plants innortheast France (Figure V.52), located on
the banks of the Meuse (Chooz NPP), theMoselle (Cattenom NPP) and on the Grandcanal d’Alsace alongside the Upper Rhine(Fessenheim NPP).

Nuclear power plants
Major urban centers
RiversDepartments

Nord
Chooz

BELGIUM
Charleville-Mézières
Aisne
LUXEMBOURG
Ardennes
Cattenom
GERMANY
Reims
euse
La M

Metz
Moselle

Marne
Meuse
Nancy

Strasbourg
Bas-Rhin

Le Rhin

Meurthe-et-Moselle

le
sel
Mo
La

Aube

VosgesGERMANY
Fessenheim

Haute-Marne

Haut-Rhin
Territoirede-Belfort

Haute-Saône

Doubs

Figure V.52 - NPP locations in northeast France

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

149

© EDF Médiathèque/S.Brandstrom

Monitoring of Nuclear Fuel Cycle Facilities

Figure V.53 - Chooz NPP

150

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Chooz NPP

3,350

The Chooz nuclear power plant (Figure V.53)
is located beside the Meuse in a small enclaveof French territory in the Ardennes, close to
the Belgian border. The Chooz B site has two
1450 MW pressurized water nuclear reactors,
put into service in 1996. The Chooz A plant, in
operation between 1967 and 1991, has onepressurized water reactor (PWR), currently
being dismantled.

956

3,015

163

1,143

15
EDF
IRSN
ASN

AtmosphericContinental aquatic
Terrestrial

Figure V.54 - Breakdown of the number of samples by data provider and by environment for theChooz NPP

2,506

1,161

3,124

132

415

Fessenheim NPP
The Fessenheim nuclear power plant is locatedbeside the Grand Canal d’Alsace, some thirty
kilometers northeast of Mulhouse, near the
Swiss and German borders. It has two
900 MW reactors put into service in 1977.

4
EDF
IRSN
ASN

AtmosphericContinental aquatic
Terrestrial

Figure V.55 - Breakdown of the number of samples by data provider and by environment for the
Fessenheim NPP

Cattenom NPP
The Cattenom nuclear power plant is locatedbetween the Moselle and the Garche national
forest, not far from the German and Luxembourg borders. The plant has four 1300 MW
pressurized water reactors, put into service
in 1986, 1987, 1990 and 1991.

3,266

1,009

8
EDF
IRSN
ASN

1,192

2,936

155
AtmosphericContinental aquatic
Terrestrial

Figure V.56 - Breakdown of the number of samples by data provider and by environment for theCattenom NPP

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

151

Monitoring of Nuclear Fuel Cycle Facilities

Atmospheric compartment

Activity (mBq/m3)
4

Atmospheric aerosols

Fukushima accident

3

Apart from the observations recorded during the period of the Fukushima accident,
monitoring of the beta activity index did notreveal any abnormal value (Figure V.57). The
gamma spectrometry measurements
showed that, apart from naturally occurring radionuclides (7Be, 210Pb), no artificial
gamma-emitting radionuclide could be measured above the decision thresholds of the
instruments used.
Significant levels of cesium-134, cesium-137
and iodine-131 were observed by gamma
spectrometry between the end of March 2011
and the beginning of May 2011 (Table V.28).
These were due to the radioactive fallout on
French territory from the Fukushima accident.
During this same period, an increase in the
gross beta activity was also recorded (Table
V.29). This short-term rise was also related tothe presence of artificial radionuclides in the
air after the Fukushima accident.
For more information
Chapter III – Fukushima accident
Rainwater
IRSN measured significant tritium activity
levels in rainwater collected in the immediate
vicinity of the Cattenom NPP, of approximately 5 Bq/L (Figure V.58). No other significant activity of anthropogenic origin wasmeasured in the rainwater collected in theimmediate vicinity of the Fessenheim, Chooz
and Cattenom NPPs, nor in the ambient air.
Gases sampled by bubblers
No significant activity of gaseous tritium was
detected near the NPPs in northeast France
over the period January 2010 - June 2011.

2

1

0

Jan. 10

Apr. 10

Measurement < DT

Jul. 10

Oct. 10Jan. 11

Apr. 11Significant measurement (> DT)

Figure V.57 - Time plot of the beta activity index in atmospheric aerosol samples
collected in the environment of the NPPs in northeast France (mBq/m3)
 able V.28 - Radionuclides measured in atmospheric aerosol samples collectedTin the environment of the NPPs of northeast France during the period of the Fukushima accident(March 22 to May 6, 2011) (mBq/m3)

PlantsCattenom, Chooz,
and Fessenheim NPPs

Radionuclide

Activity (mBq/m3)

Cesium-134

0.030 ± 0.004

Cesium-137

0.034 ± 0.004

Iodine-131

0.11 ± 0.02

 able V.29 - Gross beta activity in atmospheric aerosol samples collected in the environment of the
T
NPPs in northeast France (mBq/m3)

Plant

Radionuclide

0.38 ± 0.01
0.73 ± 0.02*

Cattenom NPP
Chooz NPP

Mean activity (mBq/m3)

Gross beta activity

0.26 ± 0.01
0.49 ± 0.02*
0.38 ± 0.01
0.60 ± 0.02*

Fessenheim NPP* Measurements made from March 22 to May 6, 2011 during the period of the nuclear accident
at the Fukushima nuclear plant

8

Bq/L

7
6
5
4
3
2
1
0

0
0
0
9
0
0
0
r. 1 pr. 1
y 1 un. 1
c. 0 Jan. 1 Feb. 1
J
A
Ma
Ma
De
Significant activity (> DT)

0
0
0
0
0
.10
g.1
t. 1 ct. 1
v. 1
c. 1
Jul
Au
O
De
No
Sep

Decision threshold

Figure V.58 - Tritium activity in rainwater collected in the vicinity of the Cattenom NPP (IRSN
measurements) (Bq/L)

152

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Terrestrial compartment

Continental aquaticcompartment

Terrestrial flora
Surface water
Two grass samples were collected monthly
around each NPP. Their analysis did notdetect any gamma-emitting radionuclides
potentially emitted by these plants. A single
significant value of cesium-137 (2.8 ± 1.6
Bq/kg dry on January 4, 2011) was measured
near the Chooz NPP out of the 34 analyses
performed around the plant.
Occasional traces of iodine-131, which canbe attributed to the accident at the Fukushima nuclear plant, were observed at the
beginning of April 2011 in grass collectedaround the Cattenom and Fessenheim plants.
For more information
Chapter III – Fukushima accident
Farm produce and foodstuffs
Cereals
Gamma-emitting radionuclides discharged or
likely to be discharged by NPPs were notdetected in wheat samples collected in thevicinity of the sites. Only naturally occurring
potassium-40 was measured, at a mean activity of 132 ± 12 Bq/kg dry.
Milk
The naturally occurring radioactivity measured in cow’s milk collected around theChooz, Fessenheim and Cattenom NPPs
was mainly due to potassium-40, giving amean activity concentration of
50.7 ± 1.4 Bq/L.

Chooz NPPThe Meuse river is 950 km long, with a drainage basin of 36,000 sq km oriented south tonorth. Its source is close to the Langres plateau in eastern France, where the Seine also
rises.
The Meuse shows seasonal flow fluctuations,with high water in winter (mean monthly
flow rates of 250 m³/s from December toMarch) and low water in August-September(mean monthly flow rates of 50.5 m³/s).
The tritium activity measured downstreamof the NPP (Figure V.59) was related to theliquid discharge from the NPP. The mean
activity measured in the Meuse downstream in 2010 was 22 Bq/L, with a minimum of 8.4 Bq/L and a maximum of
36 Bq/L measured by IRSN. The final shutdown of Chooz A in 1991 led to a substantial
reduction of the tritium activity in the Meusein the early 1990s, then a slight increase, but
on average lower than or close to 20 Bq/L.

140

Bq/L

120
100

Leafy vegetables
The only significant activity measured in lettuce samples collected in the vicinity of the
Fessenheim NPP was of naturally occurring
potassium-40, at a specific activity of 131 ±17 Bq/kg wet. The activity levels of artificial
radionuclides (gamma emitters, tritium)
were all below the decision thresholds of themeasuring instruments used.

80
60
40
20
0

19
70
19
72
19
74
19
76
19
78
19
80
19
82
19
84
19
86
19
88
19
90
19
92
19
94
19
96
19
98
20
00
20
02
20
04
20
06
20
08
20
10

No trace of artificial radioactivity wasobserved. All the measurement results (131I,
134Cs, 137Cs, 90Sr, HTO) were below the decision thresholds of the measuring instruments used.

Figure V.59 - Annual tritium activity in the Meuse river downstream of the Chooz NPP (Bq/L)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

153Monitoring of Nuclear Fuel Cycle Facilities

Cattenom NPP
The Moselle, a tributary of the Rhine, has
its source in the Vosges mountains. Its
drainage basin in France covers about
11,500 sq km. At Bertrange-Imeldange,
20 km upstream of the NPP, the mean
monthly flow rate of the Moselle is about
250 m³/s from December to March,decreasing to 50 m³/s in the summer.
No abnormal gross alpha or gross beta
activity was detected in the surface
water samples collected upstream anddownstream of the NPP, and no artificial
40

radionuclide other than tritium was
detected.
The tritium concentrations measured
downstream of the NPP can be related
to the routine liquid discharge by theplant. The mean activity measured in
the Moselle downstream of the NPP in2010 was 36 Bq/L, with a minimum of
14.4 Bq/L and a maximum of 51 Bq/L.
The activity measured downstream of
the NPP shows an upward trend (Figure V.60), increasing from 15 Bq/L in
1985 to 35 Bq/L en 2010.

Bq/L

35
30
25

15
10
5

20
09

20
07

20
05

20
03

20
01

19
99

19
97

19
95

19
93

19
91

19
89

19
87

19
85

0
Significant activity (> DT)
Figure V.60 - Annual tritium activity in the Moselle downstream of the Cattenom NPP (Bq/L)
Flow rate (m3/s)

2,000

1,500

1,000

500

0
2003

2004

2005

2006

2007

2008

2009

2010

2011

Figure V.61 - Mean monthly flow rate of the Rhine at Lauterbourg (Banque Hydro data) (m3/s)

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The tritium activity measured downstreamof the Fessenheim NPP was not significantly different from that measured
upstream (Figure V.62). Tritium activity has
decreased steadily since 1976. Since 2008,
improved metrological performance has enabled IRSN to again measure tritium in thewater of the Rhine, at levels close to 5 Bq/L.
The activity levels of this radionuclide canbe related to the routine liquid discharge by
the plant. Another source of tritium in the
Rhine is the Swiss watchmaking industry,
which has discharged tritium in organic formbound to sediments at activity levels of
approximately 3000 to 8000 Bq/L into theRhine and the Rhône, where the slow, persistent breakdown of the organic materials
results in transfer of tritium from the solid
phase to the aqueous phase.

20

2,500

Fessenheim NPP
The source of the Rhine is on the flank of theSaint-Gotthard massif, in the east of Switzerland. Its hydrological regime is regular. At
Lauterbourg, 150 km downstream from Fessenheim, the amplitude of the annual variation of monthly flow rates is about 1000 m3(Figure V.61). The Fessenheim NPP is locatedbeside the Grand Canal d’Alsace, which runs
parallel to the Rhine, separated from it by a
few hundred meters, over a distance of
50 km.

V.4

40

Bq/L

35
30
25
20
15
10
5
0
1975

1980

1985

Significant activity (> DT)
upstream of NPP

1990

1995

2000

Significant activity (> DT)
downstream of NPP

2010

2005

Decision threshold

Figure V.62 - Annual tritium activity in the Grand Canal d’Alsace upstream and downstreamof the Fessenheim NPP (Bq/L)

Ground water
Ground water monitoring by the operatorof the Chooz NPP demonstrated the absenceof detectable quantities of anthropogenic
radionuclides.
The operator of the Fessenheim NPP analyses the ground water around the plant atseveral monitoring points (piezometers). The
gross alpha and beta activity levels are similar
to the background, and fission products suchas cesium-134 and -137 are not detected in
the piezometers. Exceptionally high tritium
activity of 460 Bq/L was measured at point
BTN EST in April 2011 (Figure V.63), which subsequently decreased rapidly when pumping
was implemented (at well N08) to recover
the tritiated water. Investigations of the facilities by EDF have identified the causes of these
tritium activity increases: the first involved arecovery area for liquid waste from thewater tank used to fill the reactor pools ofunit 2; the second was related to theoverflow of a liquid waste tank on March 6,
2011. On March 30, 2011, the Fessenheim NPP
declared a significant environmental excursion to ASN following this increase in tritium activity.
At the Cattenom NPP, operators monitor
ground water quality by means of eightpiezometers. Three sampling points showedslight tritium concentrations, including
piezometer NAPPE N2 located at the site
(Figure V.64).

600

Bq/L

500
400
300
200
100
0

0
1
1
0
0
1
1
2
9
9
0
8
9
9
g.1
. -1 eb. 1
v. 0 eb. 0 ay 0 ug. 0 ov. 0 eb. 1 ay 1 ug. 1 ov. 1 eb. 1 ay 1
F
F
FF
Au Nov
M
M
M
A
A
N
N
No
Significant activity (> DT)

Decision threshold

Figure V.63 - Tritium activity in ground water samples collected at point BTN EST of the
Fessenheim NPP (Bq/L)

30

Bq/L

25
20
15
10
5
0

9
v. 0
No

. 10
Jan

0
r. 1
Ma

0
y1
Ma

. 10
Jul

0
t. 1
Sep

0
v. 1
No

. 11
Jan

1
r. 1
Ma

1
y1
Ma

Significant activity (> DT)
Figure V.64 - Tritium activity in water samples collected at point NAPPE N2 of the Cattenom NPP (Bq/L)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

155

Monitoring of Nuclear Fuel Cycle Facilities

Monitoringof nuclear power
plants of the Garonne
drainage basin
There are two nuclear power plants in theGaronne drainage basin (Figure V.65), locatedon the bank of the Garonne river (Golfech
NPP) and on the Gironde estuary (Le Blayais
NPP).

Charente

Corrèze
Dordogne
Le Blayais

La Dordogne

Bordeaux

e
nn
ro
Ga
La

Lot

GirondeLot-et-Garonne

Agen
GolfechTarn-et-Garonne

Landesarn
Le T

Toulouse

Gers
Haute-Garonne
Nuclear power plants
Major urban centers
RiversDepartments
Figure V.65 - NPP locations in the Garonne drainage basin

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© EDF

V.4

Figure V.66 - Le Blayais NPPLe Blayais NPP

2,651

923

392

2,984

Located on the right bank of the Gironde
estuary, the Le Blayais NPP (Figure V.66) ishalf-way between Bordeaux and Royan, inthe middle of 6,000 hectares of marshland. It
has four 900 MW pressurized water
reactors put into service in 1981, 1982,
and 1983.
194
EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.67 - Breakdown of the number of samples by data provider and by environment for
Le Blayais NPP

Golfech NPP

2,950

1,129

792

3,050

The Golfech nuclear plant is located downstream of the confluence of the Tarn andGaronne rivers, 80 km from Toulouse, insouthwestern France. It has two 1300 MW
pressurized water reactors, put into service in1990 and 1994.

258
EDF
IRSN
ASN
Pyrénées laboratory

13 8

AtmosphericContinental aquatic
Terrestrial

Figure V.68 - Breakdown of the number of samples by data provider and by environment for
Golfech NPP

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

157

Monitoring of Nuclear Fuel Cycle Facilities

Atmospheric compartment

Activity (mBq/m3)
10

Atmospheric aerosols
Apart from the observations recorded during the period of the Fukushima accident,
monitoring of the gross beta activity did notreveal any abnormal value (Figure V.69). The
gamma spectrometry measurements
showed that, apart from naturally occurring radionuclides (7Be, 210Pb), no artificial
gamma-emitting radionuclide could be measured above the decision thresholds of the
instruments used.
Significant levels of cesium-134, cesium-137
and iodine-131 were observed by gamma
spectrometry between the end of March2011 and the beginning of May 2011 (Table
V.30). During this same period, an increase in
the beta activity index was also recorded(Table V.31). This short-term rise was related
essentially to the presence of artificial
radionuclides in the air after the Fukushima
accident.
For more information
Chapter III – Fukushima accident*
8

Fukushima accident

6

4

2

0

Jan. 10

Apr. 10

Measurement < DT

Jul.10Oct. 10Jan. 11

Apr. 11Significant measurement (> DT)

Figure V.69 - Time plot of the gross beta activity in atmospheric aerosol samples collectedin the environment of the Garonne drainage basin NPPs (mBq/m3)* Abnormal value (8.6 ± 2.1 mBq/m3 on March 31, 2011) entailing additional measurements leading
IRSN to exclude this result from its study on the impact in France of fallout
from the Fukushima accident.
 able V.30 - Radionuclides measured by gamma spectrometry in atmospheric aerosol samples colT
lected in the environment of the Garonne drainage basin NPPs during the period of the Fukushima
accident (March 22 to May 6, 2011) (mBq/m3)

Plant
Le Blayais and
Golfech NPPs

Radionuclide

Mean activity (mBq/m3)

Cesium-134

0.033 ± 0.007

Cesium-137

0.043 ± 0.007

Iodine-131

0.83 ± 0.07

 able V.31 - Gross beta activity in atmospheric aerosol samples collected in the environmentTof the Garonne drainage basin NPPs (mBq/m3)

Plant

Radionuclide

Le Blayais NPP
Gross beta activity
Golfech NPP

Mean activity (mBq/m3)
0.31 ± 0.01
0.53 ± 0.02*
0.33 ± 0.01
0.59 ± 0.02** Measurements made from March 22 to May 6, 2011 during the period of the nuclear accident
at the Fukushima nuclear plant

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© EDF Médiathèque/Eranian Philippe

V.4

Figure V.70 - Recovery by an EDF technician of an atmospheric aerosol sample collected on a filterin the environment near the Le Blayais NPP

Rainwater and gases collectedby bubblers
No artificial radionuclide other than tritium(5 Bq/L) was measured in rainwater or gases
collected in the immediate vicinity of the Le
Blayais and Golfech NPPs.

Terrestrial compartment
Terrestrial flora
Most of the results of gamma spectrometry
analyses on grass samples collected near the
Golfech and Le Blayais NPPs were below thedecision thresholds of the measuring instruments used.
However, cesium-137 was occasionallydetected in two samples (out of a total of 66
samples analyzed between January 2010
and May 2011). The specific activity levels measured near the Golfech and Le Blayais
NPPs were 2 ± 0.9 Bq/kg dry and 0.13 ±0.04 Bq/kg dry, respectively.
Following the accident on March 11, 2011 at
the Fukushima nuclear plant, traces ofiodine-131 and cesium-134 and -137 weredetected in the grass samples collected in April
2011 at the two NPPs.
For more information
Chapter III – Fukushima accident

Soil
Cesium-137 was detected in all the soil samples collected near the Golfech and Le
Blayais NPPs at specific activity levels of
4.3 ± 0.6 and 0.59 ± 0.1 Bq/kg dry, respectively. These activity levels can be attributed mainly to fallout from the Chernobyl
accident. Other artificial radionuclides discharged or potentially discharged by the
NPPs were not detected by gamma spectrometry analysis.
Farm produce and foodstuffs
Cereals
No gamma-emitting artificial radionuclide
was detected in the wheat sample collected
near the Golfech plant.
Milk
A cow’s milk sample is collected and analyzed every month from two farms near the
Golfech and Le Blayais NPPs. No trace of artificial radioactivity attributable to atmosphericdischarge from these nuclear plants ( 131I,
134Cs, 137Cs, 14C, 3H) was detected in thesemilk samples. Only naturally occurring
potassium-40 was detected, at a mean concentration of 52.2 ± 1.2 Bq/L.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

159

Monitoring of Nuclear Fuel Cycle Facilities

Root vegetables
Radishes collected near the Le Blayais plant
did not show any trace of artificial radionuclides (gamma emitters, HTO) attributable todischarge from the plant.
Wine
In 2010, a red wine produced on the
côteaux du Blayais near the Le Blayais plant
was analyzed by gamma spectrometry. Mostof the measured radioactivity was due to naturally occurring potassium-40 (36.4 ±3.8 Bq/L). No artificial radionuclide was
detected. Analyses carried out on grape
juice obtained by crushing the pulp, produced at Saint-Estèphe, led to the same conclusions (activity concentration ofpotassium-40 of 50.5 ± 4.8 Bq/L).
Radioactivity measurements made on apple
juice produced at Donzac, near the Golfech
NPP, were below the decision thresholds
for artificial radionuclides. Potassium-40
was measured at an activity concentration of 55 ± 5 Bq/L.

Continental aquatic compartment
The headwaters of the Garonne are in the Aran
valley in the Spanish Pyrenees, and the river is
647 km long. Its drainage basin covers about
55,000 sq km.
The flow rate of the Garonne, observed since2004 immediately downstream of the Golfech
NPP located on the right bank, is around
320 m3/s (Figure V.71). The mean monthly
low water flow rate is about 60 m3/s, while
the winter flood flow rate is about 700 m3/s,
with instantaneous flow rates of up to 1,500m 3/s in 2010. The Garonne thus shows
marked seasonal flow rate fluctuations.

1,400

Flow rate (m3/s)

1,200
1,000
800
600
400
200
0
2003

2004

2005

2006

2007

2009

2008

2010

2011

Figure V.71 - Mean monthly flow rate of the Garonne at Lamagistère (source: Banque Hydro) (m3/s)

Surface water
The tritium activity measured in the water of
the Garonne downstream of Golfech has
been about 10 Bq/L, varying between 8 and
14 Bq/L, since 1990 (Figure V.72).
20

Bq/L

18
16
14
12
10
8
6
4
2
0
0
199

2
199

4
199

6
199

Significant activity (> DT)

8
199

0
200

2
200

4
200

6
200

Decision threshold

Figure V.72 - Mean annual tritium activity measured in water from the Garonne
at Laspeyres, downstream of the Golfech NPP (Bq/L)

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IRSN – Report on the Radiological State of the Environment in France in 2010-2011

8
200

0
201

V.4
The Le Blayais NPP draws water from theGironde estuary for cooling its condensers.
The meeting of the alluvium-rich fresh water(the Garonne and the Dordogne supply 900
m3/s of fresh water) with salt water (theflood tide comprises 20,000 m3 of sea water)flocculates the clayey particles and forms asilt plug characteristic of estuary water.
Samples taken directly from the discharge
channel of the NPP show tritium activity
levels of 5 to 40 Bq/L which, after dilution in
the estuary, are in general no longer detectable at Vitrezay or at Pauillac (Figure V.73).
Ground water
Analysis of the results at five piezometersof the Le Blayais NPP showed that the
ground water at point N01 had additional
concentrations of tritium (Figure V.74),
and that its activity had increased since2009, from 10 Bq/L to 25 Bq/L. The grossbeta activity, of approximately 0.8 to 1 Bq/L,
can be attributed to potassium-40 from sea
water present in the ground water.
Sediments
In 2010, sediment samples were collected
upstream and downstream of the Le Blayais
NPP (Table V.32). The analysis results indicated that cesium-137 was present at similarlevels at the two sampling points. There isconsequently no quantifiable impact of liquid discharge, the measured cesium-137
being mainly the result of fallout fromatmospheric nuclear weapons testing in the
1960s and from the Chernobyl accident. It
should be noted that the other gammaemitting artificial radionuclides likely to bedischarged by the NPP (58Co, 60Co, 110mAg,
54 Mn, etc .) were not detected by themeasuring instruments used.
Continental aquatic fauna
Low levels of cesium-137 were measured infish caught upstream and downstream of the
Le Blayais plant (Table V.33). Other artificial
radionuclides likely to be discharged in liquid
effluent from PWR plants (58Co, 60Co, 110mAg,
54Mn, 14C, 3H, etc.) were not quantified.

Bq/L

45
40
35
30
25
20
15
10
5

0
Oct.-09

Jan.-10

PauillacMay-10Vitrezay

Aug.-10Discharge channel

Feb.-11

Nov.-10Jun-11

Decision threshold

Figure V.73 - Tritium activity measured in the water of the Gironde estuary and in the overflow
of Le Blayais NPP (Bq/L)

45

Bq/L

40
35
30
25
20
15
10
5
0
.-09
Nov

.-10
janv

.-10
Mar

-10
May

10
Jul.-

0
t.-1
Sep

.-10
Nov

-11
Jan.

.-11
Mar

-11
May

Significant activity (> DT)
Figure V.74 - Tritium activity in ground water at point N01 on the site of Le Blayais NPP (Bq/L) able V.32 - Activity levels measured in sediment samples from the aquatic environment upstreamTand downstream of Le Blayais NPP (Bq/kg dry)Radionuclide

7.5 km - SouthSaint-Androny

8 km - North
Saint-Sorlin-de-Conac

Cs

6.1 ± 0.9

5.4 ± 0.7K840 ± 120830 ± 120

137

40

Table V.33 - Activity measured in fish caught upstream and downstream of Le Blayais NPP (Bq/kg wet)

Fish

Fish

7.5 km - SouthSaint-Androny

3 km - North
Saint-Ciers-sur-GirondeCs0.081 ± 0.36

0.066 ± 0.029

K

180 ± 0.20

140 ± 10

Radionuclide

137

40

IRSN – Report on the Radiological State of the Environment in France in 2010-2011161

Monitoring of Nuclear Fuel Cycle Facilities

Monitoringof nuclear power
plants of the Rhône
drainage basin

Ain

Haute-Savoie

L’A
in

La Saône

There are five nuclear power plants in the
Rhône drainage basin (Figure V.75) located on
the banks of the Rhône upstream of Lyon
(Creys-Malville and Bugey NPPs) and downstream (Saint-Alban, Cruas and Tricastin
NPPs).

Rhône
Loire

Bugey

Lyon

CreysMalville
SavoieIsère
Le RhôneL’IsèreSaint-Alban

Haute-Loire
ArdècheRomans-sur-Isère

Valence

L’Ardèche

Drôme

Cruas

Hautes-Alpes
Montélimar

LozèrePierrelatte
Alpes-deHaute-Provence

Tricastin

Gard

Vaucluse

Le
Ve
rd
or

Avignon

La Durance
Hérault

Bouches-du-Rhône
Var

Nuclear power plants
Major urban centers
RiversDepartments

Figure V.75 - NPP locations in the Rhône drainage basin

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IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Alpes-Maritimes

© Grégoire Maisonneuve/IRSN

V.4

Figure V.76 - Cruas NPP

Creys-Malville site
The Creys-Malville nuclear site is located ineast-central France 50 km east of Lyon and
60 km west of Chambéry. It is on the bank of
the Rhône 30 km upstream of the Bugey
nuclear power plant. The site accommodates
the industrial prototype of a sodium-cooled
fast neutron reactor. The 1200 MW Superphénix reactor was put into service in 1985. Following a government decision, its final
shutdown was implemented in December
1998, and it is currently being dismantled.

3,002

EDF
IRSN

962

176

729

3,059

AtmosphericContinental aquatic
Terrestrial

Figure V.77 - Breakdown of the number of samples by data provider and by environment for the
Creys-Malville site

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

163

Monitoring of Nuclear Fuel Cycle Facilities

Bugey NPP

1,001

38

49

914

Located on the right bank of the Rhône,some thirty kilometers from Lyon, theBugey NPP has four 900 MW pressurizedwater reactors put into service in 1978 and1979. It also has a GCR reactor, shut down in1994 and currently being dismantled.
Note: Following a technical incident affecting
the transmission of data from the Bugey NPP to
the RNM, only the measurements made by IRSN
were available for use in this 2010-2011 report. The results of the monitoring measurements made by EDF are now available on the
RNM website: www.mesure-radioactivite.fr.

AtmosphericContinental aquatic
Terrestrial

IRSN

Figure V.78 - Breakdown of the number of samples by data provider and by environment for the
Bugey NPPSaint-Alban NPP

2,464

897

178

340

2,843

Located on the left bank of the Rhône, 50 km
south of Lyon, the Saint-Alban NPP has two
1300 MW pressurized water reactors put into
service in 1985 and 1986.

EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.79 - Breakdown of the number of samples by data provider and by environment for theSaint-Alban NPP

Cruas NPP

3,121

902

144

907

2,972

The Cruas-Meysse plant (Figure V.76) islocated on the right bank of the Rhône, insoutheastern France near Montélimar. It has
four 900 MW pressurized water reactors put
into service in 1983 and 1984.

EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.80 - Breakdown of the number of samples by data provider and by environment for the Cruas
NPP

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IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
1,726

Tricastin NPP

182

18

356

1,534

Located on the right bank of the Rhône diversion canal about 70 km north of Avignon, inthe south of France, the Tricastin NPP has four
900 MW pressurized water reactors put into
service in 1980 and 1981.
Note: Following a technical incident affecting thetransmission of data from the Tricastin NPP to the
RNM, the majority of the measurements used forthis 2010-2011 report were made by IRSN. The
results of the monitoring measurements made by
EDF are now available on the RNM website: www.
mesure-radioactivite.fr.

EDF
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure V.81 - Breakdown of the number of samples by data provider and by environment for the
Tricastin NPP

Atmospheric compartment

Activity (mBq/m3)
10

Atmospheric aerosols
8

In 2010, monitoring of atmospheric aerosols
detected some abnormal values of the grossbeta activity in samples collected in the environment of the Creys-Malville NPP, at CreysMépieu, on June 3-4, 2010: 9.2 ± 1.1 mBq/
m 3 and 5.0 ± 0.7 mBq/m 3 . Additional
investigations by the operator establishedthat these unusual activity levels were notdue to artificial radionuclides.
Apart from these observations and theresults obtained during the period of the
Fukushima accident, monitoring of the grossbeta activity did not reveal any abnormal
value (Figure V.82). The gamma spectrometry
analyses showed that, apart from naturally
occurring radionuclides (7Be and 210Pb), no
artificial radionuclide was present in theenvironment.
Significant levels of cesium-134, cesium-137
and iodine-131 were observed between theend of March 2011 and the beginning ofMay 2011 (Table V.34). These results were
evidence of radioactive fallout on French
territory from the accident at the Fukushima
nuclear plant. Also during this period, atemporary increase in the gross beta activity
was observed (Table V.35), related mainly
to the presence of artificial radionuclides in
the air following the Fukushima accident.
For more information
Chapter III – Fukushima accident

Fukushima accident

6

4

2

0
Jan. 10

Apr. 10

Measurement < DT

Jul. 10

Oct. 10Jan. 11

Apr. 11Significant measurement (> DT)

Figure V.82 - Time plot of the gross beta activity in atmospheric aerosol samples collectedin the environment of the Rhône valley NPPs (mBq/m3)
 able V.34 - Radionuclides measured in aerosols from the environment of the RhôneTvalley NPPs during the period of the accident at the Fukushima nuclear plantfrom March 22 to May 6, 2011 (mBq/m3)

Plant

Radionuclide

Mean activity (mBq/m3)

Bugey, Creys-Malville, Cruas,Saint-Alban
and Tricastin NPPs

Cesium-134

0.025 ± 0.005

Cesium-137

0.028 ± 0.005

Iodine-131

0.15 ± 0.02

 able V.35 - Gross beta activity in atmospheric aerosol samples collected in the environmentTof the Rhône valley NPPs (mBq/m3)

Plant
Bugey NPP

Radionuclide

Creys-Malville NPP
Cruas NPPSaint-Alban NPP
Tricastin NPP

Gross beta activity

Mean activity (mBq/m3)
0.38 ± 0.01
0.32 ± 0.01
0.57 ± 0.02*
0.40 ± 0.01
0.68 ± 0.02*
0.40 ± 0.01
0.62 ± 0.02*
0.37 ± 0.01
0.50 ± 0.02** Measurements made from March 22 to May 6, 2011 during the period of the accident at the Fukushima nuclear plant

IRSN – Report on the Radiological State of the Environment in France in 2010-2011165

Monitoring of Nuclear Fuel Cycle Facilities

The significant tritium activity levels observedin 2010 in the rainwater for all the NPPs
ranged between the decision thresholds and40 Bq/L (value measured at the Tricastin
NPP). These results can be viewed in thecontext of the time plots compiled by IRSN,
showing a decrease in measured activity
levels over the decades, which can be related
to the reduction of gaseous tritium
discharge from the Marcoule site. This trend
is illustrated in Figure V.83, which shows theannual means of the significant tritium
activity levels for all the NPPs located in the
Rhône valley.
The time plot of the annual tritium activity
measured in rainwater in the vicinity of the
Tricastin NPP (Figure V.84) shows quite highvariability between the minimum and maximum values. This variability can be
explained by the geographical proximity of
the Marcoule and Pierrelatte sites, to whichmust be added influencing environmental
factors such as wind speed and rainfall.

60

Bq/L

50
40
30
20
10
0
19
72
19
75
19
77
19
79
19
81
19
83
19
85
19
87
19
89
19
91
19
93
19
95
19
97
19
99
20
01
20
03
20
05
20
07
20
09

Rainwater

Significant measurement (> DT)
Figure V.83 - Time plot of past annual mean tritium activity measured by IRSN
in rainwater collected in the vicinity of the Rhône NPPs (Bq/L)
140

Bq/L

120
100
80
60

Gases sampled by bubblers
40

Tritium in form HTO (tritiated water vapor)could be detected at values close to thedecision thresholds in the immediate vicinity of the Cruas NPP (Figure V.85). The available results for the other Rhône NPPs
showed only decision thresholds.
The levels generally observed in the air in
France are from 0.01 to 0.05 Bq/m3 awayfrom any tritium emission source, andbetween 0.5 and a few Bq/m3 in the near-fieldenvironment of nuclear sites permitted todischarge tritium into the atmosphere.

20
0
1970

1975

Mean activity

1980

1985

1990

Maximum activity

1995

2000

2005

2010

2015

1
.-1
Jan

1
r.-1
Ma

1
y-1
Ma

Minimum activity

Figure V.84 - Historic variability of tritium activity in rainwater collected
at the Tricastin NPP (Bq/L)

Bq/m3
0.6
0.5
0.4
0.3
0.2
0.1
0

0
0
0
0
09
-10
.-1
.-1
r.-1
t.-1
c.Jul
Jun
Feb
Ap
De
Sep
Significant activity (> DT)
Decision threshold

10
v.No

Figure V.85 - Tritium activity measured in the air in the vicinity of the Cruas NPP (Bq/m3)

166

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Terrestrial compartment
Terrestrial flora
Cesium-137 was detected occasionally ingrass samples collected monthly within
4 km of the Creys-Malville and Cruas NPPs
(Table V.36). The mean specific activity levels of the significant measured results
varied between 1.3 ± 0.5 Bq/kg dry and4.2 ± 2 Bq/kg dry. These intervals of variation, close to the means calculated forthe results below the decision thresholds(between 0.5 and 1.3 Bq/kg dry), arewithin the range of values characteristicof the Chernobyl accident. Any impact on
the operation of these plants cannot be
detected.
Traces of iodine-131 were detected at the
beginning of April 2011 on grass samples
collected in the vicinity of the Creys-Malville and Saint-Alban NPPs. These activity
levels were related to fallout from the
Fukushima plant accident in Japan on
March 11, 2011.
For more information
Chapter III – Fukushima accident
Soil
In 2010, a soil sample was collected
5.5 km from the Saint-Alban NPP under
the prevailing winds. Cesium-137 activity
wa s d e t e c t e d i n t h i s s a m p l e a t

21 ± 2 Bq/kg dry. The majority of thisactivity can be explained by fallout frompast atmospheric nuclear weapons testing
and from the Chernobyl accident. The contribution to the activity attributable to discharge from the NPP cannot be quantified.
Farm produce and foodstuffs
Cereals
Gamma-emitting radionuclides likely
to be discharged by the PWR plants were
not detected in wheat samples collected
near the Creys-Malville, Bugey, SaintAlban and Cruas NPPs.
Milk
The radioactivity measured in milk produced in the vicinity of the NPPs in the
Rhône valley basin was due mainly topotassium-40, with mean activity levelsof 48.4 ± 1.3 Bq/L in cow’s milk and 57.9
± 2.9 Bq/L in goats' milk. No trace of artificial radioactivity attributable to discharge
from the NPPs (131I, 134Cs, 137Cs, 3H) could bemeasured by the measuring instruments
used.
A significant level of strontium-90 was
measured in goat’s milk produced in theregion of Tricastin. The activity, close to
the decision thresholds (0.056 ±0.011 Bq/L), can be attributed to past fallout from atmospheric nuclear weapons
testing in the 1960s.

Table V.36 - 137Cs activity measured in grass samples collected near the Rhône drainage basin NPPs (Bq/kg dry)

Creys-Malville NPPSaint-Alban NPP

Cruas NPPSaint-Pierrede-Boeuf

Meysse(500 munder theprimary
prevailingwind)Tourrettes(4 km
under thesecondaryprevailing winds)

0 significant
measurements out of15

0 significant
measurements
out of 14

1 significant
measurementout of 17

4 significant
measurements
out of 17///

4.2 ± 23.9 ± 0.7

< 0.5

< 1.2

< 1.3

< 1.3

< 1.3

Sampling
localities

Creys-Mépieu
(1.36 km under
the primaryprevailing winds)

Bouvesse-Quirieu(3.7 km, slightly
outside theinfluence of thesecondaryprevailing winds)

Pélussin

Number of significant
measurements out of thetotal number of measurements

2 significant
measurements
out of 18

0 significant
measurements
out of 18

Mean 137Cs activity –significant results *1.3 ± 0.5

Mean 137Cs activity –results below
the decision thresholds< 0.5* Excluding values attributable to the Fukushima accident

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

167

Monitoring of Nuclear Fuel Cycle Facilities

Fruit
Radionuclides discharged or likely to be discharged by the power plants (131I, 134Cs,
137Cs, 60Co, 3H, etc.) were analyzed in rhubarb,
strawberries, pears and peaches producednear the Bugey, Saint-Alban, Cruas andTricastin NPPs, respectively. The analysis
results showed activity levels below the decision thresholds of the instruments used. Only
tritium activity was measured in peaches
produced in the region of Tricastin, at 5.1 ±1.8 Bq/kg wet. Although low, this value ischaracteristic of an environment affected byanthropogenic activities.
Wine
No significant anthropogenic activity wasmeasured in red wine produced in theimmediate vicinity of the Saint-Alban and
Cruas NPPs. Only naturally occurring potassium-40 was measured, at a mean activity
concentration of 37.7 ± 2.7 Bq/L.

Continental aquaticcompartment
The Rhône rises on the southern slope of
the Saint-Gotthard massif in Switzerland,
feeds into Lake Geneva, exits from the lake at
the city of Geneva, then marks the FrenchSwiss border for a few kilometers. In France,
the radiological monitoring of the Rhône
begins at the Injoux-Génissiat hydroelectric
plant operated by the Compagnie Nationale
du Rhône (CNR). Most of the radioactivity
transported by the Rhône upstream of theborder is bound to suspended solids. Tritium
discharge by the Swiss watchmaking industry are responsible for remanent radioactivity
in the Rhône.
In France, the Rhône drainage basin has alarge number of nuclear facilities (4NPPs, Creys-Malville site, Marcoule site,
Pierrelatte industrial complex, etc.). Some ofits tributaries also have nuclear sites, including the Isère (FBFC Romans-sur-Isère) and the
Durance (CEA Cadarache). The tributaries of
the Rhône are major rivers and substantially
increase the volume of its water, generating aconsiderable dilution effect.
The Rhône is very different from the Loire interms of hydrodynamics. Its flow rate issignificantly higher and more regular. At
Beaucaire, about 60 km from the mouth of
the river, the mean annual flow rate of the
Rhône was 1790 m3/s in 2010, with a peak
instantaneous flow rate of 5950 m3/s in

168

December. Cycles are observed in themonthly flow rates calculated from the mean
daily flow rates obtained by height or flowrate measurements (Figure V.86). In
comparison with the Loire, the low amplitudeof the seasonal cycles is not reflected in theactivity levels measured downstream of the
NPPs. Any such influence would become
harder to detect as the high flow rate of the
Rhône dilutes discharge.

3,500

Flow rate (m3/s)

3,000
2,500
2,000
1,500
1,000
500
0
2003

2004

2005

2006

2007

2008

2009

2010

Figure V.86 - Mean monthly flow rate of the Rhône at Beaucaire (source: Banque Hydro) (m3/s)

Surface water
Routine monitoring of the Rhône NPPs by
IRSN started in 1972 (Bugey I-GCR) with the
installation of a river water sampler downstream of the site (Figure V.87). The activity
measured in 1973, about 32 Bq/L, decreased
rapidly to below 20 Bq/L in 1976. From the
1980s, all the NPPs have been monitored by
IRSN. The activity decreased by a further factor of 2 until 1998. The metrological performance showed its limitations in thesubsequent period to 2008, when the mean
tritium activity in the Rhône fell below
10 Bq/L. From 2008 the decision thresholds
were improved (5 Bq/L, then 1 Bq/L in2010) and the activity in the Rhône could
again be quantified.
Strontium-90 is measured periodically downstream of the Bugey NPP at activity levels of
about 0.004 Bq/L, close to the decisionthresholds. The measurement of strontium-90 downstream of the Bugey NPP

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
originated in the operation of the GCR system developed in the 1950s in France. However, the strontium-90 activity levels
measured here are characteristic of atmospheric fallout from nuclear weapons testing.
Ground water

Bq/L

35
30
25
20

The ground water circulating under the
Rhône valley NPPs and which is monitoredshows additional concentrations of tritium ataround 8 Bq/L, with a maximum activity of
14 Bq/L measured at the Tricastin NPP. The
mean tritium activity in the vicinity of each
NPP remained stable over time (Figure V.88).

15
10
5

19
73
19
75
19
77
19
79
19
81
19
83
19
85
19
87
19
89
19
91
19
93
19
95
19
97
19
99
20
01
20
03
20
05
20
07
20
09

0

Tricastin

CreysSaint-Alban

Bugey

Cruas

Figure V.87 - Significant (> DT) mean annual tritium activity measured in the water of the Rhône
downstream of the NPPs (Bq/L)

16

Bq/L

14
12
10
8
6
4
2
0
Oct.-09
Cruas

Jan.-10May-10Saint-Alban

Aug.-10
Tricastin

Nov.-10

Feb.-11

Jun.-11

Decision threshold

Figure V.88 - Mean tritium activity in ground water in the vicinity of the Rhône valley NPPs (Bq/L)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

169

Monitoring of Nuclear Fuel Cycle Facilities

Monitoring of
nuclear power plants on
the Channel and North
Sea coasts
There are four nuclear power plants along the
Channel - North Sea coast (Figure V.89),
located near Cherbourg (Flamanville NPP), in
Normandy (Penly and Paluel NPPs) andbetween Calais and Dunkirk (Gravelines NPP).

Gravelines
CalaisPas-de-Calais

Somme
Penly
AmiensPaluelSeine-Maritime

Flamanville

Le Havre

MancheCaen
Calvados

Orne

Nuclear power plants
Major urban centers

RiversDepartments

Figure V.89 - NPP locations on the Channel - North Sea coast

170

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Rouen

Oise

© EDF

V.4

Figure V.90 - Flamanville NPP

Flamanville NPP

2,174

1,228

79

664

2,454

Located on the west coast of the Cotentin
peninsular, 30 km southeast of Cherbourg,
the Flamanville NPP (Figure V.90) has two
1300 MW pressurized water reactors put
into service in 1985 and 1986, and a1650 MW EPR unit under construction since
2006.

14
EDF
IRSN
ASN

219
AtmosphericContinental aquatic
Marine aquatic
Terrestrial

Figure V.91 - Breakdown of the number of samples by data provider and by environment for the
Flamanville NPPIRSN – Report on the Radiological State of the Environment in France in 2010-2011

171

Monitoring of Nuclear Fuel Cycle Facilities

Paluel NPP

2,822

834

188 147

349

2,972

Located on the Channel coast 30 km west ofDieppe, the Paluel NPP has four 1300 MW
pressurized water reactors put into service in
1984, 1985 and 1986.

EDF
IRSN

AtmosphericContinental aquatic
Marine aquatic
Terrestrial

Figure V.92 - Breakdown of the number of samples by data provider and by environment for the
Paluel NPP

Penly NPP

2,672

860

194

170

174

2,994

Located on the Channel coast 11 km east ofDieppe, the Penly NPP has two 1300 MW
pressurized water reactors put into service in1990 and 1992.

EDF
IRSN

AtmosphericContinental aquatic
Marine aquatic
Terrestrial

Figure V.93 - Breakdown of the number of samples by data provider and by environment for the Penly
NPP

Gravelines NPP

703

53

3,028

296

464

2,828

Located on the North Sea coast between
Dunkirk and Calais, the Gravelines NPP has six
900 W pressurized water reactors put into
service in 1980, 1981, 1984, and 1985.

196
EDF
IRSN
ASN

AtmosphericContinental aquatic
Marine aquatic
Terrestrial

Figure V.94 - Breakdown of the number of samples by data provider and by environment for theGravelines NPP

172

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Atmospheric compartment

Activity (mBq/m3)
4

Atmospheric aerosols
Apart from the observations recorded during
the period of the Fukushima accident, monitoring of the beta activity index did notreveal any abnormal value (Figure V.95). The
gamma spectrometry measurements
showed that, apart from naturally occurring
radionuclides (7Be and 210Pb), no artificial
radionuclide could be measured in the environment above the decision thresholds ofthe instruments used.
Significant levels of iodine-131 wereobserved in the aerosols between the end of
March 2011 and the beginning of May 2011
(Table V.37). As was the case in the rest ofFrance, these results represented detection ofradioactive fallout from the accident at the
Fukushima nuclear plant. The increase in thebeta activity index between the end of March2011 and the end of April 2011 (Table V.38)
was due mainly to artificial radionuclides infallout from the Fukushima accident.
For more information
Chapter III – Fukushima accident

Fukushima accident

3

2

1

0
Jan.-10

Apr.-10

Measurement < DT

Jul.-10

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)

Figure V.95 - Time plot of the gross beta activity in atmospheric aerosol samples collectedin the environment of the Channel and North Sea NPPs (mBq/m3)
 able V.37 - Radionuclides measured in aerosols in the environments of the Channel and North Sea
T
NPPs during the period of the accident at the Fukushima nuclear plant from March 22 to May 6, 2011
(mBq/m3)

Plant

Radionuclide

Mean activity (mBq/m3)

Flamanville,
Gravelines
Paluel,and Penly NPPs

Cesium-134< 0.037

Cesium-137< 0.040

Iodine-131

0.085 ± 0.03

 able V.38 - Gross beta activity index in atmospheric aerosol samples collected in the environmentTof the Channel and North Sea NPPs (mBq/m3)

Plant

Radionuclide

Mean activity (mBq/m3)

Flamanville NPP

0.23 ± 0.01
0.56 ± 0.02*

Gravelines NPP

0.24 ± 0.01
0.47 ± 0.02*

Gross beta activity
Paluel NPP

0.24 ± 0.01
0.59 ± 0.02*

Penly NPP

0.25 ± 0.01
0.48 ± 0.02** Measurements made between March 22 and May 6, 2011 during the period of the nuclear accident
at the Fukushima nuclear power plant

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

173

Monitoring of Nuclear Fuel Cycle Facilities

Rainwater and gases collected bybubblers

Bq/L
98

The tritium detected in rainwater collectedin the vicinity of the NPPs on the Channel
and North Sea coasts was measured
periodically at values close to the decisionthresholds (Figure V.96).

7
6
5
4

No tritium activity was detected in the ambient air collected by bubblers in the environment of these NPPs.

Terrestrial compartment

3
2
1
0
.-09
Nov

Terrestrial flora

10.-10 ay-10
Jan.M
Mar

Gravelines

Apart from the observations recorded during the period of the Fukushima accident,
the results of grass analyses by gamma spectrometry remained below the decisionthresholds of the instruments used.
Following the accident at the Fukushima
nuclear plant, traces of iodine-131 weredetected in grass samples collected by theoperators of the Flamanville, Paluel and
Penly NPPs between the end of March andthe beginning of April 2011. In addition,
cesium-134 and -137 were measured in thevicinity of the Flamanville plant at levels
close to the decision thresholds of the
instruments used.
For more information
Chapter III – Fukushima accident
Soil
Cesium-137 was detected in all the soil samples collected in the vicinity of the Paluel,
Penly and Gravelines NPPs (Table V.39). The
main source of this activity was radioactive
fallout from atmospheric nuclear weapons
testing and the Chernobyl accident.
Table V.39 - Activity measured in soil (Bq/kg dry)

Penly

11
.-11 ay-11
Jan.M
Mar

11
Jul.-

Decision threshold

Figure V.96 - Tritium activity in rainwater collected in the vicinity of the Channel and North Sea
NPPs (Bq/L)

Farm produce and foodstuffs

produced near the Penly NPP, at activity levels close to values measured outside theinfluence of nuclear facilities (16 ± 4.9 Bq/L).

Cereals
Gamma-emitting radionuclides likely to bedischarged by the PWR plants were notdetected in the wheat samples collected near Vegetables
In 2010, lettuce produced in the vicinity of
NPPs.
the Paluel, Penly and Gravelines sites wasanalyzed for radioactivity. Leeks and potatoes were also collected in the areas affectedMilk
The naturally occurring radioactivity meas- by the Flamanville and Gravelines NPPs,
ured in cow’s milk was due mainly to potas- respectively. No artificial radionuclides
sium-40, with mean activity concentrations were detected in the vegetable samples colbetween 45.8 ± 1.7 and 54.3 ± 2.6 Bq/L, lected in the vicinity of the Flamanville,
depending on the geographical sector. These Paluel and Gravelines NPPs. Traces ofvalues are consistent with those measured cesium-137, close to the decision thresholds,
in milk collected in the territory as a whole. were measured in lettuce collected in the
The activity concentrations of artificial radio- vicinity of Penly at activity levels of 0.035 ±nuclides (131I, 134Cs, 137Cs, 3H) were below the 0.007 Bq/kg wet.
decision thresholds of the instruments used.
Only one significant carbon-14 measurement was obtained, in a sample of milkRadionuclide

Gravelines NPP

Paluel NPP

Penly NPP

Cs

3.29 ± 0.19

5.5 ± 0.5

6.8 ± 0.9

137

174

Paluel10.-10 ov.-10
Jul.N
Sept

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Aquatic compartment
18

Ground water
Flamanville NPP
Ground water at the Flamanville NPP showed
spot tritium activity levels between 6 and16 Bq/L and a median activity for all thesampling points of 6.9 Bq/L (Figure V.97).
Paluel NPP
Ground water circulation is linked with theparticularly high level of fracturing in the
coastal hanging valleys, where karst systems
develop preferentially. The influence of thetides on ground water levels inland is highlyvariable on the scale of the site. No significant activity was measured, other thangross beta activity, which can vary withground water salinity according to the
influence of the tides (Figure V.98), related
to 40K.
Penly NPP
Tritium traces in the unconfined groundwater under the Penly NPP, considered to behydraulically confined at its base, was about
15 Bq/L at the points “nappe N1” and “nappe
N2”, sampled by the operator.
At piezometer N1 (Figure V.99), there were
few traces of tritium apart from the period
between November 2010 and February
2011, during which tritium activity
increased to 94 Bq/L before decreasing tovalues below 30 Bq/L. The operator has
not identified the cause of this temporary rise in activity.

16
14
12
10
8
6
4
2
0
Nov.-09

Jan.-10 Mar.-10

Water tower

Borehole

May-10Jul.-10 Sept.-10 Nov.-10

La Robinerie

Pz 11

Pz 13

Jan.-11 Mar.-11 May-11
Pz 15

Pz 21

Pz 6

Figure V.97 - Tritium activity in ground water at and in the vicinity of the Flamanville
NPP (Bq/L)

1.6

Bq/L

1.4
1.2
1
0.8
0.6
0.4
0.2
0
Nov.-09

Jan.-10 Mar.-10 May-10

Ground water N1 Ground water N2

Jul.-10 Sept.-10 Nov.-10

Ground water N3

Jan.-11

Mar.-11 May-11

Ground water N4 Ground water N5

Figure V.98 - Gross beta activity in ground water on the site of the Paluel NPP (Bq/L)

120

Bq/L

100
80
60
40
20
0

No
v.0
De 9
c.09
Jan
.-1
Fe 0
br.
-1
Ma 0
r.1
Ap 0
r.10
Ma
y10
Jun
-1
0
Jul
.-1
Au 0
g.1
Se 0
pt
.-1
Oc 0
t.1
No 0
v.1
De 0
c.10
Jan
.-1
Fe 1
b.1
Ma 1
r.1
Ap 1
r.1
Ma 1
y11
Jun
-1
1

Measurements made on water samples collected from the outfalls and from the
Channel for these NPPs are given in Chapter IV – Marine and coastal environment.

Bq/L

Significant activity (> DT)

Decision threshold

Figure V.99 - Tritium activity in ground water at point N1 on the site of the Penly NPP (Bq/L)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

175Monitoring of Nuclear Fuel Cycle Facilities

Piezometer N2 (Figure V.100) showed mean
traces of tritium activity of 16 Bq/L, decreasing during the period studied.

35

Bq/L

30
25

Gravelines NPP
Two unconfined quaternary aquifers werelocated above a Flanders clay layer about
100 meters thick and highly impermeable.
This assembly is underlain by three deep
aquifers in carboniferous limestones, chalkand Ostricourt sands.

20
15
10
5

No
v.0
De 9
c.09
Jan
.-1
Fe 0
b.1
Ma 0
r.1
Ap 0
r.1
Ma 0
y10
Jun
-1
0
Jul
.-1
Au 0
g.1
Se 0
pt
.-1
Oc 0
t.1
No 0
v.1
De 0
c.10
Jan
.-1
Fe 1
b.1
Ma 1
r.1
Ap 1
r.1
Ma 1
y11
Jun
.-1
1

0

Tritium traces in the ground water wereobserved at seven of the eleven sampling
points. The mean activity observed for allthese points was 20 Bq/L. Point N5 showeda mean tritium activity level of about
20 Bq/L, disturbed between April and July2010 by an increase in tritium activity(Figure V.101).

Significant activity (> DT)

Decision threshold

Figure V.100 - Tritium activity in ground water at point N2 on the site of the Penly NPP (Bq/L)

120

Bq/L

100
80
60
40
20

No
v.0
De 9
c.09
Jan
.-1
Fe 0
br.
-1
0
Ma
r.10
Ap
r.10
Ma
y10
Jun
-1
0
Jul
.-1
0
Au
g.1
Se 0
pt
.-1
Oc 0
t.1
No 0
v.1
De 0
c.10
Jan
.-1
1
Fe
b.11
Ma
r.1
Ap 1
r.11
Ma
y11

0

Significant activity (> DT)
Figure V.101 - Tritium activity in ground water at point N5 on the site of the Gravelines NPP (Bq/L)

176

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Monitoringof the nuclear
power plant at
Nogent-sur-Seine

It is located on the right bank of the river,
120 km southeast of Paris. The NPP has two
1300 MW pressurized water reactors, putinto service in 1987 and 1988.

There is one nuclear power plant on the
Seine river, at Nogent-sur-Seine (Figures
V.102 and V.103).

Yonne

Seine-Saint-Denis
Paris
Marne

Val-de-Marne
Hautsde-Seine
Seine-et-Marne

EssonneMelun

Nogent-sur-Seine

La Seine

Nuclear power plants
Major urban centers
RiversDepartments

Yonne

Aube

Troyes© G. Baumont/IRSN

Figure V.102 - Location of the Nogent-sur-Seine NPP

Figure V.103 - Nogent-sur-Seine NPPIRSN – Report on the Radiological State of the Environment in France in 2010-2011

177

Monitoring of Nuclear Fuel Cycle Facilities

3,310

Atmospheric compartment

918

1,080

2,991

Atmospheric aerosols
The gamma spectrometry measurements
showed that, apart from naturally occurring radionuclides, no artificial radionuclide
was detected in the environment above thedecision thresholds of the measuring instruments used.
32

As was observed for the other NPPs, anincrease in the gross beta activity related
essentially to the fallout from the Fukushima
accident was observed between the end of
March 2011 and the end of April 2011 (Table
V.40 and Figure V.105).
For more information
Chapter III – Fukushima accident

EDF
IRSN
ASN

AtmosphericContinental aquatic
Terrestrial

Figure V.104 - Breakdown of the number of samples by data provider and by environment for theNogent-sur-Seine NPP able V.40 - Gross beta activity in atmospheric aerosol samples collected in the environmentTof the Nogent-sur-Seine NPP (mBq/m3)

Plant

Radionuclide

Mean activity (mBq/m3)

Nogent-sur-Seine NPP

Gross beta activity

0.31 ± 0.01
0.62 ± 0.02** Measurements made from March 22 to May 6, 2011 during the period of the Fukushima accident

Fukushima accident

2

1

0

Jan.-10

Apr.-10

Measurement < DT

Jul.-10

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)

Figure V.105 - Time plot of the gross beta activity in atmospheric aerosol samples collectedin the environment of the Nogent-sur-Seine NPP (mBq/m3)

178

Rainwater and gases collectedby bubblers
Rainwater collected in the field near the
NPP showed tritium activity levels close to
the decision thresholds, with a maximum
value between 2009 and 2010 of 4.8 Bq/L.
Air collected by bubbler for analysis of tritium in the form of water vapor did not contain any detectable significant activity in2010.

Activity (mBq/m3)
4

3

189

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Terrestrial compartment
Terrestrial flora
The grass samples collected monthly aroundthe Nogent-sur-Seine plant did not containany trace of artificial radioactivity attributable to the gaseous discharge from the facility.
Traces of iodine-131 and cesium-134 and-137 were measured at the beginning of April
2011. They can be attributed to the accident
on March 11, 2011 at the Fukushima nuclear
plant in Japan.
For more information
Chapter III – Fukushima accident

this point the Seine has a shallow gradientand forms many wide meanders. The Seine
has a relatively regular flow regime, a consequence of the oceanic climate of its
drainage basin. It is nevertheless subject tomajor floods that have necessitated major
control works in the upper part of its
course and of its tributaries. Its mean flowrate at Paris is about 328 m3/s, but canexceed 1600 m3/s in flood periods.

Farm produce and foodstuffs
Flow rate (m3/s)

Cereals
The gamma-emitting radionuclides likely
to be discharged by the PWR plants were notdetected in the wheat samples collectedaround the Nogent-sur-Seine NPP.

200
180
160
140

Milk
No trace of artificial radioactivity ( 131I,
134Cs, 137Cs, 3H, 90Sr) was measured in samples
of cow’s milk collected in the vicinity of theNogent-sur-Seine plant. Only naturally
occurring potassium-40 showed significant
activity levels, at 51.8 ± 1.9 Bq/L.
Vegetables
The radioactivity measured in vegetables wasdue to naturally occurring potassium-40; its
activity was 130 ± 17 Bq/kg wet in lettuceand 112 ± 15 Bq/kg wet in leeks collectedaround the Nogent-sur-Seine plant. Artificial
radionuclides (134Cs, 137Cs, 3H, etc.) were notdetected by the measuring instruments used.

120
100
80
60
40
20
0
2003

2004

2005

2006

2007

2008

2009

2010

2011

Figure V.106 - Mean monthly flow rate of the Seine at Pont-sur-Seine (source: Banque Hydro) (m3/s)

Continental aquaticcompartment
The source of the river Seine is at a heightof 446 meters on the Langres plateau in Burgundy. The Seine and its main tributary, theYonne, join at Montereau-Fault-Yonne. The
Yonne has a higher flow rate and a larger
drainage basin than the Seine: the mean flowrate of the Yonne is 93 m3/s, compared withbarely 80 m3/s for the Seine. The Nogent-surSeine NPP is located 44 km upstream of theconfluence with the Yonne, on the “Petite
Seine”, as the river is known between its
source and Montereau-Fault-Yonne. The flowrate of the river measured near the NPP at
Pont-sur-Seine is shown in Figure V.106. At

IRSN – Report on the Radiological State of the Environment in France in 2010-2011179Monitoring of Nuclear Fuel Cycle Facilities

m3

Surface water250

In 2010, no abnormal gross alpha or beta
activity was observed in surface water collected upstream and downstream of theNogent-sur-Seine NPP. Analyses performedon water samples collected from the Seine
downstream of the NPP detected tritium
activity at a mean value of about 50 Bq/L
(Figure V.108), and at low water (Figure
V.107) in June 2010 a maximum activity of
110 Bq/L, due to liquid effluent from the NPP.

200
150
100
50
0
Jan.

The tritium traces in the Seine water sampled downstream of the NPP are characteristic of the operation of the plant (Figure V.
109).
Sediments
Sediments were sampled in 2010 at the station downstream of the Nogent-sur-Seine
NPP, at mid-discharge. Gamma spectrometry
analyses detected cesium-137 at an activity of
4.6 ± 0.8 Bq/kg dry. The other gamma-emitting radionuclides potentially present inliquid effluent discharge from PWRs (54Mn,
58 Co, 60 Co, 110m Ag, 134 Cs, etc.) were notdetected.

Feb.

Mar.

Apr.

May

Jun.

Jul.

Aug.

Sept.

Oct.

Nov.

Dec.

QMM: Measured monthly flow
Qdm: Mean daily flow rate
Figure V.107 - Daily flow rate of the Seine at Pont-sur-Seine in 2010 (source: Banque Hydro) (m3)
Bq/L
120
100
80
60
40
20
0

09
c.De

0
.-1
Feb

0
r.-1
Ap

0
.-1
Jun

10
g.Au

0
t.-1
Oc

10
c.De

1
.-1
Feb

1
r.-1
Ap

Significant activity (> DT)

Figure V.108 - Tritium activity measured at the station downstream of the Nogent-sur-Seine NPP(Bq/L)

Bq/L
70
1987: second reactor put into service
60
1988: first reactor put into service
50
40
30
20
10
0
8
0
4
6
0
2
8
6
4
4
8
0
2
6
198 198 198 199 199 199 199 199 200 200 200 200 200 201

Significant activity (> DT)

Decision threshold

Figure V.109 - History of annual tritium activity measured downstream of theNogent-sur-Seine NPP (Bq/L)

180

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V.4
Monitoring of theBrennilis nuclear
power plant© EDF

The Brennilis nuclear site is located in western Brittany, about 60 km from Brest, in theMonts d'Arrée area (Figure V.110).

Figure V.111 - Brennilis NPPSaint-Brieuc

Brest
Brennilis

Côtes-d’Armor

Finistère

Quimper

MorbihanLorient

Brennilis NPP
Major urban centers
Departments

Figure V.110 - Location of the Brennilis NPP

Seine-Saint-Denis
Paris

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

181

Monitoring of Nuclear Fuel Cycle Facilities

1,150

The Brennilis reactor (Figure V.111), a 70
MWe industrial prototype of the heavy water
system, was put into service in 1967 andoperated jointly by EDF and the CEA until its
final shutdown in 1985, when reactor
dismantling operations started. At the endof October 1996, the Monts d’Arrée site
(SMA) became a storage facility forequipment from the former nuclear plant,
and in September 2000 EDF became the soleoperator.

Atmospheric compartment

794

933

EDF
IRSN

Significant levels of cesium-134, cesium-137
and iodine-131 were also observed at Brennilis between the end of March 2011 and the
beginning of May 2011 following the Fukushima accident (Table V.41). An increase in the
gross beta activity related to fallout from the
Fukushima accident was observed during thissame period (Table V.42).
For more information
Chapter III – Fukushima accident
Rainwater and gases collectedby bubblers
Tritium measured in rainwater collected in
the vicinity of the Brennilis NPP did notexceed the decision thresholds of the measuring instruments used. Moreover, no tritium
activity was detected in ambient air.

944

AtmosphericContinental aquatic
Terrestrial

Atmospheric aerosols
Apart from observations recorded during theperiod of the Fukushima accident, monitoring of the beta activity index did not show
any abnormal value (Figure V.113) and, apartfrom naturally occurring radionuclides (7Be,
210Pb), no other radionuclide was detectedby gamma spectrometry above the decisionthresholds of the instruments used.

67

Figure V.112 - Breakdown of the number of samples by data provider and by environment for the
Brennilis NPP

Activity (mBq/m3)
4
Fukushima accident

3

2

1

0

Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11

Measurement < DT
Significant measurement (> DT)
Figure V.113 - Time plot of the gross beta activity in atmospheric aerosol samples collectedin the environment of the Brennilis NPP (mBq/m3)
 able V.41 - Radionuclides measured in atmospheric aerosol samples collectedTin the environment of the Brennilis NPP and measured during the period of the Fukushima
accident from March 22 to May 6, 2011 (mBq/m3)

Plant

Brennilis NPPRadionuclide

Mean activity (mBq/m3)

Cesium-134

0.042 ± 0.010

Cesium-137

0.048 ± 0.008

Iodine-131

0.40 ± 0.09

 able V.42 - Gross beta activity of atmospheric aerosol samples collected in the environmentTof the Brennilis site (mBq/m3)

Plant

Radionuclide

Mean activity (mBq/m3)

Brennilis NPP

Gross beta activity

0.18 ± 0.01
0.51 ± 0.05** Measurements made from March 22 to May 6, 2011 during the period of the nuclear accident
at the Fukushima nuclear plant

182

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.4
Terrestrial compartment

Aquatic compartment

Terrestrial flora

The subsoil of the site consists of backfill,
alluvium, arenaceous granite, and weatheredand sound granite. The ground water under
the site circulates mainly in the arenaceous
rocks and the backfill, but also in the alluvium and the weathered granite.

Three significant cesium-137 values were
measured in grass samples collected in thevicinity of the Brennilis NPP, out of the eightmeasurements made in 2010 (threemonthly sampling at two monitoring
points). The significant specific activity
levels measured were 5.4 ± 1.1 Bq/kg dryin June 2010 and 13 ± 3 Bq/kg dry in September 2010 at 1.5 km from the plant under
the prevailing winds, and 4.3 ± 1.2 Bq/kg
dry at 4 km under the prevailing winds.
These results were similar to those obtained
away from the influence of atmospheric discharge, evidence that past discharge fromthe site had no influence on the analyzed
radionuclides.

No significant tritium activity was measured
between 2010 and 2011 in the surface wateror ground water analyzed.

Farm produce and foodstuffs
Cereals
Gamma-emitting radionuclides likely to bedischarged by the Brennilis nuclear plant
were not detected in the wheat samples collected in the vicinity of the plant.
Milk
The naturally occurring radioactivity measured in cow’s milk was due mainly to potassium-40, with a mean activity concentrationof 49.1 ± 3.3 Bq/L. The activity concentrations of artificial radionuclides likely to bedischarged by the Brennilis site and transferred into the milk (131I, 134Cs, 137Cs, 3H) were
below the decision thresholds.
Vegetables
In 2010, no artificial radionuclide was
detected in the cabbage sample analyzed by
gamma spectrometry.
Cider
The radioactivity measured in the cider produced in the neighbourhood of the Brennilis
plant was mainly due to naturally occurring
potassium-40, giving an activity of
36.4 ± 3.7 Bq/L. No artificial radionuclide
was detected.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

183

Monitoring of Nuclear Fuel Cycle Facilities

V.5 Monitoring ofindustries in theback end of thenuclear fuelcycle
Industry in the back end of the cycle
receives the fuel unloaded from reactors, maintains or dismantles nuclear
equipment, and treats liquid effluent
and solid waste.
The Areva site at La Hague carries out
the first step in recycling spent fuelfrom nuclear reactors. The site is adjacent to the CSM waste disposal facility
operated by ANDRA and located in the
Manche department. As environmental
radiological monitoring is common tothese two sites, it is described here in asingle section.

This section also gives the results ofthe monitoring of the Somanu nuclear
maintenance plant located at
Maubeuge. The monitoring results of
the Socatri plant located on the Tricastin industrial site are grouped withthose of the other facilities on the
Tricastin site operated by Areva (Section V.3). The monitoring results of
the Centraco plant located on the
Marcoule site are grouped with thoseof the CEA (Chapter VI).

La Hague site:
Areva and ANDRA facilities
For the purpose of environmental monitoring, the La Hague site is considered here to
be a unit formed by the Areva La Hague
plant and the ANDRA CSM waste disposal
facility.
The La Hague site is located in thenorthwest of the Cotentin peninsula, about
20 km west of Cherbourg and 6 km fromthe tip of Cap de La Hague. The site
occupies parts of four municipalities in the

LegendWater
Built-up areas andbusiness parks
Forest and farmland
Sand, gravel
Rock and scree

Figure V.114 - Location of the La Hague industrial site184

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Manche department (Figure V.114).
Inaugurated in 1962, initially to process spent fuel from the first graphitemoderated gas-cooled (GCR) plants,
the present Areva plant at La Hague
processes spent fuel from French pressurized water reactors (PWR) andfrom some foreign facilities.
Most of the activity in gaseous discharge
from the Areva La Hague plant consistsof noble gases (226,000 TBq in 2010,
48.2% of the discharge permit limit),
tritium (56.8 TBq in 2010, 37.9% of thedischarge permit limit), and carbon-14(16 TBq in 2010, 57% of the permit
limits).
The activity in liquid waste, discharged
into the sea, is predominantly due totritium (9,960 TBq in 2010, 53.8% of thepermit limit) and carbon-14 (7.34 TBq in2010). In this discharge, iodine and otherfission products (cesium, ru t h e nium-106, etc.) and activation products accounted for about 5 TBq in2010.

© Andra

V.5

Figure V.115 - La Hague industrial site with ANDRA CSM in the foreground

Inaugurated in 1969, the ANDRA waste disposal facility covers an area of 15 hectares(Figure V.115). It received its last packagei n 1 9 9 4 ( gi v i n g a t o t a l of n e a r ly
530,000 m3 of waste). After several yearsof work to complete the cap, the facility
entered the monitoring phase in 2003. The
radioactive discharge resulting from waterdraining over and under the facility structures is collected and channeled to theadjacent Areva plant for discharge into thesea (4.04 GBq of 3H discharged in 2010, 3.2%of the permit limit).

2,821

7

4,207

1,140

22,555

9,824

9,440

Andra
Areva
Acro*
IRSN
LDA Manche

8,449

3,017

AtmosphericContinental aquatic
Marine aquatic
Terrestrial

Figure V.116 - La Hague site: breakdown of the number of samples by data provider
and by environment* Additional fresh water and sea water samples were sent by ACRO to the RNM in 2010. The measurements could not be used in this report (communicated after July 2011) but can be consulted on the RNM
website (www.mesure-radioactivite.fr).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

185

Monitoring of Nuclear Fuel Cycle Facilities

Atmospheric compartment

Activity (mBq/m3)
1

Aerosols
Apart from the observations recorded
during the period of the Fukushima accident, no artificial radionuclide activity was
detected in the environment over the
2010-2011 period (Figure V.116 andFigure V.117).

0.75

0.5

0.25

As is the case for the majority of aerosol
samples collected from the environment,
significant cesium-134, cesium-137 andiodine-131 activity levels were observed in
the vicinity of the La Hague site between theend of March and the beginning of May, 2011
(Table V.43). They can be explained by thearrival of air masses contaminated by theaccident at the Fukushima nuclear power
plant. These air masses also caused anincrease in the gross beta activity over thesame period (Figure V.118).
For more information
Chapter III – Fukushima accident

0

Jan.-10

Jul.-10

Apr.-10

Measurement < DT

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)

Figure V.117 - Time plot of gross alpha activity in aerosols near the La Hague site (mBq/m3)

Activity (mBq/m3)
4

Fukushima accident

3

2

1

0
Jan.-10

Apr.-10

Jul.-10

Measurement < DT

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)

Figure V.118 - Time plot of gross beta activity in aerosols near the La Hague site (mBq/m3)

 able V.43 - Activity measured in aerosol samples collected in the environment of theT
La Hague site (mBq/m3)

Radionuclide typeRadionuclide

Mean activity (mBq/m)

Gross alpha activity

0.77 ± 0.002

Gross beta activity

0.34 ± 0.01
0.60 ± 0.03*

Cesium-134

0.045 ± 0.006*

Cesium-137

0.050 ± 0.007*

Iodine-131

0.077 ± 0.012*

Gross activity levels

Artificial
radionuclides* Measurements made during the period of the nuclear accident at the Fukushima nuclear power plant
between March 22 and May 6, 2011.

186

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.5
Atmospheric tritiumand carbon-14

Othergases(krypton-85, iodine-129, iodine-131)

Gaseous waste discharge is regulated by
the 2007 order for operation of the La Hague
nuclear site. The gaseous discharge is generated by the ventilation of the workshops
and the process apparatus. They undergo
various consecutive purification treatments
according to the physical-chemical nature of theelements.

Monitoring of gaseous iodine-129 and -131
did not reveal any significant releases ofiodine into the environment by the La Hague
facilities.

Most of the tritium is trapped in the formof tritiated water that is discharged into thesea as liquid effluent. A small fraction of thetritium is discharged in gaseous form. The
tritium levels in the atmosphere, measured
using bubblers , were not significant. The
mean decision threshold observed at
La Hague was between 0.60 and 0.78 Bq/m3.

In contrast, the krypton-85 discharged by
the same facilities during the reprocessingof spent fuel rods was detected regularly inthe atmosphere (Table V.44).

 able V.44 - Krypton-85 and iodine isotopes in gaseous form measured in the environment nearT
the La Hague site (Bq/m3)

Radionuclide type

Sampling of atmospheric carbon-14 in theenvironment using bubblers gave a mean
activity of about 0.05 Bq/m3 of air, measured
at five sampling stations located near the
Areva site (Figure V.119).

Artificial radionuclides ingaseous form

Radionuclide

Mean activity or
detection limit (Bq/m3)

Iodine-129< 0.009

Iodine-131< 0.001

Krypton-85

130 ± 4

In comparison, carbon-14 activity in the airin an area not affected by nuclear operations is about 0.03 Bq/m3. A study in which
IRSN took part (Fontugne et al.) attributed
part of the carbon-14 content in vegetation in the vicinity of the coast to degassing of 14CO2 from sea water contaminatedby the effluent from La Hague.

0.35

Bq/m3

0.30
0.25
0.20
0.15
0.10
0.05
0.00
09
v.No

0
.-1
Jan

0
-1
ar.
M

0
-1
ay
M

Significant activity (> DT)

10
l.Ju

0
.-1
pt
Se

10
v.No

1
.-1
Jan

1
-1
ar.
M

1
-1
ay
M

11
l.Ju

Decision threshold

Figure V.119 - Carbon-14 activity measured in air near the La Hague site (Bq/m3)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

187

Monitoring of Nuclear Fuel Cycle Facilities

Rainwater
The prevailing climate type on the Cotentin peninsula is oceanic (900 millimetersof rain in 2010, with an average of 150
rainy days). Rainwater is collected atvarious points near the La Hague site.
Weekly measurements are made on
the monthly mixed collection.

90

Bq/m3

80
70
60
50
40

Since 1975, IRSN has been measuring
the tritium activity in rainwater collected weekly at Gréville-Hague, east of
the La Hague site (Figure V.120). It isclear that tritium has no longer been
detected since the 1980s, despite theimprovement in the decision thresholdsof the measuring instruments, currently
about 5 Bq/L.

30
20
10
0

19
73
19
75
19
77
19
79
19
80
19
82
19
84
19
85
19
87
19
89
19
91
19
92
19
94
19
96
19
98
19
99
20
01
20
03
20
04
20
06
20
08
20
10

No activity of artificial radionuclides,
other than tritium, was measured above
the decision thresholds in the rainwater.
Near the site, a mean tritium activity of
11.5 Bq/L was observed, with a maximum
value of 52.5 Bq/L measured by Areva.

Significant activity (> DT)

Decision threshold

Figure V.120 - Tritium activity measuredi n rainwater near the La Hague site (Bq/m3)

Terrestrial compartment
Monitoring of the environment aroundthe La Hague nuclear site includes regular sampling of plants, soil, milk andvarious farm produce (vegetables, cider,meat, etc.) in the immediate vicinity ofthe site and in areas potentially affectedby discharge from nuclear facilities.
Flora
Samples of terrestrial plants (grass, pasture) are collected regularly at twelve
sampling stations around the site in six
municipalities (monthly or threemonthly sampling). In 2011, an additional spot sample was collected inanother municipality, Vauville, south of
the site following the Fukushima accident(Table V.45).
The majority of naturally occurring
radioactivity observed in plants was due
to potassium-40. Several artificial
radionuclides were measured in plants:
cesium-137, bound tritium, carbon-14
and iodine-129. The measured levels
varied considerably over time, and werecorrelated with the activity discharged by

the La Hague facilities and with theweather conditions at the time ofdischarge (Figure V.121).

12

Bq/kg dry

10

8

6

4

2

0
1/1/103/3/103/5/103/7/102/9/10200 m to the northeast (significant results > DT)
360 m to the southwest (significant results > DT)

2/11/10

2/1/11

4/3/11

4/5/11

360 m to the southwest (results < DT)
8.5 km to the southeast (results < DT)

Figure V.121 - Time-related change of iodine-129 activity measured in grass samples collected
at the most affected stations (Bq/kg dry)188

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.5
Table V.45 - Mean activity measured in grass samples collected around the La Hague site (Bq/kg dry)Jobourg
Radionuclide

DigullevilleWest siteboundary

Southwest
360 m

Southwest
1 km

Northwest
1.1 kmEast
110 m

Northeast
200 m

Northeast
1.1 km

K

610 ± 16644 ± 15491 ± 22826 ± 33759 ± 33734 ± 19755 ± 31129I

0.41 ± 0.06

2.34 ± 0.12

0.71 ± 0.13

< 0.28nm

2.01 ± 0.12

1.04 ± 0.15

Cs*

1.79 ± 0.16

< 0.6

< 0.42< 0.42< 3.1

0.59 ± 0.08

0.64 ± 0.14

Ru

<9

<9

<7

<7

< 50

<8

< 10

Other
gamma-emitting radionuclides (125Sb,
134Cs, 60Co)

< 2.4

< 2.5

< 1.9

< 1.8

< 13

< 2.3

< 2.6

OBT

8.85 ± 0.41

9.4 ± 0.41

4.46 ± 0.41

3.23 ± 0.34

nm

12.19 ± 0.5

8.3 ± 0.6

14C

137 ± 6349 ± 9120 ± 877 ± 7nm

268 ± 8205 ± 12Am

< 0.37< 0.41< 0.26< 0.23nm< 0.5< 0.41Pu< 0.08< 0.05< 0.021< 0.014nm< 0.06< 0.09Pu< 0.08< 0.035< 0.025< 0.019nm< 0.06< 0.06Cm< 0.046< 0.039< 0.014< 0.021nm< 0.027< 0.048

40

137

106

241

238

239+240

244

Omonville-la-Petite

HerquevilleBeaumontHague

Vauville

Biville

North
660 m

South
250 m

Southeast
1.1 kmSoutheast
6 km

Southeast
8.5 km

K

710 ± 18719 ± 18580 ± 26800 ± 90830 ± 32

129

I

1.79 ± 0.12

0.71 ± 0.07

0.45 ± 0.09

nm

< 0.32

Cs*

0.51 ± 0.07

0.82 ± 0.1

< 0.5

< 1.7

< 0.45

Ru

<8

<8

<9

nm

<7

Other
gamma-emitting
radionuclides(125Sb, 134Cs, 60Co)

< 2.2

< 2.1

< 2.3

< 1.3

<2

OBT

7.5 ± 0.34

6.95 ± 0.34

5.4 ± 0.5nm

2.72 ± 0.35

14C

271 ± 8207 ± 7139 ± 10nm

91 ± 9Am< 0.42< 0.42< 0.28nm< 0.42Pu< 0.027< 0.025< 0.02nm< 0.08Pu< 0.027< 0.025< 0.033nm< 0.08Cm< 0.039< 0.042< 0.023nm< 0.031

Radionuclide

40

137

106

241

238

239+240

244* Excluding values attributable to the Fukushima accident
nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

189

Monitoring of Nuclear Fuel Cycle Facilities

Other gamma-emitting artificial radionuclides (125Sb, 106Ru, 60Co, etc.) did not give significant measured activity levels. Similarly,
the activity levels of alpha-emitting artificial radionuclides (241Am, 238Pu, 239+240Pu,
244 Cm) remained below the decisionthresholds.

Omonville-la-Petite
400
Digulleville
300
200

Jobourg

100
0

In general, the highest activity levels ofartificial radionuclides were recorded at thestations located directly under the prevailingwinds, i.e. in samples collected southwest andnortheast of the La Hague site (Figures V.122
to V.124).
In the near environment, within a radius of
1 km around the site, the concentrations ofcarbon-14, bound tritium, and iodine-129
showed an impact on terrestrial plants
related to gaseous discharge from the
La Hague site. However, these concentrations decreased rapidly with distance fromthe site (Figure V.125).
Cesium-137 was only measured in a few
samples in the near environment, and not at
all at greater distances. The iodine-129
traces was also limited to an area close to
the site.
The activity measured at the most affected
station varied between 208 ± 25 and 710± 60 Bq/kg dry for carbon-14 and between
6 ± 1.2 and 42 ± 4.4 Bq/kg dry for boundtritium. These values were higher than thevalues generally observed in areas notaffected by discharge from a nuclear facility.
At 8.5 km southeast of the La Hague site,t he observed activity varied around
100 Bq/kg dry for carbon-14, and between
1.8 ± 0.7 and 5.3 ± 1 Bq/kg dry for boundtritium.
Traces of cesium-134 and -137 were measured at the beginning of April 2011 in fourmunicipalities. The traces were related tothe event at the Fukushima nuclear plant on
March 11, 2011. Cesium-134 activity measu re d ra n ge d f ro m 0.79 ± 0.34 to
1.7 ± 0.47 Bq/kg dry.
For more information
Chapter III – Fukushima accident

Le Bouchard

Beaumont-Hague

at 1.1 km(significant results > DT)
HerquevilleNear-field environment (< 660 m)(significant results > DT)

Figure V.122 - Distribution of mean carbon-14 activity measured in grass samples collected around the
La Hague site (Bq/kg dry)Omonville-la-Petite
2.5
Digulleville2
1.5
Jobourg

1
0.5
0

Le Bouchard

Beaumont-Hague

Herquevilleat 1.1 km(significant results > DT)
at 1.1 km (< DT)
Near-field environment (< 660 m)(significant results > DT)

Figure V.123 - Distribution of mean iodine-129 activity measured in grass samples collected around the
La Hague site (Bq/kg dry)Omonville-la-Petite
14
Digulleville
12
10
8
6

Jobourg4
2
0

Le Bouchard

Beaumont-Hague

Herquevilleat 1.1 km(significant results > DT)
Near-field environment (< 660 m)(significant results > DT)

Figure V.124 - Distribtion of mean organically bound tritium (OBT) activity measured in grasssamples collected around the La Hague site (Bq/kg dry)

190

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.5

14

Soil

129

C activity (Bq/kg dry)300

I and OBT activities (Bq/kg dry)7

Cesium-137 was measured in all the soil
samples collected every three months in
the immediate vicinity of the La Hague site
(less than 750 m from the site boundary) atmean activity levels between 6.3 ± 0.9 and44.3 ± 2.7 Bq/kg dry (Table V.46). The
majority of this activity can be explainedby fallout from past atmospheric nuclear
weapons testing and from the Chernobyl
accident. Although a contribution attributable to discharge from the La Hague site cannot be excluded, it cannot be quantified.

6

250

5

200

4
150
3
100
2
50

1

0

0

1 000

2 000

3 000

14

4 000

5 000

6 000

C (significant results > DT)

129

1 (< DT)

OBT (significant results > DT)

129

7 000

Activity of the other gamma-emitting
artificial radionuclides (125Sb, 134Cs, 60Co,
106Ru + 106Rh) remained below the decisionthresholds.

0
9 000

8 000

1 (significant results > DT)

Figure V.125 - Decrease of mean activity of carbon-14, iodine-129 and organically bound tritium
measured in grass samples collected along the southeast axis with distance from the La Hague site
(Bq/kg dry)
Table V.46 - Mean activity measured in soil samples in the immediate vicinity of the La Hague site (Bq/kg dry)Radionuclide

Omonville-la-Petite

Jobourg

Digulleville

HerquevilleK

994 ± 48670 ± 38902 ± 46822 ± 42847 ± 46644 ± 36845 ± 43Cs

7.6 ± 0.9

8.9 ± 1.1

6.3 ± 0.9

14.5 ± 1.3

18.3 ± 1.7

11.2 ± 1.2

44.3 ± 2.7

Cs

< 1.8

< 1.7

< 1.8

< 1.7

< 1.7

< 1.5

< 1.5

Ru

< 24

< 24

< 24

< 24

< 25

< 21

< 25

Sb

< 3.8

< 3.7

< 3.8

< 3.6

<4

< 3.2

<4

Co

< 1.5

< 1.2

< 1.4

< 1.5

< 1.5

< 1.2

< 1.2

40
137
134
106

125
60

Table V.47 - Mean activity measured in cow’s milk produced around the La Hague site (Bq/L)

Radionuclide

BeaumontHague

K

46.9 ± 0.7

I0.0188 ± 0.0017

Cs

Digulleville

Herqueville

Jobourg

51.8 ± 1
0.0165 ±0.0023< 0.0449.1 ± 1< 0.03949.9 ± 1
0.0048 ±0.001< 0.04

Ru

< 0.6

< 0.6

< 0.6

< 0.6

Other gammaemitting
radionuclides(125Sb, 134Cs, 60Co)< 0.18< 0.18< 0.18< 0.1890

Sr0.0646 ± 0.0028

HTO

<9

0.0491 ±0.0034
6 ± 0.80.0452 ±0.00125.5 ± 0.7

0.0577 ±0.0038<9C

19 ± 0.5

25.6 ± 0.8

27 ± 0.9

17.5 ± 0.8

40

129
137
106

14

< 0.018< 0.04

Farm produce and foodstuffs
Milk
Cow’s milk samples are collected regularly from four farms located near the siteat Herqueville, Beaumont-Hague, Digulleville and Jobourg. Of the artificial radionuclides likely to be discharged by the
La Hague site, traces of iodine-129, carbon-14 and tritium were observed in somesamples (Table V.47).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

191

Monitoring of Nuclear Fuel Cycle Facilities

In general, the highest activity was observedin milk collected in the municipalities
located directly under the prevailing winds(southwest and northeast sectors) (Figures
V.126 to V.129).
Iodine-129 was detected fairly regularly insamples collected at Herqueville andDiguelleville, and occasionally in samples
collected at the Beaumont-Hague station(two significant values measured between
January 2010 and May 2011).
The results for other gamma-emitting
radionuclides remained below the decisionthresholds for all the stations. The
strontium-90 concentrations measured inmilk were between 0.023 ± 0.016 and 0.14
± 0.023 Bq/L, within the range of values
measured in areas not affected by industrial
discharge.
In addition, traces of iodine-131, related
to the nuclear accident at the Fukushimaplant in Japan in March 2011, were detectedin milk collected at the beginning of April
2011 in farms in Herqueville, BeaumontHague and Jobourg (activity between 0.144± 0.049 and 0.23 ± 0.1 Bq/L). Cesium-137
was also measured in milk collected at the
beginning of May 2011 in Jobourg, with anactivity concentration of 0.059 ± 0.035 Bq/L.
For more information
Chapter III – Fukushima accident

Omonville-la-Petite
30
Digulleville
25
20
15
Jobourg

10
5
0

Le Bouchard

Beaumont-Hague

HerquevilleSignificant results (> DT)

Figure V.126 - Distribution of mean carbon-14 activity measured in milk samples from cows raised near
the La Hague site (Bq/L)
Omonville-la-Petite
0.02
Digulleville
0.015
0.01
Jobourg
0.005
0

Le Bouchard

Beaumont-Hague

HerquevilleSignificant results (> DT)< DT

Figure V.127- Distribution of mean iodine-129 activity measured in milk samples from cows raised near
the La Hague site (Bq/L)

JobourgOmonville-la-Petite
0.07
Digulleville
0.06
0.05
0.04
0.03
0.02
0.01
0

Le Bouchard

Beaumont-Hague

HerquevilleSignificant results (> DT)

Figure V.128 - Distribution of mean strontium-90 activity measured in milk samples from cows raisednear the La Hague site (Bq/L)

192

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.5

Omonville-la-Petite
10
Digulleville8
6
4

Jobourg

2
0

Le Bouchard

Beaumont-Hague

Significant results (> DT)< DT

Herqueville

Figure V.129 - Distribution of mean organically bound tritium (OBT) activity measured in milk samples
from cows raised near the La Hague site (Bq/L)

Meat
The radioactivity measured in farm meat
samples collected in the vicinity of the La
Hague nuclear site was due mainly to naturally occurring potassium-40 (Table V.48).
Rabbit raised in Herqueville showed tracesof strontium-90 (specific activity 0.087 ±
0.033 Bq/kg wet). It is difficult to distinguish between activity attributable to discharge from the La Hague nuclear facilities
and that due to past fallout from atmospheric nuclear weapons testing.

The specific activity of carbon-14 measured inbeef in 2010 (528.5 ± 2 Bq/kg C) is evidence of
livestock exhibiting added concentrations
linked with gaseous discharge from the
La Hague site: this value is nearly twice as highas the values customarily observed in areas
not affected by discharge from nuclear
facilities.
These analyses also revealed bound tritium,
at low activity levels, attributable to theoperation of the La Hague reprocessing plant.
Activity levels of other radionuclides
remained below the decision thresholds ofthe instruments used.

Table V.48 - Mean activity measured in meat produced near the La Hague site (Bq/kg wet)*Omonvillela-Petite

Herqueville

Jobourg

Slaughterhousenear the site

Slaughterhousenear the site

Poultry

RabbitMutton

Beef

Beef

K

128 ± 13126 ± 992 ± 9105 ± 13104 ± 12I

< 0.07< 0.07< 0.045

nm

nm

Radionuclide

40

129

Cs

< 0.11< 0.09< 0.07< 0.18< 0.15

Ru

< 1.8

< 1.6

< 1.2

< 1.5

< 2.1

Other gamma-emitting
radionuclides (125Sb, 134Cs, 60Co)< 0.46< 0.41< 0.32

< 0.8

< 0.9

OBT

nm

6.3 ± 0.5

0.81 ± 0.38

1.11 ± 0.36

0.344 ± 0.019

C

27 ± 549.7 ± 5

26 ± 886.47 ± 0.33
(528.5 ± 2 Bq/kg C)

32.53 ± 0.17
(243.8 ± 1.3 Bq/kg C)

Srnm

0.087 ± 0.033

nm< 0.035< 0.026

Am< 0.08< 0.08< 0.05

nm

nm

Pu

nm

< 0.005

nm

nm

nm

Pu

nm

< 0.008

nm

nm

nm

Cm

nm

< 0.0042

nm

nm

nm

137
106

14

90
241

238

239+240244

nm: not measured* unless otherwise indicated
IRSN – Report on the Radiological State of the Environment in France in 2010-2011

193

Monitoring of Nuclear Fuel Cycle Facilities

Cereals
Wheat samples were collected during
the annual harvest in Digulleville. Concentrations of the gamma-emitters, otherthan potassium-40, remained below thedecision thresholds.
Tritium, in a form bound to organic matter, was measured at a specific activity of
4.9 ± 0.25 Bq/kg dry, indicating a slight
impact on wheat by discharge from the
La Hague site.
Vegetables, mushrooms
and aromatic plants
Samples of terrestrial plants intended forhuman consumption (vegetables, mushrooms, aromatic plants) were collectedunder the primary prevailing winds in
Herqueville, Digulleville and Omonvillela-Petite (Table V.49).
Several artificial radionuclides attributable
to discharge from the La Hague site were
measured in plants: tritium, carbon-14, andiodine-129.

Potatoes grown in Herqueville showedstrontium-90 activity within the range ofvalues measured in areas not affected byindustrial discharge. This activity can be
attributed to past fallout from atmospheric nuclear weapons testing.
The cesium-137 measured in the mushrooms collected in Digulleville (activity
0.55 ± 0.07 Bq/kg wet) can be attributed to past fallout from the Chernobyl
accident. Activity of other radionuclides
remained below the decision thresholds.
Following the accident at the Fukushima
nuclear plant on March 11, 2011, traces ofcesium-134 and -137 were measured in
the thyme sample collected on April 20,
2011 in Herqueville, at a specific activityof 0.34 ± 0.16 and 0.44 ± 0.21 Bq/kg wet,respectively.
For more information
Chapter III – Fukushima accidentT able V.49 - Mean activity measured in terrestrial plants intended for human consumption produced near
the La Hague site (Bq/kg wet)

Digulleville

HerquevilleOmonville-la-Petite

Radionuclide
Mushroom

Leek

PotatoParsley

Thyme

CarrotCauliflower

K

82 ± 7139 ± 13169 ± 15255 ± 25

275 ± 27

119 ± 1181 ± 5I

0.053 ± 0.021< 0.037< 0.044< 0.090.39 ± 0.14

< 0.031< 0.018

Cs*

0.55 ± 0.07

< 0.042< 0.05< 0.140.44 ± 0.21

< 0.033< 0.018Ru< 0.39

< 0.8

< 0.8

< 2.1

< 2.9

< 0.6

< 0.32Other
gamma-emitting
radionuclides(125Sb, 134Cs*,
60Co)< 0.11< 0.21< 0.24< 0.54< 0.62< 0.16< 0.09OBT

0.68 ± 0.11

1.46 ± 0.16

0.75 ± 0.24

2.31 ± 0.32

3.8 ± 0.5

2.23 ± 0.21

1.22 ± 0.09C

9.4 ± 1.6

16.4 ± 2.2

34 ± 526.9 ± 4.7

45 ± 715.2 ± 2.2

9.7 ± 1.1

Sr

nm

nm

0.29 ± 0.11

nm

nm

nm

nm

Am

< 0.019< 0.033< 0.041< 0.09< 0.14< 0.028< 0.016

Pu

nm

nm

< 0.01

nm

nm

nm

nm

Pu

nm

nm

< 0.0048

nm

nm

nm

nm

Cm

nm

nm

< 0.009

nm

nm

nm

nm

40

129

137

106

14

90

241

238

239+240
244* Excluding significant results attributable to the Fukushima accident
nm: not measured

194

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.5
Cider
Analysis of cider collected at SaintGermain-des-Vaux did not detect any
artificial radionuclides: only naturally
occurring potassium-40 was measured,a t a n a c t i v i t y concentration of
44.2 ± 3.7 Bq/L.

Table V.50 - Mean activity measured in eggs and honey produced near the La Hague site
(Bq/kg wet)

Beaumont-Hague

Herqueville

Honey

Eggs

K

16.2 ± 4.3

51 ± 6I< 0.07< 0.047Cs< 0.12< 0.07

Ru

< 1.8

< 1.2

Other gamma-emitting radionuclides(125Sb, 134Cs, 60Co)< 0.52< 0.31OBT

4.2 ± 1.3

2.9 ± 0.6

C

102 ± 2235 ± 15Srnm0.27 ± 0.11

Am

< 0.08< 0.046Pu

nm< 0.013Pu

nm< 0.013Cm

nm< 0.011

Radionuclide
40

129

Other farm produce(eggs, honey)
In 2010, annual samples of eggs andhoney were collected in the immediate
vicinity of the La Hague nuclear plant, in
Herqueville and Beaumont-Hague(Table V.50).

137
106

14

The radioactivity measured in the honeyand eggs was mainly due to carbon-14
and potassium-40. Traces of bound tritium attributable to discharge from the
La Hague site were detected in the two
samples, and traces of strontium-90 in
the eggs collected in Herqueville.

90
241

238

239+240244

nm: not measured

Continental aquaticcompartment
Surface water
The general configuration of the relief of
the Cotentin isthmus and the narrownessof the peninsular leave space only forsmall coastal rivers flowing into the
Channel. These include the SainteHélène, Landes and Moulinets streams,
which are affected by the La Hague site.
They are used as historic reference sites
for radiological impact related to the
La Hague industrial site. Rainwater andsite drainage water that are not radioactive contamination risks are collected
and transferred to a storm water basin
located at the Areva facility, then discharged into the Sainte-Hélène stream.
The analyses performed on this water inthe vicinity of the La Hague site did notreveal americium-241, cobalt-60 or
plutonium-238, -239 or -240 at quantifiable levels. However, cesium-137,
radium-226 and the uranium isotopes
were detected occasionally.
Since 1996, IRSN has been collecting
surface water samples from the Landes
stream, northwest of the site. Thesesamples had added concentrations ofstrontium-90, an artificial radionuclide

produced in fission reactions, which
has a radioactive half-life of 28 years.
These activity levels can be related to thestrontium-90 contamination of theground water by waste stored on thesurface at the site in the 1980s(Figure V.130).

4

Bq/L

3

2

1

0
1995

1996

1998

2000

2002

2003

2005

2007

2009

2010

Significant activity (> DT)
Figure V.130 - Strontium-90 activity in water from the Landes stream (Bq/L)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

195Monitoring of Nuclear Fuel Cycle Facilities

Tritium remains in the vicinity of the
La Hague site. It is detected in water of all
the streams located in the immediate environment of the site, with maximum values
recorded in the Sainte-Hélène stream at
Digulleville (Figure V.131). This contamination is linked with the historic presence oftritium in ground water contaminated by adisposal incident that occurred at the
ANDRA facility in 1976. This contaminationis recorded in measurements made by IRSN
since 1973. The activity level started todecrease from the 1990s. Since then, themeasured tritium activity has been approximately 100 Bq/L.

100,000

Bq/L

10,000

1,000

100

10

0
1971 1973 1976 1979 1982 1984 1987 1990 1993 1995 1998 1993 2001 2004 2006 2009
Significant activity (> DT)

Decision threshold

Figure V.131 - Tritium activity in water from the Sainte-Hélène stream (Bq/L)

Sediments
Sediment samples were collected every threemonths from the Landes, Combes, SainteHélène, Grand-Bel and Moulinets streams(Table V.51). Monthly samples were collectedfrom the Sainte-Hélène stream at the “laBrasserie” site. Analyses revealed artificial
radionuclides ( 134Cs, 137Cs, 60Co, 238Pu,
239+240Pu) attributable to discharge from the
La Hague site (Table V.51).
Only cesium-137 was detected in all the sediment samples, at a mean specific activity
between 1.85 ± 0.24 and 50.4 ± 1.8 Bq/kg
dry in the Grand-Bel and Moulinets
streams. Large fluctuations were observed
during the year: the cesium-137 activity
measured in the Sainte-Hélène stream at the“le Pont-Durand” site ranged from 5.6 ± 0.6
to 70 ± 7 Bq/kg dry. Although cesium-137
concentrations due to discharge from thesite, mainly in the past, cannot be excluded,
they are also a result of past atmosphericfallout.
Cesium-134 was measured occasionally in
the Sainte-Hélène stream (maximum activity 35.9 ± 1.4 Bq/kg dry recorded at the “laBrasserie” site) and in the Grand-Bel stream(3 ± 0.8 Bq/kg dry). The sediments of theSainte-Hélène and Moulinets streams
showed occasional traces of cobalt-60 at
specific activity levels between 0.39 ± 0.12
and 2.05 ± 0.38 Bq/kg dry.

196

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Plutonium activity recorded in the SainteHélène and Moulinets streams demonstrate
a slight impact due to discharge from thesite. The 238Pu/239+240Pu activity ratio of about
0.5 is characteristic of civil spent fuel (theratio characteristic of atmospheric fallout
from nuclear weapons testing in the 1960s is
about 0.025). According to time plots of
239+240Pu concentrations, added concentrationlevels in sediments in the Landes stream
seems to date mainly from contamination
incidents during the period 2001-2003 (concentration time plots on page 118 of the
IRSN Report on the Radiological State of theEnvironment in France in 2009).
In addition, analysis of sediment samples
collected every three months from a stream
100 m from the Valognes railroad terminal,
used for shipments of nuclear material toand from the Areva site, did not detect any
radiological anomaly. Only cesium-137,
attributable to past atmospheric fallout, wasmeasured at a mean specific activity of 3.1 ±0.7 Bq/kg dry. The other artificial gammaemitting radionuclides analyzed (125Sb, 110mAg,
134Cs, 60Co, 54Mn, 106Ru) were not detected by
the measurement techniques used.

V.5
 able V.51 - Mean activity measured in sediment samples from the freshwater environment collected from the streams located nearT
the La Hague site (Bq/kg dry)LandesstreamCombesstreamSainte-Hélène stream

Grand-Bel
streamMoulinets
stream150 mdownstreamof theLa Hague site
Hameaudes Landes

500 m
downstreamof L’arsenal
near La Hague
site

200 m
downstream of
Le Pont
Durand near
the La Haguesite

1.1 kmdownstreamof
La Brasserie
near theLa Hague site

2.2 kmdownstream of
La Fosse nearthe
La Hague site

750 mdownstreamof theLa Hague site
Hameaules Clerges

Downstreamof theLa Haguesite

K

359 ± 14848 ± 29425 ± 12nm

900 ± 70890 ± 80941 ± 31Cs

6.9 ± 0.5

4.06 ± 0.23

10.24 ± 0.44

43.7 ± 1.5

13.9 ± 0.9

1.85 ± 0.24

50.4 ± 1.8

Cs< 0.38< 0.38< 0.310.58 ± 0.07

0.32 ± 0.07

0.45 ± 0.09

< 0.5

Co

< 0.3

< 0.390.44 ± 0.05

< 0.7

< 0.31< 0.6

0.7 ± 0.12

Other
gamma-emitting radionuclides (125Sb,
106Ru, etc.)

<5

<6

<1

<7

<6

<5

<9

Ra

nm

nm

nm

nm

65 ± 32

nm

nm

Pu

0.132 ± 0.035< 0.130.261 ± 0.032

nm< 0.14nm0.174 ± 0.042

Pu

1.86 ± 0.2

0.183 ± 0.048

0.365 ± 0.044

nm< 0.15nm0.35 ± 0.08

Radionuclide

40
137
134
60

226
238

239+240

nm: not measured

Flora
Aquatic phanerogam samples were collected
every three months from the Sainte-Hélène,
Combes and Landes streams (Table V.52).
Apart from the customary presence of potassium-40, the analyses detected artificial
radionuclides such as cesium-137,
iodine-129, americium-241, tritium, and,more occasionally, cobalt-60. The recorded
activity levels increased with the proximityof the sampling points to the La Hague
nuclear facilities, indicating the impact of theoperations on this site on the near-field continental aquatic environment.
The measured values varied considerably overtime. They varied in particular according to
the vegetative stage of the sampled phaneroga m s . S p e c i f i c a c t i v i t y b e t w e e n
7.4 ± 0.9 and 36.3 ± 4.4 Bq/kg dry for americium-241 and between 2.3 ± 0.6 and23.7 ± 2.7 Bq/kg dry for tritium wereobserved 150 m from the La Hague site in
the Landes stream. Similarly, spot measurements of cobalt-60 closest to the site in theLandes stream showed values varying
between 2.6 ± 0.6 and 6.4 ± 0.7 Bq/kg dry.

T able V.52 - Mean activity measured in aquatic phanerogam samples collected near
the La Hague site (Bq/kg dry)LandesstreamSainteHélène
streamCombesstream

150 m dowstreamof the La Haguesite

At thewaterfall

500 m downstreamof the La Hague
site

K

338 ± 15608 ± 25355 ± 17I

0.45 ± 0.1

11.4 ± 1

2.85 ± 0.3

Cs3.31 ± 0.28

45.6 ± 2.1< 0.42Co< 0.5

1.04 ± 0.16

< 0.46Am

9.4 ± 0.5

1.54 ± 0.25

< 0.32Other gamma-emitting
radionuclides(125Sb, 134Cs, 106Ru)

<9

< 11

<8

OBT

5.17 ± 0.34

14.5 ± 0.8

5.03 ± 0.38

Radionuclide

40

129
137
60
241

IRSN – Report on the Radiological State of the Environment in France in 2010-2011197

Monitoring of Nuclear Fuel Cycle Facilities

Bq/L

Ground water
Ground water is drained mainly towards theSainte-Hélène and Grand-Bel streams. It also
has outlets to the Combes, Landes and Moulinets streams. The La Hague ground water isanalyzed mainly by the nuclear operators(Areva and ANDRA) by means of more than
240 piezometers, half of which are checked
periodically.
The CSM waste disposal facility is monitored
using 60 piezometers, 48 of which are sampled
for radiological analyses. Significant tritium
activity levels can be measured, with a meanin 2010 of 4821 Bq/L and a maximum measured value of 168,000 Bq/L. These measurements at the CSM result from past pollutionof the ground water with tritium. The piezometer located within the nuclear facility is
subject to systematic monitoring to checkchanges in pollution and its lack of dosimetric impact outside the site.
Traces of artificial radionuclides such ascobalt-60 and cesium-137 are detected occasionally at 12 piezometers on the La Hague
site.
The majority of the ground watermeasurements made on the La Hague site
showed gross alpha and beta activity values
below the limits recommended by the WHO
for the consumption of potable water. Somep i e zo m e t e rs s t i l l s h o w a d d i t i o n a lconcentrations at values above these limits
due to past events. The mean tritium activity
measured in the ground water was 345 Bq/L,
with a maximum value of 19,000 Bq/L.
These occasional added concentrations
concerned a piezometer located at theedge of the CSM waste disposal facility site,near the ANDRA piezometer showing
past pollution (see above). IRSN monitors
some ground water outside the La Haguesite (Figures V.132 and V.133). The trend
shows decreasing tritium activity since theearly 2000s. However, the ground water
under and around the La Hague site is not
used for human consumption.

198

10,000
9,000
8,000
7,000
6,000
5,000
4,000
3,000
2,000
1,000
0
90
-19
May

8
199
Jul.-

95
93
-19
.-19
Jan.
Oct

Significant activity (> DT)

01
.-20
Apr

06
04
-20
.-20
Jan.
Oct

9
200
Jul.-

12
.-20
Apr

Decision threshold

Figure V.132 - Tritium activity in ground water samples collected at point Z702 locatedto the northwest of the CSM site (Bq/L)

Bq/L
60
50
40
30
20
10
0
90
-19
May

95
93
-19
.-19
Jan.
Oct

Significant activity (> DT)

8
199
Jul.-

01
.-20
Apr

06
04
-20
.-20
Jan.
Oct

9
200
Jul.-

12
.-20
Apr

Decision threshold

Figure V.133 - Tritium activity in ground water samples collected at point Z106 near the La Haguesite (Bq/L)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.5
SomanuThe Somanu site is a nuclear maintenanceplant located at Maubeuge in northern
France, near the Belgian border. Listed as abasic nuclear installation (INB), the site has
facilities for maintenance and repair of certain
nuclear components outside their original
installation site.
The equipment and tool maintenance carriedout at the Somanu plant can include disassembly, decontamination, machining, repair,reassembly, and testing. Somanu also organizes and manages transport on the public
highway for reception and shipment ofequipment belonging to nuclear operators.

Figure V.134 - Somanu plant workshop (“hot workshop”)
418

549

142

825

Atmospheric compartment
Aerosols
Monitoring of the gross beta activity in aerosol samples collected in the environment of
the Somanu site did not reveal any abnormal
value (Table V.53 and Figure V.136). The
gamma spectrometry analyses showed thatno artificial radionuclide was detected in theenvironment.

Areva
IRSN

AtmosphericContinental aquatic

Figure V.135 - Somanu plant: breakdown of the number of samples by data provider
and by environment

Table V.53 - Activity measured in atmospheric aerosol samples collected in the environment of theSomanu plant (mBq/m3)

Radionuclide typeRadionuclide

Activity (mBq/m3)

Gross activity levels

Beta activity

0.42 ± 0.02

Beryllium-7

2.37 ± 0.1

Lead-210

0.41 ± 0.03

Naturally occurring radionuclides

Activity (mBq/m3)
4

3

2

1

0

Jan.-10

Apr.-10

Measurement < DT

Jul.-10

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)

Figure V.136 - Time plot of gross beta activity in atmospheric aerosol samples collected
near the Somanu plant (mBq/m3)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

199

Monitoring of Nuclear Fuel Cycle Facilities

D13

1

4A

LA

LA

Longevillesur-la-Laines
HAUTE-MARNE

S

D24A

4

D

18

D2
4

D400

ES

B
D

La Ville-aux-Bois

Andra
Centre FA/MAde l'Aube

D2

Brienne-le-Château

D130A

D102
D102

Morvilliers

D9

60

D1
1B

02

102

D

96
02

D1

02

B

Ville-sur-Terre

0

D46A

4
D7

D443

10

D2

02
D1

1
D2

L'AUBE

Lac
Amance

D11D
D11C

D11

4
D7

Dienville

D2

D1
1

D46B

D18

D10

2

D18

Meadow
ForestFarmMine, dump and work site
Water

Municipality
Main roads
Industrial park
Built-up area
02

4 Kilometers©IFEN - CORINE land cover 2000®

Figure V.137 - Geographic locations of the CSFMA and CSFTA waste disposal facilities

200

13
D1

Legends
Department

Monitoring of surface water and groundwater did not reveal evidence of addedconcentrations due to the operations on
the Somanu industrial site.

Soulaines-d'Huys
7
D4

Andra
Centre TFA
de Morvilliers
A

D1

Chausmesnil

D46

The gross beta activity varied between thedecision threshold (0.03 Bq /L) a n d0.27 Bq/L. As in the case of the waterfrom La Flamenne, the gross alpha activity
measurements were generally below or close
to the decision threshold (0.04 Bq/L). Only
one spot measurement in June 2011 showed
activity greater than 0.1 Bq /L(0.27 ± 0.06 Bq/L).

2

D18

24

D69
D6
D6

D3

Measurements of tritium in this water were
all below the decision threshold (4 Bq/L).

IN

Crespy-le-Neuf
C

AUBE
30

LA

D155

Ground water
D1

Louze
LA

96

D3

Epothémont

D124

2

95

Vallentigny

9

The ground water is subject to regular monitoring by means of several piezometers atseveral points on the Somanu site.

74

D1

INE

D1

B

4

D2

80

82

Hampigny

29

D1

D1

D

80

Ceffonds

D1

180

D1

73

E

D62

D38

D193

D6

It should be noted that there are no artificialalpha emitters in the equipment received formaintenance in the plant.

D1

D173

D62

D2

The gross alpha activity measurements weregenerally below or close to the decisionthreshold (0.04 Bq/L). Only two analyses (0.18± 0.07 Bq/L on September 1, 2010 and 0.19
± 0.07 Bq/L on June 6, 2010) showed activity levels above the reference value recommended by the French public health code forwater intended for human consumption(gross alpha activity 0.1 Bq/L).

As the monitoring system of the CSM iscombined with that of the Areva plant at
La Hague, the results of the CSM monitoring
are given in the section on the monitoringof the La Hague site (Section V.5).

IRThe gross beta activity varied between 0.12
and 0.6 Bq/L. These values are below the reference value recommended by the French
public health code for water intended forhuman consumption (gross beta activity
1 Bq/L).

VO

The measurements of tritium in water fromthis stream were all below the decisionthreshold (4 Bq/L).

For the disposal of low- and intermediatelevel short-lived radioactive waste, theNational Radioactive Waste Management
Agency (ANDRA) first operated the CSM
waste disposal facility, now closed and in themonitoring phase. ANDRA now operates thelow- and intermediate-level short-lived
radioactive waste disposal facility (CSFMA)
and the very-low-level waste disposal
facility (CSTFA), both located about
175 km east of Paris. These two “surface
disposal” facilities are sited at Soulaines andMorvilliers in the Aube department(Figure V.137).

These disposal sites are subject to the regulations applicable to basic nuclear installations(INB) (CSM and CSFMA), or those applicable
to regulated facilities (ICPE) (CSTFA), which
require the operator to implement environmental monitoring including radiological andchemical measurements on rainwater, surface
water (streams), ground water, and ambient
air. After the operation (conditioning and storage) phase, the regulations stipulate that
ANDRA must continue to monitor the site
and the environment for several decades tomake sure that the disposal facility has no healthimpact on persons or its environment.

LA

Water samples are collected every monthfrom the La Flamenne stream at mid-discharge.

D2

Surface water

V.6 Monitoring of
waste
disposalfacilities

D129

Continental aquaticcompartment

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.6
CSFMA waste
disposal facility
and CSTFA waste
disposal facility

Most LILW-SL waste is generated bymaintenance (clothing, tools, filters, etc.)
and operation of nuclear facilities,
research centers and medical centers.
LILW-SL waste is managed by the
CSFMA in solid form. Some waste may
be compacted on site in the ANDRA
facilities to reduce its volume. For disposal, the waste is placed in concreteor metal containers, and mixed with
an embedding material (concrete, for© Andra

The CSFMA waste disposal facility has
been used since 1992 for surface disposal of low- and intermediate-level
short-lived radioactive waste (LILW-SL).
The facility is situated in three municipalities: Soulaines-Dhuys, Épothémont
and La-Ville-aux-Bois.

example). The waste is stored on thesurface in reinforced concrete structures. When the structures are full,they are closed by a concrete slab
sealed with an impermeable coating(Figure V. 138).

Figure V.138 - CSFMA waste disposal facility at Soulaines
843

Andra
IRSN

4,985

2,499

299

3,030

AtmosphericContinental aquatic

Terrestrial
Figure V.139 - ANDRA – CSFMA site: breakdown of the number of samples by data provider
and by compartment

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

201

Monitoring of Nuclear Fuel Cycle Facilities

Located a few kilometers from the CSFMA,
the CSTFA waste disposal facility has
been used since 2003 for the surface disposal of very-low-level waste. The facility
is located in Morvilliers and La Chaise.

© Andra

The waste accepted by the CSTFA comesfrom French nuclear facilities, laboratories
and research centers, mostly from dismantling operations. Other waste is received fromthe chemicals and metallurgical industries
and from cleanup of polluted sites.

The levels of radioactivity of waste categorized as vert low-level waste (VLLW) are very
close to the level of naturally occurring radioactivity. This waste is conditioned in drums
or big bags, then stacked in disposal caverns excavated in a clay layer (Figure V.140).
When the maximum disposal height isreached, the cavern is capped with compacted clayey backfill to restore its original
impermeability.

Figure V.140 - CSTFA waste disposal facility at Morvilliers
193

Andra

10

183

AtmosphericContinental aquatic

Figure V.139 - ANDRA – CSFTA site: breakdown of the number of samples by data provider
and by compartment

202

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.6
Atmospheric compartment

Dhuys and La Ville-aux-Bois (Table V.54
and Figure V.142).

Atmospheric aerosols
Additional measurements made onthese samples confirmed the absence ofartificial radionuclides in the environment. The investigations were able toexplain these particular values by ameasurement incident.

In the environment of the CSFMA andCSFTA sites, the atmospheric aerosol
monitoring showed no impact of site
operation. Just a few unusual gross alphaactivity values were measured simultaneously at the two monitoring points
located at the CSFMA, in Soulaines-

Table V.54 - Abnormally high gross alpha activity levels at the CSFMA waste disposal facility (mBq/m3)

Location

Gross alpha activity (mBq/m3)

Sampling period

CSFMA(Soulaines-Dhuys)
CSFMA(La Ville-aux-Bois)

0.52 ± 0.07
March 16-17, 2010

CSFMA
(Soulaines-Dhuys)
CSFMA(La Ville-aux-Bois)
CSFMA(Soulaines-Dhuys)
CSFMA(La Ville-aux-Bois)

0.47 ± 0.07
0.86 ± 0.09
March 4-7, 20110.79 ± 0.08
0.67 ± 0.07
April 22-26, 20110.72 ± 0.08

Activity (mBq/m3)
1

0.75

0.5

0.25

0
Jan.-10

Apr.-10

Measurement < DT

Jul.-10oct.-10

Apr.-11Jan.-11Significant measurement (> DT)F igure V.142 - Time plot of the gross alpha activity of aerosols over the ANDRACSFMA and CSFTA waste disposal facilities (mBq/m3)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

203

Monitoring of Nuclear Fuel Cycle Facilities

No artificial radionuclide was detected in
the environment of the disposal facilities.

Table V.55 - Activity measured in aerosols in the environment of the ANDRA CSFMA and CSFTA waste
disposal facilities (mBq/m3)

During the period of fallout in France fromthe Fukushima accident, significant activity
levels of cesium-134, cesium-137 andiodine-131 were observed between the endof March and the beginning of May 2011
(Table V.55, Figure V.143).
For more information
Chapter III – Fukushima accident

Radionuclide typeartificial radionuclides

Radionuclide

Mean activity (mBq/m3)

Cesium-134

0.008 ± 0.002*

Cesium-137

0.007 ± 0.002*

Iodine-131

0.013 ± 0.003*

Gases (Iodine-125, -129 and -131)
Activity (mBq/m3)

The presence of iodine-125, -129 and -131
in gas form was also checked in air samples
collected in cartridges. This monitoring did
not reveal evidence of significant releasesof these radionuclides into the environment. However, iodine-131 was measured
during the period of the accident at the Fukushima nuclear plant (Table V.56).

4

Rainwater1

Two collectors installed on the CSFMA site,in Soulaines-Dhuys and La Ville-aux-Bois, areused to collect rainwater. Weekly samples
are taken.
The results of the gross alpha, gross beta
and tritium measurements of this water
showed no impact from the site operations.
T h e o n ly o u t l i e rs w e re a n a ly s e sperformed on the samples collected at thetwo stations from April 7 to 14, 2011 (0.25
and 0.29 Bq/L), which were ten times
higher than the values generally observed.
These results were linked with low rainfall
during this period and with the presence ofsuspended solids of diverse origins(atmospheric dust , p o l l e n , e t c . ) .
Ad d i t i o n a l a n a ly s e s (gamma
spectrometry) performed on these raw(unfiltered) samples showed no evidenceof artificial radionuclides.

204

3

2

0
Jan.-10

Apr.-10

Jul.-10

Measurement < DT

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)

Figure V.143 - Time plot of the gross beta activity of aerosols near the ANDRACSFMA and CSFTA waste disposal facilities (mBq/m3)
Table V.56 - Gaseous iodine isotopes measured in the environment of the CSFMAand CSTFA sites (mBq/m3)

Radionuclide typeartificial radionuclides ingaseous form

Radionuclide

Mean activity or decisionthreshold (mBq/m3)

Iodine-125< 0.040

Iodine-129< 0.068

Iodine-131< 0.087
0.063 ± 0.01** Measurements made during the period of the nuclear accident at the Fukushima nuclear power plant
between March 22 and May 6, 2011.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

V.6
Terrestrial compartment
The immediate environment of the CSFMAand CSFTA disposal facilities is subject toregular monitoring by sampling of grass, milk,
cereals and mushrooms.
Terrestrial floraMonthly grass samples are collected in threemunicipalities located in the immediateproximity of the radioactive waste disposal

facilities (Table V.57). These are supplemented
by three-monthly sampling at two othersampling points.

The low activity of bound tritium observed
was close to values that can be observed customarily in areas not affected by discharge
from nuclear facilities.

In normal situations, only three samples gavesignificant results for cesium-137, out of the
53 analyses performed. These values werestill close to the decision thresholds of the
instruments used, and could be attributed topast fallout from the Chernobyl accident in
1986.

Table V.57 - Mean activity measured in grass samples collected in the immediate vicinity of the waste disposal facilities and the railroad terminal (Bq/kg dry)*

Soulaines-Dhuys
Monitoring of the CSFMA
site at Soulaines
Sampling on site

Radionuclide

La Ville-aux-Bois
Monitoring of the CSFMA site
at Soulaines

K

760 ± 70269 ± 18228 ± 21126 ± 23258 ± 18

Cs**

< 1.3

< 1.1

1.14 ± 0.16

< 0.9

1.05 ± 0.14

Cs**

<1

< 0.9

< 0.9

< 0.8

< 0.9

Co

< 1.4

< 1.2

< 1.2

< 1.1

< 1.2

OBT

2.3 ± 1.2

3.3 ± 1.3nm

nm

3.5 ± 1.1

C (Bq/kg C)

280 ± 90260 ± 100nm

nm

200 ± 30

40
137
134

60

14

Brienne-le-Château
Monitoring of the railroad terminal* Unless otherwise indicated** Excluding values attributable to the Fukushima accident
nm: not measured

The carbon-14 activity measured corresponded to the activity levels normallyobserved away from any nuclear facility.

© E. Gaffard/Andra

Some samples collected on April 6, 2011
showed traces of cesium-134 and -137. The
activity ratio of the cesium isotopes measured in grass samples, close to 1, was representative of the atmospheric fallout related
to the accident at the Fukushima nuclear
plant.
For more information
Chapter III – Fukushima accident

Figure V.144 - Oven drying of a grass sample

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

205

Monitoring of Nuclear Fuel Cycle Facilities

Soil

Farm produce and foodstuffs

Analysis of annual soil samples collected at
the low- and intermediate-level waste disposal facility did not detect any radiological anomaly related to the CSFMA site (Table
V.58). The cesium-137 measured can be
attributed to past fallout from the Chernobyl
accident. Measured uranium-234 and -238
activity levels were compatible with thenaturally occurring isotopes.

Milk
The radioactivity measured in cow’s milk
samples collected every three months fromfarms located in La Ville-aux-Bois andLongeville-sur-la-Laines was mainly due ton a t u ra l ly o cc u r ri n g p o t a s s i u m - 4 0 ,with a mean activity concentration of
53.7 ± 2.1 Bq/L.

Table V.58 - Mean activity measured in soil
samples collected at the CSFMA waste disposal
facility (Bq/kg dry)

Soulaines-Dhuys
Monitoring of the
CSFMA site atSoulaines
Radionuclide

Sampling on siteK

330 ± 50410 ± 60Cs

6.3 ± 0.9

3.9 ± 0.640137

No artificial radionuclide activity could bemeasured above the decision thresholds
associated with the measurement techniques
used.

Co

< 0.42

< 0.5

Am

< 1.3

< 0.8

Pu

< 1.4

< 0.9

Pu

< 2.4

< 1.2

Pu

<3

< 1.5

137

U

6.6 ± 0.9

6.2 ± 0.9134U

6.5 ± 0.9

7.3 ± 1

60

238

239

240

234

238

ActivityK

97 ± 17Cs

0.54 ± 0.1

Cs< 0.04160

Co< 0.06

HTO

< 2.5

OBT

0.06 ± 0.06

C (Bq/kg C)

270 ± 90

40
137
134

14

The carbon-14 activity was close, allowing for
uncertainty, to the background (about
235 Bq/kg carbon).

< 0.6

241

Radionuclide

The low levels of tritium (free and bound)observed conform to the background levelmeasured in France.

< 0.3560

T able V.60 - Activity measured inmushrooms collected in
La Ville-aux-Bois (Bq/kg wet)*

Cereals
No radiological anomaly was observed inwheat and maize samples collected in La
Ville-aux-Bois (Table V.59).

Cs

134

Mushrooms
The results of radiological analyses performedon the mushroom sample collected in La
Ville-aux-Bois did not show any anomaly due
to the operations on the ANDRA sites (Table
V.60). They corresponded to the values normally observed in France away from theinfluence of any nuclear facility.

* Unless otherwise indicatedT able V.59 - Activity measured in cereals harvested in La Ville-aux-Bois in 2010 (Bq/kg dry)*Radionuclide

Wheat

Maize

K

160 ± 50111 ± 16

Cs

< 0.7

< 0.08Cs< 0.6< 0.08

Co

< 0.7

< 0.1

HTO
(Bq/kg wet)nm

0.6 ± 0.6OBT

2.4 ± 1.3

2.2 ± 1.1

C (Bq/kg C)

200 ± 80260 ± 70

40

14

© P. Bourguignon/Andra* Unless otherwise indicated
nm: not measured

Figure V.145 - Collection of a milk sample

206

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V.6
Continental aquaticcompartment
Surface water
Water collected at the CSFMA disposal facility is subject to checks before it is channeled to a specific outlet. A storm waterbasin collects all the rainwater of the site.
After checking, this water is discharged into
the Les Noues d’Amance stream. The sampling frequency is weekly for the point
located in the stream immediately downstream of the site, and monthly at the otherpoints located upstream or further downstream. The results of the gross alpha, grossbeta and tritium measurements taken on
this water showed no impact due to theoperations of the site. Only traces of naturally
occurring uranium-234 and -238 wereobserved occasionally in the samples collected in La Ville-aux-Bois.
Ground water

Overall, examination of the gross alpha, grossbeta and tritium measurements did not show
any radiological anomaly linked with theindustrial operations on these sites.
Aquatic fauna
No artificial radionuclide activity was
detected in the fish sample caught in La Villeaux-Bois (Table V.61).

T able V.61 - Activity measured infish caught in La Ville-aux-Bois (Bq/kgwet)

Radionuclide

ActivityK

18 ± 6Cs< 0.027

40

137

Cs

< 0.023

Co< 0.033

Am< 0.0036

Pu< 0.0042

Pu< 0.01Pu< 0.015

U< 0.008U< 0.008

134

60

241

The environmental monitoring of the waterof these sites also covers the ground water.
The geological environment below anddownstream of the CSFMA consists of a layerof sand containing the unconfined groundwater and a clay layer about 25 meters thickprotecting the deeper ground wateraquifers.

238

239

240

234

238

The radiological monitoring of the groundwater at these facilities is accomplishedusing more than 30 piezometers installedon and near the sites, in Soulaines-Dhuys,
La Ville-aux-Bois, Épothémont, Morvilliers,
La Chaise and Brienne-le-Château. The sampling frequency is either monthly (for the
samples collected near the disposal structures), or three-monthly for samples collected further away and consequently lessexposed to any ground water contaminationfrom operations on the sites.

Continental aquatic flora
In 2010, no artificial radionuclide activity
attributable to operations at the ANDRA
waste disposal facilities was detected in theaquatic renunculus samples collected
monthly from the Les Noues d’Amancestream (Table V.62).
The detection of cesium-137 (main source:
Chernobyl accident) and isotopes -234 and-238 (naturally occurring) of uranium in
November 2010 was probably related toresuspension of ground dust.

T able V.62 - Activity measured inaquatic renunculus samples collectedin the Noues d’Amance stream (Bq/kg dry)Radionuclide

June
2010

November
2010

K

630 ± 120500 ± 140

Cs

< 0.45

1.13 ± 0.45

Cs

< 0.4

< 0.41

Co

< 0.6

< 0.5

Am

< 0.15< 0.32Pu< 0.18nm

Pu< 0.22< 0.33Pu< 0.29< 0.38U< 0.6

3.9 ± 1.6

U

< 0.484 ± 1.2

40

137

134

60

241

238

239

240

234

238

nm: not measured

The tritium measurements were below thedecision thresholds of the instruments used.
Only twelve spot measurements of grossalpha activity gave activity levels between
0.15 and 0.33 Bq /L in Morvilliers, andbetween 0.12 and 0.14 Bq/L in Soulaines,
above the reference value recommended by
the French public health code for water
intended for human consumption (0.1 Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

207

Monitoring of Nuclear Fuel Cycle Facilities

Sediments
Sediment samples are collected regularly atfour sampling stations near the CSFMA and
CFTFA disposal facilities: in a small pond
located between the CSTFA storm waterbasin and the Loriguette brook, in the Saint
Victor brook, in the Noues d’Amance stream,and in the Voire river (monthly, threemonthly, or six-monthly sampling). Samples
are also collected from two ditches near therailroad terminal at Brienne-le-Château
(Table V.63).
Cesium-137 was measured in all the sediment samples: it can be attributed to past
fallout from atmospheric nuclear weapons
testing and from the Chernobyl accident.

Four significant cesium-134 values, attributable to fallout in France from the Fukushima
accident, were measured in April and May
2011 in sediment samples collected in Morvilliers, Soulaines-Dhuys, and La Ville-auxBois, at low specific activity levels between
1.1 ± 0.37 and 1.6 ± 0.6 Bq/kg dry.
Analysis of sediment samples collected froma ditch close to the railroad terminal at
Brienne-le-Château revealed artificial
cobalt-60, related to present or past operations at the terminal (one significant value of
2.2 ± 0.7 Bq/kg dry, out of the three measurements taken).
Other artificial radionucleides investigatedwere not detected by the measuring
instruments used.

The samples contained similar activites ofuranium isotopes 234 and 238, between 4.46
± 0.34 and 8.2 ± 0.9 Bq/kg dry, compatible
with naturally occurring uranium.

Table V.63 - Mean activity levels measured in sediment samples collected near the CSFMA and STFA waste disposal facilities and the railroad terminal (Bq/kg dry)Radionuclide

Morvilliers
Monitoringof the CSTFA
facility
Small pond
locatedbetween the
CSFTA
storm waterbasin and the
Loriguettebrook

SoulainesDhuys
Saint Victor
brook

La Ville-aux-Bois
Les Nouesd’Amance stream

Voire river

Sampling
in ditches,in the immediate vicinityof the terminal

Knm

168 ± 17310 ± 17348 ± 32367 ± 34

255 ± 41Cs

0.31 ± 0.07

1.99 ± 0.24

0.81 ± 0.09

4.64 ± 0.46

5.1 ± 0.6

4.2 ± 0.8

Cs*nm

< 0.38< 0.38< 0.47< 0.5< 0.46

Co

< 0.1

< 0.5

< 0.5

< 0.6

0.84 ± 0.23

< 0.6

Am

nm

< 0.9

< 0.9

< 1.6

<1

< 1.1

Pu

< 0.019

< 1.2

< 0.6

< 1.3

<1

< 1.1

Pu

nm

< 1.7

< 1.3

< 2.1

< 1.5

< 0.9

Pu

nm

< 2.2

< 1.8

< 2.9

< 2.2

< 1.1

U

8 ± 1.1

8.2 ± 0.9

5.38 ± 0.39

7.4 ± 0.7

nm

nm

U

6.5 ± 0.8

7.5 ± 0.9

4.46 ± 0.34

6.8 ± 0.6

nm

nm

40

137

134

60

241

238

239

240

234

238

* Excluding values measured occasionally in April and May 2011 attributable to the Fukushima accident
nm: not measured

208

Rosnay-l’Hôpital

Brienne-le-Château
Monitoring of the railroad
terminal

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

© Geneviève Baumont/IRSN

V.6

Figure V.146 - The Tricastin nuclear power plant

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

209© A. Chézière/CEA

Monitoring of Research Centers and Nuclear Naval Bases210

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI
Monitoringof ResearchCenters andNuclear Naval
Bases
VI.1 CEA nuclear research centers and theInstitut Laue-Langevin (ILL) international
research center© O. Seignette/M. Lafontan/IRSN

VI.2 Nuclear naval bases

Monitoring of Research Centers and Nuclear Naval Bases

The results shown in this chapter concern the environmental monitoring
conducted on the research centers and nuclear naval
bases whose locations are shown in Figure VI.1 below.

VI.1 CEA nuclear
research
centers
and THE
Institut LaueLangevin (ILL)
international
research
center

Cherbourg

Fontenay-aux-Roses

Brest

SaclayÎle Longue

Bruyères-le-Châtel
ValducILL Grenoble
Grenoble
Pierrelatte
Marcoule
Cadarache

ToulonFrench Navy nuclear naval bases
CEA research center
Institut Laue-Langevin (ILL) research center

The monitoring set up around the research
centers is suited to the different potential
sources of radiological exposure present onthese sites (as a single center may containseveral types of nuclear installations) andthe environmental characteristics of each ofthese sites. For this reason, the monitoring
programs (frequency, sample matrices andradionuclide analysis) and the associatedresults differ from one site to another.
This chapter presents the radiological monitoring results for the Cadarache, Saclay, Bruyères-le-Châtel, Marcoule and Valduc CEA
centers as well as for Fontenay-aux-Roses,
whose nuclear activities are greatly reduced.
As ILL has been responsible for the environmental monitoring of both its own sites andthe Grenoble CEA center since 2010, theresults are presented in a single chapter.

Figure VI.1 – Geographical location of the research centers and nuclear naval bases.

The Codolet Centraco facility’s measurements are jointly analyzed with those of theadjoining Marcoule CEA center.

212

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Cadarache CEA center
The Cadarache CEA center, which was builtin October 1959 in the Bouches-du-Rhône
department in southern France, is located inSaint-Paul-Lez-Durance 40 kilometers northof Aix-en-Provence. This center’s activities

are structured around several R&D technological platforms mainly relating to nuclear
energy but also to new energy technologies(biomass and hydrogen), as well as to studies on the effects of radiation on plants(plant ecophysiology and microbiology).

kilometers

LegendA51 highway
Main roads
Water
Forest and farmland
Built-up areas andbusiness parks

Figure VI.2 – Geographical location of Cadarache CEA center.

6,110

1,368

8,158
CEA
IRSN

2,965
AtmosphericContinental aquatic
Terrestrial

451

Figure VI.3 – Cadarache CEA center: sample distribution by data producer and by compartment.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

213

Monitoring of Research Centers and Nuclear Naval Bases

Atmospheric compartment
Atmospheric aerosols

Activity (mBq/m3)
4

The monitoring of beta and alpha activity
indices (Figures VI.4 and VI.5) has notrevealed any abnormal values related to the
Cadarache center’s activities. No artificial
gamma-emitting radionuclide activity
above the decision thresholds of the measurement protocols used could be measured.

3

In the Cadarache CEA site’s environment,
some significant cesium‑134, cesium‑137
and iodine‑131 activity levels were observed
between the end of March and the beginning of May 2011 (Table VI.1). These findings
can be attributed to air masses contaminated by the Fukushima nuclear power plant
accident passing over France. An increase in
the gross beta activity was also observed
during this period (Figure VI.4). This is due tothe presence of artificial radionuclides linked
with the Fukushima accident.
For more information
Chapter III – The Fukushima Accident

0

Fukushima accident

2

1

Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11

Date
Measurement < DT

Significant measurement (> DT)

Figure VI.4 – Gross beta activity of aerosols near the Cadarache CEA center (mBq/m3).

Activity (mBq/m3)
1

0.75

0.5

0.25

0

Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11

Date
Measurement < DT

Significant measurement (> DT) Figure VI.5 – Gross alpha activity of aerosols near the Cadarache CEA center (mBq/m3).
Table VI.1 – Activities in aerosol samples taken in the Cadarache CEA center’s environment(mBq/m3).

Radionuclide type

Gross activity

Artificial radionuclides

Radionuclide

Mean activity (mBq/m3)

Alpha activity

0.032 ± 0.001

Beta activity

0.32 ± 0.01
0.68 ± 0.02*

Cesium-134

0.032 ± 0.008*

Cesium-137

0.036 ± 0.008*

Iodine-131

0.13 ± 0.02** Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

214

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Bq/m3

Gases sampled by bubblers
1

Atmospheric tritium and carbon-14 are collected using bubblers. The activities measured for these two radionuclides are rarely
above the decision thresholds (their respective mean activities are 0.18 Bq/m3 for tritium – see Figure VI.6 – and 0.06 Bq/m3 forcarbon-14).

0.9
0.8
0.7
0.6
0.5
0.4
0.3

Other gases (iodine-131)

0.2

The monitoring of gaseous iodine-131 activity revealed the presence of this radionuclide during the Fukushima nuclear power
plant accident (Table VI.2). Except during
this period, no significant activity was measured because there is very little of this radionuclide in the discharge from the center’s
installations.

0.1
0
0
.-1
Jan

0
r.-1
Ma

0
y-1
Ma

Significant activity (> DT)

-10
Jul.

0
t.-1
Sep

0
v.-1
No

1
.-1
Jan

1
r.-1
Ma

1
y-1
Ma

Decision threshold

Figure VI.6 – Atmospheric tritium activity near the Cadarache CEA center (Bq/m3).

Bq/L

10
T able VI.2 – Gaseous iodine-131 activity measured in the ambient air near the Cadarache CEA
center (mBq/m3).

9
8
7Radionuclide
type

Radionuclide

Mean activity
ordecisionthreshold(mBq/m3)

6
5
4
3
2

Radionuclide
in gaseous
form –of artificial
origin1

Iodine131< 2.90.14 ± 0.04 ** Measurements taken during the period of the
Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

0

90
v.-0 Jan.-1
No

0
r-1
Ma

0
y-1
Ma

Significant activity (> DT)

-10
Jul.

0
t.-1
Sep

0
v.-1
No

1
.-1
Jan

1
r-1
Ma

1
y-1
Ma

-11
Jul.

Decision thresholdFigure VI.7 – Tritium activity measured in rainwater near the Cadarache CEA site (Bq/L).

Rainwater
The measured tritium activities in the rainwater samples taken near the site vary
between the decision thresholds (in 95% ofcases) and 6.5 Bq/L between 2009 and mid2011 (Figure VI.7). As the site discharges little tritium, the tritium levels observed in theenvironment are very low and usuallyunquantifiable.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

215

Monitoring of Research Centers and Nuclear Naval Bases

Terrestrial compartment
The terrestrial monitoring of the Cadarache
CEA center is based on the regular sampling
and analysis of milk and agricultural plants
and cereals produced in areas potentiallyinfluenced by the facilities’ discharge, within
a 20 km radius of the site.

are between 0.36 ± 0.26 and0.99 ± 0.43 Bq/kg wet. Similarly, low
cesium-134 activities were also detected in
the thyme sample taken on April 3, 2011 in
Ginasservis (a specific activity of
0.26 ± 0.13 Bq/kg wet).
For more information
Chapter III – The Fukushima Accident

Agricultural production and foodstuffs
Milk
Monthly or quarterly goat’s and cow’s milk
samples are taken at three farms in themunicipalities of Gréoux-les-Bains, Meyrargues and Jouques around the Cadarache
center. The measured radioactivity is mainly
due to natural potassium-40, whose mean
activity concentration is 49.6 ± 2.8 Bq/L in
cow’s milk and 61 ± 2.2 Bq/L in goat’s milk.
Normally, artificial gamma-emitting radionuclides (134Cs, 137Cs and 131I), like free tritium, are not detected by routine monitoring
methods. Traces of iodine-131 were, however, detected in the goat’s milk sample
taken on April 8, 2011 in Gréoux-les-Bains(0.55 ± 0.3 Bq/L); this was due to long-range
atmospheric fallout caused by the damaged
Fukushima nuclear plant.
For more information
Chapter III – The Fukushima Accident
Cereals
No gamma-emitting radionuclides likely tobe released by the Cadarache CEA center’sfacilities have been detected in the wheat
samples taken in the area around this site.
Only natural potassium-40 is measured,with a mean specific activity of
137 ± 29 Bq/kg dry.
Leafy vegetables and aromatic plants
Analysis of monthly or annual samples ofthyme, chives and spinach grown near the
Cadarache center has not revealed any
anomalies (Table VI.3). Cesium-137 is regularly measured in the thyme samples, probably as a result of fallout from the Chernobyl
accident. The traces of strontium-90 measured in the spinach samples taken in Vinonsur-Verdon can be attributed to past
atmospheric fallout from nuclear weapons
testing.
Following the nuclear disaster at the Fukushima-Daiichi power plant in Japan on
March 11, 2011, traces of iodine-131 weredetected in the four thyme samples taken
on April 3, 2011. Their measured activities

216

T able VI.3 – Mean activity levels measured in the vegetable and aromatic herb samples taken around
Cadarache CEA center (Bq/kg wet).
Saint-Paul-lez-Durance

Ginasservis

Vinon-sur-Verdon

1.7 km300 m
3.8 kmsouth of southeast northeastof thethe siteof thesite (out(undersite
of thethe(underprevailingprevailingtheprevailingwinds)
winds)
winds)

7.6 kmsoutheastof the site(undertheprevailingwinds)

5.5 km northeastof the site (out of theprevailing winds)

Thyme

Thyme

Thyme

Thyme

ChivesSpinachK

229 ± 7233 ± 8202 ± 6

201 ± 635 ± 10185 ± 23

Cs

0.24 ±
0.03

0.24 ±
0.03

0.22 ±
0.03

0.20 ± 0.03

< 0.12< 0.06Cs*< 0.16< 0.15< 0.14< 0.14< 0.1< 0.05Pb

37.4 ±
3.3

54 ± 533.8 ±
3.3

61 ± 5

nm

nm

90

Sr

nm

nm

nm

nm

nm

0.08 ±
0.015

HTO

nm

nm

nm

nm

nm

<8

Radionuclide

40

137

134

210

* Excluding a significant value measured following the Fukushima accident nm: not measured

Continental aquaticcompartment
Surface water
The Cadarache CEA center is the only nuclear
site on the banks of the Durance river. The
discharge is monitored downstream of thesite by means of automatic sampling at the
Mirabeau bridge. The tritium activity measured at this point ceased to be quantifiable atthe beginning of the ’90s, as the levels havebeen below 5 Bq/L since then (Figure VI.8).
Sediments
In 2010, three sediment samples were takenin the Durance river, 400 meters downstream of the Cadarache site’s liquid waste
discharge point.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

Of the three artificial gamma-emitting radionuclides being monitored, only traces ofcesium-137 were detected. The annual
mean value in 2010 for this radionuclide(1.07 ± 0.17 Bq/kg dry) is similar to the levels observed in previous years. Given the lowlevels of cesium-137 discharged in the
Cadarache site’s liquid waste (< 10 Bq/L in
the waste before it enters the river), thepresence of this radionuclide in the sediments is mainly due to residue from atmospheric fallout (nuclear weapons testing in
the atmosphere, and fallout from the Chernobyl accident). The other radionuclides’
measurement results were all below thedecision threshold (Table VI.4).

VI.1
 able VI.4 – Mean activity levels measured inT
Durance river sediment samples taken
400 meters from the Cadarache CEA center'sdischarge point (Bq/ kg dry).

Bq/L

40
35
30

Radionuclide

ActivityK

253 ± 20

25

40

20

137

15
10

0

1.07 ± 0.17
<6Am

0.16 ± 0.05

Pu

< 0.05Pu< 0.05

241

1968
1970
1971
1973
1975
1977
1978
1980
1982
1983
1985
1987
1989
1990
1992
1994
1996
1999
2001
2002
2004
2006
2008
2009
2011
2013

5

Cs

Other gamma-emitting
radionuclides(110mAg, 124Sb, 125Sb, 134Cs,
58Co, 60Co, 131I, 54Mn, 106Ru)

Significant activity (> DT)

238

Decision threshold

239+240

F igure VI.8 – Tritium activity in Durance river water downstream of the Cadarache
CEA site (Bq/L).
Bq/L
Ground water
0.30

Other spot sampling points exist, notably a
piezometer network for monitoring groundwater activity levels. The site is located on
two aquifers, the upper consisting of Miocene and Quaternary detrital formations
while the lower consists of karstic limestone.
The ground water finally enters the Durance
river via its tributaries.
A slight total alpha concentration(0.11 Bq/L) is observed in the piezometer“CHAU02” located near the Magenta facility on the site (Figure VI.9). This piezometer
already detected natural gross alpha activity values slightly above the decision threshold before this facility entered into
operation.

0.25
0.20
0.15
0.10
0.05
0
Jul.-10

Sept.-10

Nov.-10Significant activity (> DT)

Jan.-11

Mar.-11May-11

Decision thresholdFigure VI.9 – Gross alpha activity measured in ground water at piezometer “CHAU02” (Bq/L).
Bq/L
60
50
40

The tritium measurements vary between
the decision thresholds and 50 Bq/L at the“SD5” point (Figure VI.10). This point also
detected gross beta activity, with levels fluctuating between 3 and 71 Bq/L from 2009
to mid-2011 (Figure VI.11). This layer’s historic concentration level has no impact outside the site.

30
20
10
0
Nov.-09

Jan.-10

Mar.-10Significant activity (> DT)

May-10Jul.-10

Sept.-10

Nov.-10Jan.-11

Mar.-11 May-11

Decision threshold

Figure VI.10 – Tritium activity measured in ground water at piezometer “SD5” (Bq/L).
Bq/L
90
80
70
60
50
40
30
20
10
0
Nov.-09

Jan.-10

Mar.-10May-10Jul.-10

Sept.-10

Nov.-10Jan.-11

Mar.-11 May-11

Significant activity (> DT)
Figure VI.11 – Gross beta activity measured in ground water at piezometer “SD5” (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

217

Monitoring of Research Centers and Nuclear Naval Bases

Bruyères-le-Châtel
CEA center
The Bruyères-le-Châtel CEA center, which
was created in 1955 in the Paris region, conducted the first metallurgical studies of thenuclear materials used in weapons.
Today, this center is a research facility where
work is grouped into different areas of exper-

tise (simulating and modeling the operationof nuclear weapons, assisting in the monitoring of disused French firing ranges, supporting international organizations inchecking compliance with the Nuclear Test
Ban Treaty, and managing nuclear facility
construction, clean-up and decommissioning projects).

Since 1997, clean-up operations conductedduring nuclear facility decommissioning
have continued to produce tritium releases
in the gaseous waste, although their annual
activity levels are gradually decreasing (frommore than 100 TBq released in 2005 to lessthan 50 TBq in 2009).

All of the site’s military activities weretransferred to the Valduc center in 1996.

LegendWater
Forest and farmland
Built-up areas andbusiness parks

metersFigure VI.12 – Geographical location of Bruyères-le-Châtel CEA center.

4,376

6,394

178

34
CEA
IRSN

1,874

AtmosphericContinental aquatic
Terrestrial

Figure VI.13 – Bruyères-le-Châtel CEA center: sample distribution by data producer and by compartment.

218

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VI.1
Atmospheric compartment
4

Atmospheric aerosols
Apart from the readings taken during theperiod of the Fukushima accident, no otherabnormal alpha activity index values(Figure VI.15) and beta activity index values(Figure VI.14) or artificial radionuclides havebeen detected.
In the Bruyères-le-Châtel site’s environment,
the monitoring of atmospheric aerosols
revealed an increase in gross beta activity
between the end of March and the end of
A p r i l 2 0 1 1 ( Ta b l e V I . 5 a n dFigure VI.14), which can be attributed to thepresence of artificial radionuclides releasedin the Fukushima nuclear power plant
accident.
For more information
Chapter III – The Fukushima Accident
 able VI.5 – Alpha and beta activity
T
indices of the Bruyères-le-Châtel CEA
center’s environmental aerosols (mBq/m3).

Radionuclide
type

Gross
activity

Activity (mBq/m3)

Radionuclide

Mean
activity(mBq/m3)Alpha
activity

0.024 ±
0.001

Beta
activity

0.25 ± 0.01
0.47 ±
0.01** Measurements taken during the period of the
Fukushima nuclear power plant accident.

Fukushima accident

210Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11

Date
Measurement < DT

Significant measurement (> DT)

Figure VI.14 – Time plot of the gross beta activity of aerosols near the
Bruyères-le-Châtel, Saclay and Fontenay-aux-Roses CEA centers (mBq/m3).
Activity (mBq/m3)
2
See CEA
Fontenay-aux-Roses

1,5

1

0,5

0
Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11

Date
Measurement < DT

Significant measurement (> DT)F igure VI.15 – Time plot of the gross alpha activity of aerosols near the
Bruyères-le-Châtel, Saclay and Fontenay-aux-Roses CEA centers (mBq/m3).

Rainwater
Rainwater is drained at the site’s four cardinal points. The activity levels of the water
samples taken there vary depending on thegaseous releases and the wind direction.
Only the tritium activity levels measured in
the water in the drain at the site’s east side
exceed 5 Bq/L, with maximum values ofnearly 30 Bq/L in 2010 reflecting the site’s
activities (Figure VI.16).

See CEA
Fontenay-aux-Roses

3

35

Bq/L

30
25
20
15
10
5
0
Nov.-09

Jan.-10E. station

Mar.-10
N. station

May-10Jul.-10

W. station

Sept.-10
S. station

Nov.-10Jan.-11

Mar.-11 May-11

Decision thresholdFigure VI.16 – Tritium activity in rainwater near the Bruyères-le-Châtel CEA site (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011219

Monitoring of Research Centers and Nuclear Naval Bases

Terrestrial compartment
The area surrounding the Bruyères-le-Châtel
CEA center is monitored by means ofmonthly grass and milk samples. The site’smonitoring also includes the analysis of vegetable samples.
Terrestrial flora
Tritium is occasionally measured in the grasssamples taken within a 1.7 km radius of the
Bruyères-le-Châtel CEA center. The significant free tritium values, which vary between
3.2 ± 1.9 and 6.7 ± 2.1 Bq/kg wet, are close
to the decision thresholds and show little
added environmental concentraion by the
Bruyères-le-Châtel center’s environmental
discharge (Table VI.6).

Continental aquaticcompartment
The Bruyères-le-Châtel CEA center islocated in the basin of the Orge river, whichflows into the left side of the Seine at a rateof nearly 5 m3/s.
Surface water
The cesium-134, cesium-137, cobalt-60,
selenium-75 and strontium-90 levels in thesurface water samples taken near the Bruyères-le-Châtel CEA center are too low to
be measured. The mean total alpha concentration at a surface water source near theside of the Orge river’s retaining basin is
0.07 Bq/L, which is slightly higher than at
the other sampling points (0.04 Bq/L) (Figure VI.17). This concentration level is mainly
due to naturally occurring radionuclides.

The gross alpha activity in the water of thepond named “Mare 6” west of the Orge river’s retaining basin is approximately 1 Bq/L.
Added concentrations were detected only atthis sampling point. In the other ponds, thisactivity varies between 0.05 Bq/L and
0.1 Bq/L (Figure VI.18).
The presence of alpha-emitting radionuclides in pond “Mare 6”, whose activity concentration is higher than that of the otherponds, is of natural origin (natural uranium
decay chain products are present). This pond
is located in an agricultural environment(the 238U content is increased through theuse of fertilizers).

Agricultural production and foodstuffs
Milk
The radioactivity measured in the cow’s milk
samples taken each month at farms in SaintSulpice-de-Favières and Cheptainville ismainly due to natural potassium-40, whosemean activity concentration is35.6 ± 0.6 Bq/L. Between January 2010 andthe end of May 2011, the milk from Cheptainville occasionally contained traces oftritium (10 ± 4 Bq/L in September 2010 and
3.6 ± 1.9 Bq/L in March 2011). These activities should be viewed in relation to the concentration level in grass due to the site’sdischarge.
Leafy vegetables
The OBT specific activity measured in the
carrot samples taken in Saint-Yon in 2010
was 0.123 ± 0.006 Bq/kg wet. This is close
to the value that is naturally found in theenvironment.

Bq/L
0.25

0.20

0.15

0.10

0.05

0
Nov.-09

Jan.-10

Mar.-10May-10Significant activity (> DL)

Jul.-10

Nov.-10Jan.-11

Mar.-11 May-11

Decision limitF igure VI.17 – Gross alpha activity in surface water samples taken near the Orge river’s
retention basin (Bq/L).

 able VI.6 – Mean tritium activity levels measured in grass samples taken aroundT
Bruyères-le-Châtel CEA center.

Sampling location

Number of significant
results/total number of
HTO measurements

HTO(Bq/kg wet)

OBT
(Bq/kg dry)Bruyères-le-ChâtelWest of the site

0/17

< 3.2

nm

Bruyères-le-ChâtelSouthwest of the site

2/17

3.2 ± 0.39

nm

OllainvilleSoutheast of the site

3/17

3.33 ± 0.41nm

OllainvilleNortheast of the site

5/17

3.41 ± 0.41

2.34 ± 0.12

nm: not measured

220

Sept.-10

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Bq/L
10

1

0.1

0.01

.-09
Dec

.-10 ar.-10 ay-10
Jan
M
M

Orge retaining basin

-10
Jun

“Mare 2“-10 pt.-10 ov.-10
Aug
N
Se

.-11 eb.-11 pr.-11
Jan
F
A“Mare 3““Mare 6““Mare 5“-11Jun

© IRSNF igure VI.18 – Gross alpha activity in water samples taken in the ponds near the
Bruyères-le-Châtel CEA center (Bq/L).

F igure VI.19 – Taking a water sample in the Fontaine pond near Bruyères-le-Châtel CEA center.

Sediments
In 2008, IRSN conducted an exploratoryenvironmental sampling campaign near thiscenter in order to measure the radioactivity
levels of the river and lake sediments. Two
sampling points were chosen to provide thesite’s routine monitoring, one in the
Rémarde river and other in the Grand Rué
stream, both of which flow into the Orge
river. The presence of transuranium radionuclides such as plutonium-239+340 andamericium-241 can be attributed to past liquid waste discharge (Table VI.7). As in 2008
and 2009, the uranium-234 and uranium-238 isotope ratios measured in 2010,
the values of which were approximately 1,
show the natural presence of uranium.

 able VI.7 – Activities measured in the sediment samples taken in 2010 near the
T
Bruyères-le-Châtel site (Bq/kg dry).

Radionuclide

Le Grand Rué stream

La RémardeCs

1.02 ± 0.28

2.6 ± 1Other gamma-emitting
radionuclides(124Sb, 125Sb, 134Cs, 54Mn,
58Co, 60Co, 106Ru)

< 4.6

<6

Am

0.59 ± 0.16

0.16 ± 0.08

Pu

< 0.08nm

239+240Pu

3.2 ± 0.5

nm

U15.3 ± 3.2

12.9 ± 1.2

U0.84 ± 0.18

0.68 ± 0.16

U

16.3 ± 3.3

13.1 ± 1.2

U/238U activity ratio

0.941

0.980

137

241

238

234
235
238
234

nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

221

Monitoring of Research Centers and Nuclear Naval Bases

Fontenay-aux-Roses
CEA centerand development activities, including thefirst French atomic pile (“Zoé”), were conducted at this site in Fontenay-aux-Roses.

The Fontenay-aux-Roses CEA center, which
is located in the Paris region and was thefirst CEA center, was built on the premisesof the historical Châtillon fort in 1946. For
nearly ten years, all French nuclear research

After orienting the site’s activities towards
plutonium and transuranium chemistry,
radiation and the examination of fuels,
radiation metallurgy and controlled fusion,

CEA ceased all its nuclear research activities
at Fontenay in 1995. The center’s research
now concentrates on public health mattersof great socioeconomical importance in theradiobiology and toxicology, neurovirology
and prion diseases, robotics and virtual
reality fields.

LegendDepartment
Municipalities
Highways
Main roads
Business parks
Built-up areas
Meadows
ForestWater

Km

Figure VI.20 – Geographical location of Fontenay-aux-Roses CEA center.

4,381

7,353

2,706

6
272
CEA
IRSN

AtmosphericContinental aquatic
Terrestrial

Figure VI.21 – Fontenay-aux-Roses CEA center: sample distribution by data producer and by compartment.

222

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VI.1
Atmospheric compartment

 able VI.8 – Alpha and beta activity indices of aerosols in the Fontenay-aux-Roses CEAT
center’s environment (mBq/m3).

Atmospheric aerosols
The monitoring of atmospheric aerosols in
the Fontenay-aux-Roses CEA site’senvironment by checking gross alpha andgross beta activity (Figures VI.14 and VI.15)
revealed unusually high levels in a sample
t a k e n i n F o n t e n a y - a u x- R o s e s o n
February 11–12, 2010 (its beta activity
index was 1.8 ± 0.9 mBq/m3, and its alphaactivity index was 1.9 ± 0.9 mBq/m 3).
Further investigations concluded that theseunusually high activities were not due toartificial radionuclides.

Radionuclide type

Gross activity

Radionuclide

Mean activity (mBq/m3)

Alpha activity

0.025 ± 0.001

Beta activity

0.29 ± 0.01
0.57 ± 0.01** Measurements taken during the period of the Fukushima nuclear power plant accident
from March 22 to May 6, 2011.

An increase in the gross beta activity
between the end of March and the end of
April 2011 was also observed, however(Table VI.8). This can be attributed to thepresence of artificial radionuclides released
at the time of the Fukushima nuclear power
plant accident.

© F. Jannin/CEA

Apart from this finding and the readings
taken during the period of the Fukushima
accident, no other abnormal alpha activity
and beta activity index values or artificial
radionuclides have been detected in theenvironment.

Figure VI.22 – Daily retrieval and conditioning of the aerosol filter.

Gases sampled by bubblers
The mean activity of atmospheric tritium,
which was sampled using bubblers, wasapproximately 0.3 Bq/m 3 in 2010 (Figure VI.23). Tritium oxide (HTO) activity
increased slightly in the first half of 2011
(between 0.6 and 0.8 Bq/m3). Until January 2011, only the first bubbler tank’s measurement was used to calculate atmospherictritium activity. Following an inspection in
December 2010, however, the French
Nuclear Safety Authority (ASN) asked CEA
to also use the second sparge tank so thatthe two tanks’ activities could be added
together. This explains the increased activity
values from January 2011 onwards.

1.6

Bq/m3

1.4
1.2
1
0.8
0.6
0.4
0.2
0
Jan.-10 Mar.-10

May-10Significant activity (> DL)

Jul.-10

Sept.-10

Nov.-10Jan.-11

Mar.-11May-11 Jul.-11

Decision limitF igure VI.23 – Atmospheric tritium (HTO) activity measured near the Fontenay-aux-Roses CEA
center (Bq/m3).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

223

Monitoring of Research Centers and Nuclear Naval Bases

Other gases

 able VI.9 – Gaseous iodine-131 activity measured in the ambient air nearTthe Fontenay-aux-Roses and Saclay CEA centers (mBq/m3).

The monitoring of gaseous iodine-131 activity revealed the presence of this radionuclide during the period of the Fukushima
nuclear power plant accident (Table VI.9).
For more information
Chapter III – The Fukushima Accident
Except during this period, no significant
activity has been measured, as the discharge
from the Fontenay-aux Roses center’s facilities contain little or no iodine-131.

A total alpha activity of 1.17 Bq/L wasdetected in rainwater samples taken in Bagneux in June 2010 (Figure VI.24). This activity is linked with a fire near theenvironmental monitoring station, causing
considerable diffusion of solid particles in
the air; these particles then settled in the
rainwater drain due to gravity and air column leaching. The supplementary measurements, which CEA took using spectrometry,
indicate natural radioactivity levels similar
to those found in the sludge.

Terrestrial compartment
The area surrounding the Bruyères-le-Châtel
CEA center is monitored by means ofmonthly grass samples.

Radionuclide

Mean activity or detection
limit (mBq/m3)

Artificial gaseous radionuclide

Iodine-131< 0.510.21 ± 0.026** Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

1.6

Rainwater

Radionuclide type

Bq/L

1.4
1.2
1
0.8
0.6
0.4
0.2
0
Nov.-09

Jan.-10

Mar.-10

FAR/EAU/ATMOS

May-10FAR/EAU/BAGNEUX

Sept.-10

Nov.-10Jan.-11

Decision thresholdF igure VI.24 – Gross alpha activity in rainwater near the Fontenay-aux-Roses
CEA site (Bq/L).

Terrestrial flora
Analysis of the monthly grass samples taken
in Fontenay-aux-Roses, Bagneux andClamart has not revealed any abnormal
activity levels. Between January 2010 andthe end of May 2011, only three samples
had significant cesium-137 activities ofbetween 1.2 ± 0.9 and 1.8 ± 1.1 Bq/kg wet.

224

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Mar.-11 May-11

VI.1
Continental aquaticcompartment
Surface water

Bq/L
0.45

Surface water monitoring is conducted at
the Colbert pool, which collects rainwaterand is situated less than 2 km from the site.
Analysis of radionuclides in its water has notrevealed any abnormal total alpha concentration levels (0.06 Bq /L). No americium-241, cesium-134 or cesium-137 has
been detected there. Tritium has been
detected in 20% of the samples, at levels
below 4 Bq/L.

0.40
0.35
0.30
0.25
0.20
0.15
0.10

Ground water

0.05

The Fontenay-aux-Roses CEA center is situated directly above ground water 65 meters
below the site. This ground water emerges
at two points: the Lavoir and Moulin fountains in Fontenay-aux-Roses, both of which
are monitored as part of CEA’s hydrologicalmonitoring plan. The ground water’s totalalpha activity varies between 0.05 and0.3 Bq/L depending on the sampling point(Figure IV.25).
The points with the highest tritium activities (Figure VI.26) differ from those withalpha-emitting radionuclide activities. The
activity in the point named “Nappe G” (orLevel G) has been increasing for a year,
whereas that in the other points is residual.
This short-term trend should, however, be
put into perspective by comparing it withthe historical chronicles, which show thatthese measurements are cyclical(Table VI.10). No other artificial radionuclides have been measured at this point.

0
Dec.-09

Feb.-10LavoirApr.-10

MoulinJun-10Level A

Level B

Jul.-10
Level C

Sept.-10

Nov.-10

Level F

Jan.-11
Level G

Mar.-11

Level HF igure VI.25 – Gross alpha activity in ground water near the Fontenay-aux-Roses
CEA site (Bq/L).

Bq/L
18
16
14
12
10
8
6
4
2
0
Dec.-09

Feb.-10LavoirApr.-10

MoulinJun-10Level A

Level B

Jul.-10
Level C

Sept.-10

Nov.-10

Level F

Jan.-11
Level G

Mar.-11
Level HF igure VI.26 – Tritium activity in ground water near the Fontenay-aux-Roses
CEA site (Bq/L).

F igure VI.27 – Tritium activity in ground water at sampling point “Nappe G” near the Fontenay-aux-Roses CEA site (Bq/L).

2002

2003

2004

2005

2006

2007

2008

2009

2010

2011

Maximum H activity (Bq/L)

9.1

12.4

15

13

18.3

16.8

6.5

8.7

12.8

16.7

Mean H activity (Bq/L)

/

/

/

/

13.1

7.2

4.7

5.8

9.4

10.6

Standard deviation

/

/

/

/

2.92

3.54

1.18

1.34

2.61

3.33

3

3

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

225

Monitoring of Research Centers and Nuclear Naval Bases

Marcoule site
The Marcoule site in southern France is
one of the country’s largest nuclear sites
and performs a wide range of activities,
conducting scientific and technologicalstudies that assist manufacturers in
improving the performance of their
existing fuel cycle plant processes. Its
work is mainly concerned with the processing and recycling of nuclear fuels
following their use in reactors, with theaim of optimizing the recycling of reusable energy materials, reducing thequantity of the final waste and ensuring
the waste’s safety. At the front end of
the cycle, the Marcoule CEA center performs research to maintain the technical and economic competitiveness ofFrench industry and reduce the environmental effects of these steps. The site
consists of 18 facilities including reactors (Phénix), a fuel production plant(Melox) and a high-radioactivity radio-chemistry research facility (Atalante). It
formerly housed the first French electricity production generator (G1) as well
as facilities that preceded those now
forming part of the La Hague plant: thereprocessing plant (UP1), and the vitrification workshop (AVM). Most of theseold facilities have now ceased operation
and are currently being dismantled.
Marcoule’s 50 years of operation havealso created nuclear waste, some ofwhich is still awaiting safe disposal.

LegendWater
Forest and farmland
Built-up areas andbusiness parks

kilometers

Figure VI.27 – Geographical location of the Marcoule CEA center.

Centraco, the French nuclear center for processing and conditioning radioactive waste,
which is also located on the Marcoule site,
is managed by SOCODEI, the French company for the conditioning of industrial waste
and effluents. The Centraco plant processes
metal and fuel waste with the aim of reducing its volume, recycling it whenever possible, and conditioning it in the ultimate
waste forms accepted by ANDRA, the French
National Radioactive Waste Management
Agency. This site’s monitoring measurement
values are discussed with those of the Marcoule CEA center in this chapter.

4,764

6,373

CEA
IRSN

1,490

991

2,020
AtmosphericContinental aquatic
Terrestrial

Figure VI.28 – Marcoule CEA center: sample distribution by data producer and by compartment.

226

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Atmospheric compartment

Activity (mBq/m3)
4

Atmospheric aerosols
Except during the Fukushima accident
period, no other abnormal gross alpha activity (Figure VI.30) and gross beta activity
values have been observed. Only lead-210
and beryllium-7, both of which are naturalradionuclides, are regularly measured.
In the Marcoule site’s environment, an
increase in the beta activity index measured
in the aerosols was observed between theend of March and the end of April 2011
(Table VI.11 and Figure VI.29). This increaseis mainly due to the presence of artificial
radionuclides linked with the Fukushima
nuclear power plant accident’s atmosphericfallout over France.
For more information
Chapter III – The Fukushima Accident

Fukushima accident

3

2

1

0
Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11

Measurement < DT

Figure VI.29 – Time plot of the gross beta activity of the aerosols near the
Marcoule site (mBq/m3).

Activity (mBq/m3)
1

0.75

0.5

0.25

0
Jan.-10

Apr.-10

Measurement < DT

Jul.-10

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)F igure VI.30 – Time plot of the total alpha activity index of the aerosols near the
Marcoule site (mBq/m3).
 able VI.11 – Activities in the atmospheric aerosol samples taken in the MarcouleTsite’s environment (mBq/m3).

Radionuclide type

Total activity indicesRadionuclide

Mean activity (mBq/m3)

Alpha activity

0.13 ± 0.01

Beta activity

0.49 ± 0.01
0.96 ± 0.02** Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

227

Monitoring of Research Centers and Nuclear Naval Bases

30
25
20
15
10
5

CodoletGaseous iodine-129 is monitored by meansof air cartridge sampling. It has not revealed
any significant activity levels (Table VI.12).
Rainwater
Analysis of the rainwater samples taken at
the Codolet monitoring station south of the
Marcoule site has revealed the continued
presence of atmospheric tritium, confirming
the measurements obtained using the bubblers. Figure VI.32 shows the variability ofthe tritium concentrations measured
in 2010 at this station. This variability
depends on the level of the discharge fromthe site’s facilities and the wind direction.

Saint-Étienne-des-Sorts

Jan
.-1
2

Jul
.-1
1
Se
pt
.-1
1
No
v.11

Jan
.-1
1
Ma
r.11
Ma
y11

0
Jul
.-1
0
Se
pt
.-1
0
No
v.10

Other gases

Bq/m3

Jan
.-1
0
Ma
r.10
Ma
y10

Significant quantities of atmospheric tritium
have been measured at the Codolet monitoring station south of the site and at SaintÉtienne-des-Sorts north of the site. The
influence of the prevailing winds, whichmainly blow southwards, can be seen in Figure VI.31. The activity concentration of theatmospheric tritium is generally higher andusually significant in Codolet (south of thesite) than in Saint-Étienne-des-Sorts (northof the site).

35

No
v.09

Gases sampled by bubblers

Decision thresholdFigure VI.31 – Atmospheric tritium activity measured near the Marcoule site (Bq/m3).
 able VI.12 – Gaseous iodine-129 activity measured in the ambient air nearT
the Marcoule site (mBq/m3).

Radionuclide typeRadionuclide

Mean activity or detection
limit (mBq/m3)

Artificial gaseous radionuclide

Iodine-129< 0.32

140

Bq/L

120
100
80
60
40
20
0
Dec.-09

Feb.-10

Apr.-10Significant activity (> DT)

Jun-10Jul.-10

Sept.-10

Nov.-10

Decision thresholdFigure VI.32 – Tritium activity in the rainwater samples taken near the Marcoule site (Bq/L).

228

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

Jan.-11

VI.1
Terrestrial compartment
The Marcoule nuclear site’s monitoring
includes regular sampling of terrestrial
plants (grass, vegetables and fruit), milk,
cereals and wine in zones potentially influenced by the facilities’ discharge, within a
20 km radius of the CEA center.
Terrestrial floraMonthly grass samples are taken at ten
sampling points around the Marcoule site,seven of which are within 300 meters of
its boundary. This monitoring is supplemented by two twice-yearly samples
taken in Codolet and Saint-Étienne-desSorts. The main results are shown in
Table VI.13.
Low cesium-137 activities are occasionally measured at five sampling points
directly under the main and secondary
prevailing winds. These are between
0.8 ± 0.7 Bq/kg dry and 3.6 ± 1.3 Bq/kg
dry. The two strontium-90 analyses

conducted in 2010 revealed the presenceof this radionuclide in the grass samples
taken north and south of the site; theiractivities were similar to those observed
throughout France as a result of past
atmospheric fallout from nuclear
weapons testing.

The free tritium activity levels measured
in the grass samples are, however, considerably higher than the mean values
recorded for France (generally below
3.6 Bq/kg wet). These activity levels canbe attributed to the Marcoule site’s
atmospheric discharge, which contributeto this radionuclide's added environmental concentration. The stations mostaffected are those directly under the main
prevailing winds south of the Marcoulesite and the secondary prevailing winds
north of the site, as Figure VI.33 shows.

Between January 2010 and the end of
May 2011, very low plutonium-239 activity levels were occasionally detected atfour sampling points under the main prevailing winds, in the immediate vicinity of
the Marcoule site (one significant measurement for each of the sampling points
for the entire period). These activities,
which were between 0.007 ± 0.006 Bq/
kg dry and 0.077 ± 0.014 Bq/kg dry andwere not to be found above a certain distance away from the site, are partly due
both to past atmospheric fallout from
nuclear weapons testing and to past
waste from the Marcoule site’s facilities.
The other artificial alpha- and gammaemitting radionuclides’ activities are
below the decision thresholds.

It should be noted that these activity levels vary greatly over time, depending on
the activity level of discharge and themeteorological conditions when the sample is taken. As a result, the free tritium
activity levels measured 200 m south of
the Marcoule site vary between
76 ± 6 Bq/kg wet and 1,270 ± 60 Bq/kg
wet for the period from January 2010 to
May 2011 (Table VI.14).

Table VI.13 – Mean activities measured in the grass samples taken around the Marcoule site (Bq/kg dry)*.

CodoletRadionuclide

Southwest
Site boundary

South – 200 m

Caderousse

South – 900 m

South – Southwest – 1.8 km

East – Siteboundary

East – Southeast– 2.2 kmK

407 ± 20248 ± 15549 ± 22422 ± 20292 ± 15376 ± 17Cs

0.68 ± 0.08

0.77 ± 0.1

0.69 ± 0.08

< 0.7

0.6 ± 0.08

< 0.7

Ru

< 11

< 12

< 11

< 12

< 10

< 11

Sr

nm

nm

0.23 ± 0.05

nm

nm

nm

40
137
106
90

Am

nm

nm

< 0.0027

nm

nm

nm

Pu

< 0.0018< 0.011< 0.0038< 0.0039< 0.0035< 0.0022

Pu

0.0058 ± 0.0014

0.0188 ± 0.004

0.011 ± 0.0042< 0.009< 0.012< 0.008

HTO (Bq/kg wet)

10.4 ± 1.1

120.8 ± 4.6

30.7 ± 2.5

16.5 ± 1.8

17.8 ± 1.4

6.1 ± 1

OBT

nm

nm

135 ± 7

nm

nm

nm

C

nm

nm

173 ± 24

164 ± 22

nm

nm

241

238
239

14

ChusclanSaint-Étienne-des-Sorts

Radionuclide

Northeast
Site boundary

North
Site boundary

Northwest – 300 m

West
Site boundary

North – 5.1 km

K

288 ± 14229 ± 12233 ± 12211 ± 11610 ± 60

40

Cs

< 0.7

0.61 ± 0.08

< 0.6

< 0.7

< 0.8

Ru

< 11

<9

< 11

< 10

<7

Sr

nm

nm

nm

nm

0.39 ± 0.06

137
106
90

Am

nm

nm

nm

nm

< 0.0045

Pu< 0.0013< 0.0024< 0.0039< 0.0036< 0.0021

Pu< 0.0048< 0.006

0.006 ± 0.0016< 0.0025< 0.0021

HTO (Bq/kg wet)

37.1 ± 1.5

16 ± 1.1

41.2 ± 1.7

11.5 ± 0.9

< 1.5

241

238
239

* Unless specified otherwise
nm: not measured
IRSN – Report on the Radiological State of the Environment in France in 2010–2011229

Monitoring of Research Centers and Nuclear Naval Bases

Towards Saint-Étienne-des-Sorts
100

50
Chusclan

50

10

100

Towards Orange

Towards Orsan

CodoletMean free 3H activity(Bq/kg wet)F igure VI.33 – Geographical distribution of mean free tritium activity levels measured in the grasssamples taken in the immediate vicinity of the Marcoule site (< 300 meters from the nuclear facilities)(Bq/kg wet).

Municipality

CodoletCaderousse

ChusclanSaint-Étiennedes-Sorts

Location
relative to
the Marcoule site

Range of HTO
activities(Bq/kg wet)Southwest
Site boundary< 3.2 / 145 ± 10

South – 200 m

76 ± 6 / 1270 ± 60

South – 900 m

3.5 ± 3 / 526 ± 26

South – 1.8 km< 4 / 566 ± 28

East – Site boundary

4.7 ± 1.5 / 135 ± 9

East – Southeast
2.2 km

< 2.3 / 151 ± 11

Northeast
Site boundary

16.5 ± 2.5 / 113 ± 8North – Siteboundary

2.7 ± 1.7 / 180 ± 13

Northwest – 300 m

30 ± 3.9 / 443 ± 24

West – Site boundary

5.2 ± 1.4 / 54 ± 4.4

North – 5.1 km< 1.5© Leprieur/IRSN

 able VI.14 – Range of free tritium activity levels measured in theTgrass samples taken near the Marcoule site (Bq/kg wet).

* Unless specified otherwise

Figure VI.34 – Taking grass samples south of the Marcoule CEA center.

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IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Agricultural production and foodstuffs
Milk
The milk produced in the farms around the
Marcoule site is regularly analyzed for radioactivity: monthly cow’s milk samples aretaken in Pontet, and quarterly or annual
goat’s milk samples are taken at three farms
in Laudun-l’Ardoise, Roquemaure and SaintLaurent-des-Arbres.
Like the milk samples taken in zones considered as being unaffected by the site’s
releases, the highest level of activity is thatof potassium-40, whose mean activity concentration is 46.9 ± 1.4 Bq/L in cow’s milk
and 65.2 ± 3.7 Bq/L in goat’s milk.
A significant strontium-90 activity level has
been detected in the milk from Laudunl’Ardoise (0.044 ± 0.01 Bq/L): this is close to
the levels generally found in France as aresult of past atmospheric fallout from
nuclear weapons testing.
Lastly, the milk samples taken near the Marcoule center under the prevailing winds
show low levels of tritium activity, whichshould be viewed in relation to the site’s
releases.
The other artificial radionuclides’ activity
levels are below the decision thresholds(Table VI.15).
Cereals
No gamma-emitting radionuclides weredetected in the wheat sample taken in PontSaint-Esprit in 2010. The activity levels of
the artificial (gamma-emitting and transuranium (plutonium, americium and strontium-90)) radionuclides are below thedecision thresholds of the analytical techniques used.
Fruit and vegetables
Fruit samples are regularly taken north andsouth of the Marcoule site, in Chusclan and
Codolet. The frequency and type of thesesamples vary depending on the season andproduction (five or six samples per year). In
addition, four samples of fruit and vegetables grown within a 15 km radius of the sitewere analyzed in 2010. The main results areshown in Table VI.16.

Table VI.15 – Mean activities in the milk samples taken near the Marcoule site (Bq/L).

Laudunl’Ardoise

Le Pontet

RoquemaureSaint-Laurentdes-Arbres

Goat's milk

Cow’s milk

Goat's milk

Goat's milkK

64 ± 846.9 ± 1.4

65 ± 666 ± 6Cs< 0.39< 0.11

< 0.1

< 0.1

Cs

< 0.34nm< 0.07< 0.08I< 0.6< 0.14< 0.11< 0.1290

Sr0.046 ± 0.01

< 0.033

nm

nm

HTO

3.4 ± 0.6

4.3 ± 0.6nm

nm

Radionuclide

40

137

134

131

nm: not measured

Low strontium-90 activity levels of between
0.048 ± 0.041 Bq / kg wet and0.19 ± 0.07 Bq/kg wet were detected inthree fruit samples taken in the Chusclan
and Codolet municipalities. These levels areclose to those observed in zones outside theinfluence of any nuclear facilities.
The significant tritium activity levels
measured in the fruit and vegetable samples
indicate that concentration levels are due tothe Marcoule nuclear facilities’ atmosphericdischarge.

Wine
Analysis of red wine produced in Saint-Étienne-des-Sorts, which was conducted inorder to detect gamma-emitting radionuclides, revealed the presence of potassium-40 at an activity concentration of
34 ± 7 Bq/L. The main artificial radionuclides likely to be released by the Marcoulesite were not detected by the measuring
devices used.

 able VI.16 – Mean activities or ranges of activities measured in the fruit and vegetablesT
produced around the Marcoule site (Bq/kg wet).

Chusclan

CodoletLaudun- l’Ardoise

Orange Sauveterre

PontSaintEsprit

Fruit

Fruit

CabbageApple

LettuceAppleK

39 ± 6/140 ± 2248 ± 7/130 ± 2077 ± 941 ± 7133 ± 1742 ± 7Cs< 0.029< 0.03< 0.026< 0.07< 0.11< 0.03990Sr

0.1 ± 0.07/
0.19 ± 0.07

0.048 ±
0.041

nm

nm

nm

nm

HTO

20 ± 3.6/64 ± 64.8 ± 3.9/61 ± 6nm

nm

4.8 ± 1.9

nm

OBT

nm

nm

nm

nm

0.328 ±
0.017

nm

C

6.2 ± 1.7/
19 ± 102.7 ± 1/
9 ± 2.4

nm

nm

nm

nm

Radionuclide

40

137

14

nm: not measured

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

231

Monitoring of Research Centers and Nuclear Naval Bases

Continental aquaticcompartment

Sediments
Monthly or annual sediment samples aretaken at ten monitoring stations along the
Rhône river, from Saint-Étienne-des-Sorts
upstream of the site down to the mouth of
the Rhône at Port-Saint-Louis. The main
results are shown in Table VI.17.

Surface water
IRSN possesses all tritium activity measurements taken in the Rhône river’s water both
upstream and downstream of the Marcoulesite since the 1970s (Figure VI.35). The trend
shows that activity levels are decreasing,notably at the end of the 1990s. Tritium
concentrations in the Rhône river as a resultof the Marcoule site’s activities, which canbe measured by the ratio between theactivities upstream and downstream of thesite, was occasionally detected in the 1980s
and 1990s. The historical mean ratio is,however, 1 (Figure VI.36).

Upstream of the Marcoule site (at Saint-Étienne-des-Sorts), only cesium-137 wasdetected in the sediments in 2010, at an
activity level of 0.81 ± 0.34 Bq/kg dry.
Downstream, several artificial radionuclides(137Cs, 60Co, 54Mn, 241Am, 238Pu, 239Pu, 239+240Pu
and 90Sr) were detected in the sediments.
Cesium-137 is systematically detected in all
samples, at higher levels than the other radionuclides, mainly at the Codolet (30 ± 6 Bq/
kg dry) and Avignon (14.5 ± 3.2 Bq/kg dry)monitoring stations. Although concentrationlevels due to the site’s legacy discharge cannot be excluded in the case of this radionuclide, its presence is mainly due to past
atmospheric fallout.

Bq/L

90
80
70
60
50
40
30
20
10

0
1971 1974 1977 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 2010
Rhône upstream of site

Rhône downstream of site

Detection limitF igure VI.35 – Tritium activity in Rhône river water samples taken upstream
and downstream of the Marcoule site (Bq/L).

1.6
1.4
1.2
1
0.8

Traces of transuranium radionuclides(mainly americium-241, plutonium-239 andplutonium-240), which are primarily linked
with the Marcoule site’s past discharge, aredetected as far away as the mouth of the
Rhône, at the Port-Saint-Louis monitoring
station. The sediment samples with thehighest transuranium radionuclide activities(1.05 ± 0.24 Bq/kg dry in the case of 241Am,
and 0.49 ± 0.13 Bq/kg dry in the case of
239+240Pu) are those taken at Codolet, themonitoring station nearest the Marcoulesite’s liquid discharge point. Plutonium-238
is occasionally detected at the Roquemaureand Avignon monitoring stations: the238 Pu/ 239+240 Pu activity ratio of approximately 0.5 is typical of civilian spent fuel(that of atmospheric fallout from nuclear
weapons testing in the ’60s is approximately 0.025).

0.6
0.4
0.2

74
19
76
19
78
19
80
19
82
19
84
19
86
19
88
19
90
19
92
19
94
19
96
19
98
20
00
20
02
20
04
20
06
20
08
20
10

19

19

66

0

Figure VI.36 – Ratio of tritium activities downstream/upstream of the Marcoule site.

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IRSN – Report on the Radiological State of the Environment in France in 2010–2011

Some cobalt-60, mainly linked with the
Marcoule site’s past discharge, is detected
between Orange and Avignon, at activity
levels of between 0.63 ± 0.16 Bq/kg dry and2.6 ± 0.6 Bq/kg dry. Traces of manganese-54
and strontium-90 are also occasionallydetected in Roquemaure, at activity levelsof 0.38 ± 0.22 Bq / kg dry and0.84 ± 0.14 Bq/kg dry, respectively.

VI.1
Table VI.17 – Mean activities measured in the Rhône sediment samples taken upstream and downstream of the Marcoule site (Bq/kg dry).

Radionuclide

Saint-Étienne-desSorts
Upstream – 6 km

CodoletDownstream– 3 kmOrangeDownstream– 10 km

RoquemaureDownstream– 13 kmAvignonDownstream– 25 km

Port-Saint-Louis-duRhône
Downstream – 100 km

Cs

0.81 ± 0.34

30 ± 6

4.83 ± 0.28

5.85 ± 0.32

14.5 ± 3.2

9.7 ± 2.5

Co

< 0.46<1

0.47 ± 0.08

0.68 ± 0.07

1.39 ± 0.44

< 0.6

Mn

< 0.43< 0.9

nm0.43 ± 0.07

< 0.8

< 0.6

40

K

510 ± 70690 ± 90460 ± 23457 ± 19540 ± 80490 ± 70

Other
gamma-emitters(124Sb, 125Sb,
110mAg, 134Cs,
58Co, 106Ru)

<7

< 15

<5

<6

< 10

<9

Pu

< 0.06< 0.07< 0.140.061 ± 0.012

0.12 ± 0.07

< 0.07Pu

nm

nm< 0.43

nm

nm

nm

Pu

< 0.050.49 ± 0.13

nm

0.088 ± 0.017

0.33 ± 0.11

0.13 ± 0.08

Am

< 0.061.05 ± 0.24

< 0.330.078 ± 0.016

0.37 ± 0.12

0.2 ± 0.09

Sr

< 0.36

< 0.3

< 4.3

0.162 ± 0.037< 0.42< 0.44

137

60

54

238

239

239+240241

90

nm: not measured

Ground water

The ground water flows in the Rhône river’s
alluvium, consisting of highly permeable
sands and gravels, at a speed of approximately 1 meter/day. The alluvium forms
successive terraces whose altitude decreases
southwards. The impermeable substratum
consists of Pliocene blue marls whose surface has been shaped through river erosion,
forming channels and cuestas. This morphology considerably affects the subterranean
flows, due to the layer’s general thinness. As
a result, although the ground water generally flows southwards towards the Codolet
plain, it sometimes flows eastwards or westwards locally, notably as a result of thechannels and cuestas.
The different levels have tritium concentrations, whose measured activity levels at agiven point show little variation (Figure VI.37). The activity ranges from a few
Bq/L to approximately 200 Bq/L between
sampling points, however.

Bq/L
250

200

150

100

50

0
Nov.-09

Jan.-10

Mar.-10 May-10

CE1
F211

CE2
F213

CR1
F215

CR2
F223B

Jul.-10F050
F285

Sept.-10 Nov.-10
F115B
P12

F195
P13

Jan.-11
F196B
P15

Mar.-11 May-11

F197
P53

F205B
P92

F igure VI.37 – Tritium activity in the ground water rainwater samples taken on and near the
Marcoule site (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

233

Monitoring of Research Centers and Nuclear Naval Bases

An increase in the total alpha activity wasobserved in March 2011 at the ground water
sampling point named “MAR/EAU/F115B”,
reaching levels of over 0.5 Bq/L (Figure VI.38). The ground water flows from
north to south in this zone and collects
water with uranium concentrations from the
nearby Tourettes spring. These concentrations are the residue from old incidents inthe uranyl nitrate disposal zone, as theresults of the analyses conducted by CEA
show (Table VI.18).
The “MAR/EAU/F213” monitoring point
south of the Marcoule site’s waste processing station has residual gross beta activity(Figure VI.39). This residual activity is linked
with the zone’s total concentration levels
due to several previous incidents on the site.

 able VI.18 – Results of supplementary analyses conducted by CEA onT
old concentrations in the uranyl nitrate disposal zone (Bq/L).

Activity (Bq/L)

Radionuclide

April 2011

May 2011

Total alpha

0.54

0.60

U

0.25

0.41

U

0.02

< 0.02

U

0.28

0.50

Pu

< 0.003< 0.004

Pu + 241Am< 0.009< 0.010

234
235
238
239
238

0.8

Bq/L

0.7
0.6
0.5

Continental aquatic fauna

0.4

Fish are caught monthly in the Rhône near
the Marcoule site. The results of their radiological analysis are shown in Table VI.19. In
addition to cesium-137, which is regularly
detected at a mean activity level of
0.227 ± 0.035 Bq/kg wet, the samples occasionally have significant strontium-90 activity levels (between 0,059 ± 0.046 Bq/kg wet
and 0.4 ± 0.15 Bq/kg wet) and carbon-14
activity levels (a mean activity level of
89 ± 13 Bq/kg wet). The measured tritium
levels show the Rhône river’s concentrationlevels are due to the discharge from the
Marcoule site and, to a lesser degree, thoseof the other nuclear facilities upstream.

0.3
0.2
0.1
0
.-09 eb.-10 pr.-10
FA
Dec-10 Jul.-10 pt.-10 ov.-10 an.-11 ar.-11 ay-11 Jul.-11 pt.-11 ov.-11
Jun
J
M
M
N
N
Se
Se

Significant value (> DT)

Decision thresholdF igure VI.38 – Gross alpha activity in the ground water samples taken at point “MAR/EAU/F115B”
on the Marcoule site (Bq/L).
Bq/L
1.8

1.6
1.4
1.2

 able VI.19 – Mean activity level measured inT
the fish caught in the immediate vicinity of the
Marcoule site (Bq/kg wet).

0.8Radionuclide

Fish

0.6

K

97.6 ± 4.5

0.4

137

Cs

0.227 ± 0.035

0.2

134

Cs

< 0.09

0

Ru

< 1.3

Sr

0.081 ± 0.013

.-09
Dec

90

HTO

32 ± 3.5

C

89 ± 13

40

106

14

234

1

.-10
Feb

.-10
Apr

Significant value (> DT)

-10
Jun

10
Jul.-

0
t.-1
Sep

0
v.-1
No

.-11
Jan

1
r.-1
Ma

1
y-1
Ma

Decision thresholdF igure VI.39 – Gross beta activity in the ground water samples taken at point “MAR/EAU/F213”
south of the Marcoule site waste processing station (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Continental aquatic flora
Aquatic plant samples are taken upstream(twice yearly at Saint-Étienne-des-Sorts)
and downstream of the Marcoule site(monthly at Caderousse, and twice yearly at
Codolet) (Table VI.20).
As well as the usual presence of potassium-40, analysis also reveals the presenceof traces of artificial radionuclides such as
cesium-137 both upstream and downstream of the site. These traces can mainly
be attributed both to past atmospheric fallout from nuclear weapons testing and to
the Chernobyl accident.
The samples taken downstream of the site
show traces of plutonium-238 and plutonium-239+240 activity as well of americium-241 activity, which are higher thanthose taken upstream, suggesting that theplants have activity concentrations resulting
from the site’s authorized discharge. Thisfinding is not applicable to strontium, whose
upstream and downstream activity levels
are identical.
The tritium levels found in the aquatic
phanerogams are higher than those usuallyobserved in zones outside the influence ofany nuclear activities. The samples taken
downstream show slightly higher activity
levels than those observed upstream,s u g ge s t i n g t h a t t h ey h ave a d d e dconcentrations due to the Marcoule site’sdischarge as well as by the liquid discharge
from the nuclear power plants upstream ofthe site on the Rhône river (Chapter V –Rhône Valley NPPs).

 able VI.20 – Mean activities measured in the aquatic phanerogam samples taken upT
stream and downstream of the Marcoule site (Bq/kg dry)*.

Saint-Étienne-des-Sorts
Upstream of Marcoule –6 km

CodoletDownstream of Marcoule– 3 kmCaderousse
Downstreamof Marcoule– 5 kmPondweed

Pondweed

Phanerogam

Radionuclide

Cs

137

May 2010
sampleNovember2010 sample

May 2010
sampleNovember
2010
sampleAnnualmean< 0.8

1.9 ± 1

1.6 ± 0.7

26.7 ± 3.7

0.66 ± 0.15

I

6±3

<8

< 3.3

< 40

nm

40

K

720 ± 100

480 ± 60

1100 ± 140

810 ± 110638 ± 24

Other
gamma
emitters(124Sb, 125Sb,
110mAg,
134Cs, 58Co,
60Co, 54Mn,
106Ru)

< 14

< 18

< 30

< 33

<8

Pu

< 0.007< 0.021< 0.0220.181 ±
0.044

nm

Pu

0.013 ±
0.008

0.038 ± 0.017

0.101 ±
0.023

1.62 ± 0.18

nm

Am

< 0.0130.035 ± 0.021

0.092 ±
0.038

0.048 ±
0.031

nm

Sr

1.06 ± 0.18

nm

1.23 ± 0.22

nm

1.05 ± 0.24

U

4.78 ± 0.43

7.5 ± 1.1

nm

nm

nm

U

0.31 ± 0.05

0.62 ± 0.14

nm

nm

nm

238

U

4.64 ± 0.42

7.2 ± 1

nm

nm

nm

HTO
(Bq/kg wet)

3.4 ± 1.7< 3.7

4.5 ± 1.3

8.4 ± 1.9

8.4 ± 3.4

131

238

239+240

241

90

234
235

OBT

nm

nm

nm

41.5 ± 2.1

nm

C

nm

nm

nm

nm

220 ± 70

14

* Unless specified otherwise
nm: not measured© Leprieur/IRSN

Iodine-131 was detected upstream of the
Marcoule site in May 2010. Its presence wasmainly due to chronic discharge from thenuclear medicine centers.

Figure VI.40 – Taking aquatic plant samples downstream of the Marcoule site.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

235

Monitoring of Research Centers and Nuclear Naval Bases

Saclay site
The Saclay CEA center, which is located in
the Paris region and whose first facilities
began operation in 1952, conducts multidisciplinary research in widely varied activities
ranging from fundamental research toapplied research in the fields of nuclear
energy, physical sciences, life sciences, climate and the environment, technologicalresearch and education.
The center’s main discharge is produced by
the organic molecule concentrationlaboratory’s experimental Osiris and Orphée
reactors as well as by “CIS bio international”,
an independent company manufacturing
radiopharmaceuticals for use in nuclear
medicine.

LegendWater
Built-up areas andbusiness parks
Forest and farmland

kilometers

Figure VI.41 – Geographical location of the Saclay site.

7,114

CEA
IRSN
ASN

1,231

22

5,936

363
AtmosphericContinental aquatic
Terrestrial

Figure VI.42 – Saclay site: sample distribution by data producer and by compartment.

236

2,068

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VI.1
Atmospheric compartment
Atmospheric aerosols
 able VI.21 – Activity levels in the atmospheric aerosol samples taken in the Saclay site’sTenvironment (mBq/m3).

Apart from the readings taken during theperiod of the Fukushima accident, no otherabnormal beta activity index values(Figure VI.14) and alpha activity index values(Figure VI.15) have been detected. No
artificial radionuclides have been detectedin the environment by means of gamma
spectrometry.
In the Saclay CEA site’s environment, an
increase in the beta activity index was
observed between the end of March and theend of April 2011 (Table VI.21). This phenomenon is mainly due to the presence ofartificial radionuclides linked with theatmospheric fallout from the Fukushima
nuclear power plant accident.
Gases sampled by bubblers
Atmospheric tritium activity levels aremeasured by means of bubblers at fourmonitoring stations near the site: Saclay,
Saint-Aubin, Villiers-le-Bâcle and Orsigny.
In 2010, the tritium activity concentration
measured at these four stations was usually
below the decision threshold (< 0.4 Bq/m3).
The maximum measured value was
1.155 ± 0.082 Bq/m3 (Figure VI.43). Whentritium is detected around the Saclay center,it comes from the molecule concentration
research laboratories.

Radionuclide type

Mean activity or detection
limit (mBq/m3)

Alpha activity

0.021 ± 0.001

Beta activity

0.24 ± 0.01
0.65 ± 0.02*

Gross activity indices* Measurements taken during the period of the Fukushima nuclear power plant accident
between March 22 and May 6, 2011.

1.4

Bq/m3

1.2
1
0.8
0.6
0.4
0.2
0
Jan.-10

Mar.-10May-10Significant activity (> DT)

Other gases
The monitoring of gaseous iodine-131
activity revealed the presence of this radionuclide during the period of the Fukushima
nuclear power plant accident (Table VI.9).
Except during this period, no significant
activity levels have been measured.
Although iodine-131 is present in CIS bio
international’s gas discharge, it is rarely present in discharge from Saclay CEA center’sfacilities.

Radionuclide

Jul.-10

Sept.-10

Nov.-10Jan.-11

Mar.-11May-11

Decision thresholdF igure VI.43 – Atmospheric tritium (HTO) activity measured in samples taken near the Saclay site
(Bq/m3).

Bq/L
12
10
8
6

Rainwater
4

Analysis of the rainwater samples taken
near the Saclay site occasionally shows thepresence of tritium linked with the center’sgas discharge (Figure VI.44).

20Nov.-09

Jan.-10

Mar.-10Significant activity (> DT)

May-10Jul.-10

Sept.-10

Nov.-10Jan.-11

Decision thresholdFigure VI.44 – Tritium activity in rainwater samples taken near the Saclay site (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011237

Monitoring of Research Centers and Nuclear Naval Bases

Terrestrial compartment

Soils

The effects of the Saclay site’s activity levelupon its nearby terrestrial environment aremonitored by means of regular soil, terrestrial plant (grass, fruit and vegetable), milk
and cereal samples.

The cesium-137 specific activity measured in the topsoil samples taken
in 2010 within the zone potentiallyaffected by the Saclay center’s discharge was 5.1 ± 0.8 Bq/kg dry, which isa similar value to that observed
throughout France. These concentrations can be attributed both to past
atmospheric fallout from nuclear weapons testing and to the Chernobyl accident.

Terrestrial floraMonthly grass samples are taken at four
sampling points within a 2 km radius of the
Saclay site. This monitoring is supplemented
by the taking of twice-yearly samples in
Saclay itself.
The analytical results of the grass samples
indicates the presence of tritium, which canbe attributed to discharge from the Saclay
center (Table VI.22), and strontium-90,
which can be attributed to past atmosphericfallout from nuclear weapons testing.
Normally, the activities of the other radionuclides are below the decision thresholds
associated with the measuring devices used.
Following the Fukushima nuclear power
plant accident in March 2011, however,traces of iodine-131 were detected in thefour samples taken on April 15, 2011, withactivity levels between 0.37 ± 0.13 and0.49 ± 0.11 Bq/kg wet. Cesium-134 andcesium-137 was also detected in SaintAubin and Villiers-le-Bâcle on the same day.
For more information
Chapter III – The Fukushima Accident

Agricultural production and foodstuffs
Milk
Analysis of the monthly cow’s milk samples taken at farms near the Saclay
center does not reveal any abnormal
artificial activity (Table VI.23). A single
significant free tritium value, which wasclose to the decision thresholds(3.5 ± 1.9 Bq/L), was observed among
the six milk samples taken in Jouy-enJosas between January 2010 and
May 2011.

April 1, 2011 contained traces ofiodine-131; its measured activity concentration of 0.08 ± 0.022 Bq/L can be
attributed to the Fukushima nuclear
power plant accident in Japan a few
weeks previously.
Cereals
No artificial gamma-emitting radionuclides
were measured in the wheat samples taken
in 2010 in Saclay.
Fruit and vegetables
The radioactivity observed in the plants
grown near the Saclay center is mainly due
to natural potassium-40 (Table VI.24).
The zucchini and raspberries picked in Jouyen-Josas contain tritium levels showing
added concentration levels due to the
Saclay center’s discharge.
Low strontium-90 activity levels have been
observed in the strawberries and wild rhubarb grown in Jouy-en-Josas; they are close
to the levels generally found in France andcan be attributed to past atmospheric fallout from nuclear weapons testing.

In addition, the milk sample taken at thefarm in Saint-Rémy-lès-Chevreuse on
Table VI.23 – Mean activities in the milk samples taken near the Saclay site (Bq/L).

Radionuclide

Jouy-en-Josas

Saint-Rémy-lès-ChevreuseK

52.2 ± 1.4

51.1 ± 1.4

Cs< 0.09

nm

40
137

I*

< 0.017< 0.01790

Sr< 0.018< 0.019HTO

2.6 ± 0.5

<4

OBT

< 25

< 34

131

* Excluding a significant value measured following the Fukushima accident in March 2011.
nm: not measured
Table VI.22 – Mean activities measured in the grass samples taken around the Saclay site (Bq/kg dry)*.

Radionuclide

SaclayOrsigny

Villiers-le-Bâcle

Saint-Aubin

K

530 ± 60744 ± 30792 ± 30683 ± 29849 ± 33

Cs**

< 0.8

< 0.41< 0.31

nm

nm

90

Sr

nm

0.53 ± 0.06

0.56 ± 0.08

0.47 ± 0.06

0.56 ± 0.06

HTO (Bq/kg wet)

28.4 ± 2.6< 2.5

6.7 ± 2.6< 3.4

3.9 ± 2.1

40
137

* Unless specified otherwise** Excludes significant values measured around the Saclay site following the Fukushima accident
nm: not measured

238

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
In addition, iodine-131 was detected in the cabbage samples taken on April 4, 2011 in Saclay,
with an activity of 0.29 ± 0.12 Bq/kg wet.
This activity should be viewed in relation to
the accident at the Fukushima nuclear
power plant in Japan in March 2011.
For more information
Chapter III – The Fukushima Accident

Table VI.24 – Activities measured in the fruit and vegetables produced near the Saclay site (Bq/kg dry).

SaclayRadionuclide

Jouy-en-Josas

Cabbage

Cauliflower

Zucchini

Strawberry

Raspberry

PumpkinWild rhubarb

TomatoK

131 ± 15100 ± 1558 ± 856 ± 1050 ± 7141 ±16124 ± 1574 ± 1090Sr< 0.05< 0.26< 0.090.11 ± 0.036

nm< 0.230.047 ± 0.013< 0.09

HTO

nm

nm

25 ± 6nm

5.2 ± 1.7

nm

nm

nm

OBT

nm

nm

< 10

nm

nm

nm

nm

nm

40

nm: not measured

Continental aquaticcompartment

10,000Surface water

1,000

The tritium detected by IRSN in the
Mineurs aqueduct since 1989 showsthat its activity is regularly decreasing,which is consistent with the reductionin the center’s authorized liquid discharge (Figure VI.45).

100

10

0
1989

1991

1993

1995

Significant activity (> DT)

1997

1998

2000

2002

2004

2006

2008

2010

Decision thresholdFigure VI.45 – Tritium activity in water samples from the Mineurs aqueduct (Bq/L).

© A. Chézière/CEA

IRSN has observed strontium-90 concentrations of approximately 4 mBq/L
in surface water in the Mineurs aqueduct (outlet) near the site and in the
nearby Étang Neuf and Étang Vieux
pools. This activity should be viewed inrelation to the center’s authorizedstrontium-90 discharge.

Bq/LF igure VI.46 – Taking a water sample from the Étang Vieux pool near the Saclay site, for radiologicaland physicochemical analysis.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011239

Monitoring of Research Centers and Nuclear Naval Bases

In the case of the artificial radionuclides,
analysis of the Mineurs aqueduct’s and the
Étang Vieux pool’s sediments has revealed
residual concentrations by cesium-137,
cobalt-60, plutonium and americium-241.
This can be attributed to the site’s past liquid discharge. The annual mean specificactivity of these radionuclides has considerably decreased since then. For example,
cesium-137 activity has been reduced by afactor of 100 since 1990.

Sediments
Twice-yearly or annual sediment samples
are taken at seven monitoring stations near
the Saclay center. This monitoring includes
the taking of sediment samples in the
Mineurs aqueduct, through which the Saclay
center's liquid discharge flows; and in the
Étang Vieux pool, the discharge’s receiving
environment. Table VI.25 shows the main
results obtained in 2010.

This concentration level is no longer
observed in the Étang Neuf pool or theother watercourses further away (Ru de
Vauhallan brook, La Bièvre stream and Ru deSaint-Marc brook).

 able VI.25 – Mean activities measured in the sediment samples taken downstream of the Saclay site’s liquid waste discharge pipe and in theTneighboring watercourses (Bq/kg dry).

SaclayVauhallan

Verrières-le-Buisson

Toussus-le-Noble

Radionuclide

Mineurs
aqueduct

Mineurs
aqueduct

Étang Vieux
pool

Étang Neuf
pool

Vauhallan
streamLa Bièvre

SaclayaqueductK404 ± 37523 ± 37

480 ± 80605 ± 42384 ± 27340 ± 50460 ± 80Cs

55.6 ± 4.2

1.77 ± 0.34

74 ± 120.31 ± 0.18

0.53 ± 0.17

0.52 ± 0.21

7.9 ± 1.2Co

2.79 ± 0.47

< 0.32

1.9 ± 0.49

< 0.2

< 0.16< 0.21< 0.17

Sr

< 0.5

< 4.8

< 4.6

< 3.6

< 2.9

< 2.9

< 3.3

Am

0.24 ± 0.09

< 0.6

< 0.8

< 0.8

< 0.7

< 0.44

< 0.7

40
137
60

90
241

Pu

< 0.110.13 ± 0.05

0.36 ± 0.18

< 0.15< 0.33< 0.33< 0.26Pu

1.57 ± 0.33

0.25 ± 0.09

2.6 ± 0.7

< 0.2

< 0.33< 0.28< 0.39Unm

2.9 ± 1

< 3.5

< 3.4

nm

< 2.1

<3

238

239+240235

nm: not measured

Ground water© IRSN

There are two aquifer levels with added
tritium concentrations:• The deep aquifer of Fontainebleau sands,
which is 60 meters thick and lies on a relatively impermeable layer of marls rich inoyster fossils. The layer flows from north tosouth with outlets downstream of the site,
consisting of springs on the southern andwestern slopes of the Saclay plateau.
• The superficial aquifer consisting of millstone clays, on which perched layers are
resting, is situated in relatively impermeable sandy loam layers of varying depths
fed by rainfall and with no stable directionof flow.

Figure VI.47 – Taking sediment samples in the Étang Vieux pool near the Saclay CEA center.

240

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

The tritium activities measured by all of thepiezometers vary between the decisionthreshold and 180 Bq/L in the case of wellF44. The tritium activity in well F44 canfirstly be explained by water infiltrations
from the Villiers pool, and secondly by its
closeness to basic nuclear installation # 72,
where the center’s solid waste is stored(Figure VI.48).

VI.1

200

Bq/L

180
160
140
120
100
80
60
40
20
0
Jan.-10F1F32Mar.-10F15F33May-10
F2
F42

F19
F41

Jul.-10
F22
F43

F24
F44

Aug-10F26
F45

Oct.-10F27
F46

Dec.-10

F29
F47

F30
F48

Feb-11

Apr.-11F31
F49

F igure VI.48 – Tritium activity in the Fontainebleau sand ground water samples taken
on and near the Saclay site (Bq/L).

Continental aquatic fauna able VI.27 – Activities measured in the reed samples taken downstream of the Saclay site’s liquidTwaste discharge pipe (Bq/kg dry)*.

In 2010, pike were caught in Saclay's Étang
Neuf pool for radiological analysis. The main
results are shown in Table VI.26.

Radionuclide

Mineurs
aqueduct

Étang Vieux pool

Étang Neuf poolK

950 ± 150

800 ± 140940 ± 160

Cs

10 ± 3

< 0.8

< 0.9

Co

< 2.1

< 1.1

< 1.1

Other gamma-emitting
radionuclides(106Ru, 110mAg, 124Sb, 125Sb, 131I,
134Cs, 54Mn, 58Co)

< 36

nm

nm

Sr

nm

< 1.1

< 1.5

Pu

0.022 ± 0.011

nm

nm

Pu

0.118 ± 0.026

nm

nm

Am

0.108 ± 0.027

nm

nm

40

The free tritium activity in these fish, which
was slightly above the decision thresholds,
can be attributed to the Saclay research
center’s activities.
 able VI.26 – Activities measured in the pikeTsamples caught in the Étang Neuf pool (Bq/kg wet).

137

60

90

Radionuclide

ActivityK

140 ± 21238

Cs

0.56 ± 0.16

239+240Co< 0.1190

Sr< 0.29HTO

6.9 ± 3.5

HTO (Bq/kg wet)

14.3 ± 2.1

4.7 ± 2.5

2.8 ± 2.6

OBT

< 36

OBT

nm

< 410

< 480

40
137
60

241

Continental aquatic flora* Unless specified otherwise
nm: not measured

The annual reed samples taken in the
Mineurs aqueduct downstream of Saclay’sliquid waste discharge pipe contain residual
concentrations from the research center’s
past discharge: they contain traces of americium and plutonium and cesium-137 isotopes, as well as a slight concentration oftritium (Table VI.27).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

241

Monitoring of Research Centers and Nuclear Naval Bases

Valduc CEA center
The Valduc center, which was created in1957 and is situated 45 km northwest of
Dijon in eastern France, specializes exclusively in conducting technological researchand development on the materials used in
France’s nuclear deterrent weapons. As wellas conducting research on the production of
the weapons’ nuclear components, the center’s specialists are also responsible for maintaining and dismantling the nuclear
warheads. Due to its specialized nuclear
weapons activities, this site mainly discharges, under regulatory control, gaseous
tritium (nearly 300 TBq in 2009).

kilometers

LegendRiversRoads
Built-up areas andbusiness parks
Forest and farmland

Figure VI.49 – Geographical location of the Valduc CEA site.

1,921

2,269

824

5
Acro
IRSN
CEA

171
AtmosphericContinental aquatic
Terrestrial

310

Figure VI.50 – Valduc CEA site: sample distribution by data producer and by compartment.

242

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Atmospheric compartment

Activity (mBq/m3)
4

Atmospheric aerosols
Fukushima accident

3

Apart from the readings taken during theperiod of the Fukushima accident, no otherabnormal alpha activity (Figure VI.52) andbeta activity values have been observed.
With the exception of natural radionuclides(7Be and 210Pb), gamma spectrometry has
not detected any artificial radionuclides present in the environment.
In the Valduc CEA site’s environment, an
increase in the beta activity index was
observed between the end of March and theend of April 2011 (Table VI.28 and Figure VI.51). These readings can be attributed
to air masses passing over France after being
contaminated by the Fukushima nuclear
power plant accident.
For more information
Chapter III – The Fukushima Accident

210Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)
Figure VI.51 – Time plot of the gross beta activity of aerosols near the Valduc CEA site (mBq/m3).

Activity (mBq/m3)
0.1

0.075

0.05

0.025

0
Jan.-10

Apr.-10
Measurement < DT

Jul.-10

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)F igure VI.52 – Time plot of the gross alpha activity of aerosols near the Valduc
CEA site (mBq/m3).

Table VI.28 – Activities in the aerosol samples taken in the Valduc CEA site’s environment (mBq/m3).
Radionuclide typeRadionuclide

Mean activity(mBq/m3)

Alpha activity

0.038 ± 0.001

Beta activity

0.23 ± 0.01
0.50 ± 0.02*

Gross activity* Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

243

Monitoring of Research Centers and Nuclear Naval Bases

A bubbler continuously samples the air at
the sampling station in Salives, under the
Valduc center’s prevailing winds. The atmospheric tritium is mainly detected in significant quantities in the form of water vapor.
This activity, which varies between the decision threshold and 4.15 Bq/m3, shows thatthe environment has permanent added concentrations due to the site’s atmosphericdischarge. The tritiated water vapor’s activity tends to be cyclical over time, with thehighest values appearing in the summer(Figure VI.53).

Bq/m3

5
4
3
2
1
0

Se
pt.
-07
De
c.07
Ma
r.-0
8
Jun
-08
Se
pt.
-08
De
c.08
Ma
r.-0
9
Jun
-09
Se
pt.
-09
De
c.09
Ma
r.-1
0
Jun
-10
Se
pt.
-10
De
c.10
Ma
r.-1
1
Jun
-11
Se
pt.
-11

Gases sampled by bubblers

Gaseous tritium

Rainwater
Rainwater samples are taken at four points
near the site. The tritium’s mean activity
concentration is approximately 23 Bq/L,
reflecting the site’s activity levels. During
the observation period, 4% of the values
were above 100 Bq/L, with a maximum
value of 353 Bq/L observed at Échalot(Figure VI.54).

Tritiated water vapor

Figure VI.53 – Atmospheric tritium activity measured near the Valduc site (Bq/m3).

400

Bq/L

350
300
250
200

Terrestrial compartment
The Valduc CEA center’s monitoring is basedon regular grass and milk samples taken in
the site’s immediate vicinity, combined withannual meat and cereal samples.
Terrestrial flora
Around the Valduc center, four monthly
grass samples are taken from April to October. These are supplemented by six annual
samples. Their analysis for the presence oftritium reveals that the grass has added concentration levels due to the center’s atmospheric discharge, as shown by the results
displayed in Table VI.29. The measured freetritium levels vary greatly over time andreflect the tritium’s activity levels in the airwhen the samples are taken. These levels
mainly depend on the activities discharged
by the nuclear research center and theweather conditions at the time.

150
100
50
0
Dec.-09

Feb.-10Échalot

Lery

Apr.-10

Jul.-10

Sept.-10

Nov.-10Jan.-11

Mar.-11

Salives

Moloy

Figure VI.54 – Tritium activity measured in rainwater near the Valduc site (Bq/L).
Table VI.29 – Activity levels measured in the grass samples taken around the Valduc site.

Sampling location

Range of HTO activities(Bq/kg wet)

Mean HTO activity(Bq/kg wet)

Mean OBT activity(Bq/kg dry)Échalot

9.9 ± 2.4 / 47.3 ± 4.3

23.1 ± 1

8.8 ± 0.7

Lamargelle

5.9 ± 2.1 / 79 ± 6

20.8 ± 1

nm

Le Meixnm

nm27.3 ± 1.2

Lery

nm

nm

21.3 ± 1

Minot

nm

nm

16.7 ± 0.9

Moloy

5 ± 2.3 / 55.2 ± 5

17.1 ± 0.9

nm

Pellerey

nm

nm

12.8 ± 0.7

Salives

6.1 ± 2.3 / 32.4 ± 3.6

15 ± 0.9

34.6 ± 1.4

nm: not measured244

jun-10IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.1
Agricultural production and foodstuffs
Milk
The monitoring of cow’s milk produced
around the Valduc center consists in analyzing monthly samples taken in Salives andannual samples taken in Lamargelle.
This analysis reveals that the milk has an
added concentration of tritium discharged
by the CEA center, notably in Salives where
the measured activity levels vary between
20.5 ± 2.9 Bq/L and 42 ± 3.8 Bq/L. The
activity concentration of the milk samples
taken in April 2010 in Lamargelle was
6.5 ± 2.1 Bq/L.
The other radionuclides’ activity levels are
below decision thresholds, apart from natural potassium-40, whose activity levels are
similar to those measured throughout
France (their mean is 49.4 ± 1.8 Bq/L).

Continental aquatic
activity
Surface water
Two aquifers flow below the Valduc site.
Below the site, the upper layer is fed throughrain infiltration and drained through many
barely productive springs, most of which aretemporary and situated on the edge of theplateau. The fissured lower aquifer, whose
outlets include the Douix spring (whichflows at a rate of several tens of liters per
second), contains a layer fed by rain infiltration and by the upper layer. The two aquifers
are connected by rifts in the Combe au Tilleul area.
IRSN measures the tritium activity in thisground water by taking samples at the out-lets, which mainly consist of the Coquille,
Galopine, Prégelan and Prélard springs andthe public water fountains in the surrounding villages. The added tritium concentration
measured at these points varies between 10
and 59 Bq/L.
The watercourses that flow northwards andeastwards under the CEA site’s prevailingwinds are the Brévon and the Digeanne,both of which flow into the Seine river. The
tritium activity levels of the water in theserivers is approximately 20 Bq/L, which is dueto the Valduc center’s atmospheric discharge and the ground water that has addedconcentrations of tritium. South of the site,
the Douix à Léry stream’s water, which
enters the upper reaches of the Seine, aremarked with tritium for the same reasons.
In addition, the tritium activity measured in
the Ignon river (25 Bq/L) is reduced due tothe dilution of the stream’s water. The Ignon
river is also fed by the Douix stream(27 Bq/L), which is in turn fed by the Noirveau stream (190 Bq/L). These watercourses
are the main vectors of surface drainage.
West of the site, sheltered from the prevailing winds, the tritium activity is considerably lower in the Prélard (7 Bq/L), Revinson(4 Bq/L) and Seine (4 Bq/L) rivers.

© IRSN

Meat
Analysis of beef from cattle reared in nearby
Chanceaux has not revealed any radiological anomalies. Organically bound tritium(OBT) was measured with a specific activityof 0.52 ± 0.16 Bq/kg wet.

Cereals
In 2010, wheat samples were taken from
Salives' annual harvest. With the exceptionof potassium-40, the gamma-emitting radionuclides’ specific activity levels were below
the decision thresholds of the measuring
devices used. These samples show an addedconcentration of OBT reflecting the Valduc
center’s atmospheric discharge (measured
specific activity: 55.2 ± 2.8 Bq/kg dry).

F igure VI.55 – Taking a water sample at the La Coquille spring in Etalante.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

245

Monitoring of Research Centers and Nuclear Naval Bases

Institut Laue-Langevininternational research
center and Grenoble
CEA center
The Grenoble CEA and Institut Laue-Langevin (ILL) research centers are located very
close together in the Grenoble agglomeration in eastern France.
The Grenoble CEA center, which was createdin 1956, is one of CEA’s civilian sites. Since

January 2001, it has been engaged in a project to clean up and dismantle its six basic
nuclear installations. Their dismantling is due
for completion at the end of 2012, and thefinal installation is scheduled for administrative decommissioning in 2013. This center’s
activities now concentrate on microelectronics and nanoelectronics, new energy
technologies and biotechnologies.
Institut Laue-Langevin (ILL) is an international research center offering researchers
one of the most intense neutron sources inLegendMunicipalities
Highways
Main roads
Business parks
Built-up areas
Meadows
ForestRock, scree
Water

kilometers

Figure VI.56 – Geographical location of ILL and the Grenoble CEA center.
2,981

173

1,522

20
Acro
IRSN
ILL-CEA

1,538

114
AtmosphericContinental aquatic
Terrestrial

Figure VI.57 – ILL and the Grenoble CEA center: sample distribution by data producer and bycompartment.

246

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

the world. The center has 40 state-of-theart spectrometers providing information on
the material’s structure and dynamics (solid,
liquid, gas, etc.), and its research covers avariety of fields: particle physics, nuclear
physics, chemistry, biosciences, materialsciences, etc.
Since 2010, ILL has been responsible for theenvironmental monitoring conducted atboth sites.

VI.1
Atmospheric compartment

Activity (mBq/m3)
4

Atmospheric aerosols

Fukushima accident

3

Apart from the readings taken during theperiod of the Fukushima accident, the monitoring of beta activity indices has notmeasured any abnormal values. No artificial
gamma-emitting radionuclide activity levels
above the decision thresholds of the measuring devices used could be detected.
In the Grenoble CEA site’s and ILL’s
environment, significant cesium‑137 andiodine‑131 activity levels were observed
between the end of March and the
beginning of May 2011 (Table VI.30). Thesefindings can be attributed to air masses
p a s s i n g o v e r Fra n c e a f t e r b e i n gcontaminated by the Fukushima nuclear
power plant accident. An increase in the
gross beta activity between the end of
March and the end of April 2011 has also
been observed (Figure VI.58). This can be
attributed to the presence of artificial
radionuclides linked with the Fukushima
accident.
For more information
Chapter III – The Fukushima Accident
Gases sampled by bubblers
Two bubblers continuously sample the air,
one at a station located at the point where
the Drac and Isère rivers meet northwest of
the site, and the other southeast of the site.
Both these stations are located under theprevailing winds. The atmospheric tritium ismainly detected in significant quantities in
the form of water vapor. The maximum
activity levels measured at the stations areapproximately 1 Bq/m3 southwest of the siteand 2.3 Bq/m 3 at the northwest station(Figure VI.59).

2

1

0

Jan.-10The monitoring of gaseous iodine-131
activity has revealed the presence of thisradionuclide during the Fukushima nuclear
power plant accident (Table VI.31).
For more information
Chapter III – The Fukushima Accident
Except during this period, no significant
activity has been measured, as there is very
little of this radionuclide in the discharge
from the Grenoble CEA center’s and ILL’s
facilities.

Oct.-10Jan.-11

Apr.-11Significant measurement (> DT)F igure VI.58 – Time plot of the gross beta activity of aerosols near ILL and theGrenoble CEA site (mBq/m3).
Table VI.30 – Activity levels measured in the Grenoble CEA center’s and ILL’s environmental
aerosols (mBq/m3).

Radionuclide typeRadionuclide

Mean activity (mBq/m3)

Gross activity

Beta activity

0.37 ± 0.01
0.64 ± 0.01*

Cesium-137

0.026 ± 0.008*

Iodine-131

0.042 ± 0.011*

Artificial radionuclides** Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

4.5

Bq/m3

4
3.5
3
2.5
2
1.5
1
0.5
0

0
Jun-1

0
0
0
0
0
0
Jul.-1 Aug-1 Sept.-1 Oct.-1 Nov.-1 Dec.-1

SE station

Other gases

Jul.-10

Apr.-10

NW station

11
11 ay-11
11 eb.-11
Jan.F
M
Mar.- Apr.-

Decision thresholdFigure VI.59 – Atmospheric tritium activity measured near ILL (Bq/m3).

 able VI.31 – Gaseous iodine-131 activity measured in the ambient air near the Grenoble CEAT
center and ILL’s reactor (mBq/m3).

Radionuclide typeRadionuclide

Mean activity or decisionthreshold (mBq/m3)

Artificial gaseous radionuclide

Iodine-131< 0.300.29 ± 0.04** Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

247

Monitoring of Research Centers and Nuclear Naval Bases

Rainwater
Tritium is regularly measured in the
rainwater samples taken near the ILL site
(Figure VI.60), where the atmosphericconditions are greatly influenced by theIsère river’s transverse valley. The tritium’s
mean activity is 4.3 Bq/L. It should be notedthat a higher tritium activity level was
occasionally observed in March 2011, in
both rainwater and air.

45

Bq/L

40
35
30
25
20
15
10
5
0

ILL also measured an iodine-131 activity
concentration of 1.3 Bq/L, linked with the
Fukushima accident, in a rainwater sample
taken at the end of March 2011.

Terrestrial compartment
The CEA center’s and ILL’s environment ismonitored by means of monthly or annual
terrestrial plant, milk and cereal samples.
Terrestrial flora
The monthly grass samples taken from May
to October 2010 near the Grenoble sites
showed an added concentration of tritium,
the measured activity levels varying
between 0.7 ± 0.61 Bq / kg wet and13.9 ± 1.1 Bq/kg wet for Grenoble andbetween 1.28 ± 0.49 Bq/ kg wet and9.5 ± 1.2 Bq/kg wet for Saint-Martind’Hères. This added concentration can be
attributed to ILL’s atmospheric discharge.
From March 23 to April 9, 2011, additional
samples were taken in Varces-Allières-etRisset and Gières. The additional samples
were found to contain traces of iodine-131,
with specific activities varying between
0.6 ± 0.2 Bq/kg wet and 1.6 ± 0.4 Bq/kg
wet. These can be attributed to the Fukushima nuclear power plant accident inMarch 2011.
For more information
Chapter III – The Fukushima Accident
Agricultural production and foodstuffs
Milk
Analysis of the monthly cow’s milk samples
taken in a farm in Proveysieux has provided
the results shown in Table VI.32. Free tritium,
which can be attributed to ILL’s atmosphericdischarge, is regularly measured withactivity levels close to the decisionthresholds.

248

Nov.-09

Jan.-10 Mar.-10 May-10

SE station

Jul.-10 Sept.-10 Nov.-10

NW station

Jan.-11 Mar.-11 May-11

Jul.-11

Decision thresholdFigure VI.60 – Tritium activity in rainwater samples taken near ILL (Bq/L).

Cereals
No gamma-emitting radionuclides likely
to be released by Grenoble’s nuclear
facilities have been detected in thewheat samples taken in Buisse.
The free tritium activity of the maize
harvested in Voreppe is 4 ± 0.6 Bq/kg
wet, which is close to the decisionthresholds. This can be attributed to ILL’s
atmospheric discharge.
Leafy vegetables
In 2010, annual samples of Swiss chards
and lettuce grown near the Grenoble
CEA center and ILL were taken.
Analysis of the Swiss chards has notrevealed any abnormal artificial activity.
The measured radioactivity is mainly
due to natural potassium-40, whose
activity is 96 ± 12 Bq/kg wet.
Low free tritium activity levels linked
with ILL’s discharge have been measured
in the lettuce sample (its specificactivity is 4.1 ± 1.7 Bq/kg wet). This
sample’s carbon-14 activity level is
220 ± 50 Bq/kg of carbon, the value
usually observed in zones outside the able VI.32 – Mean activity levels measured inTmilk samples taken from cows reared near the
Grenoble CEA site (Bq/L)*.

Radionuclide

Activity (Bq/L)

K

48.1 ± 1.2

Cs< 0.05HTO

2.32 ± 0.31

40
137

* Unless specified otherwise

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

influence of any anthropic discharge(230 Bq / kg of carbon), to within
uncertainty.

Continental aquaticcompartment
Surface water
ILL’s liquid radioactive waste and storm
water are discharged, after checking, into
the Isère river 1 km upstream of the point
where it joins the Drac, which flows into theleft side of the Isère. The cooling water isdischarged into the Drac 1 km upstream ofthe point where it joins the Isère. The waste
water produced by ILL is discharged into themunicipal drain for processing by Grenoble’s
municipal water treatment plant.
Analysis of the data shows that ILL does nothave a significant influence on the radionuclide levels measured in the Isère or the Drac,
as the tritium activity levels measured
upstream and downstream of the facility areroughly equal at approximately 2.5 Bq/L
(Figure VI.61).
Sediments
Sediment samples are taken in the Isèreriver at two points: annually, immediately
downstream of ILL, and three times a year
at the Saint-Égrève dam downstream fromthe Grenoble CEA center. The main results
are shown in Table VI.33.

VI.1
4.5

Bq/L

Continental aquatic flora

4
3.5
3
2.5
2
1.5
1
0.5
0
Nov.-09

Mar.-10 May-10

Jan.-10Drac upstream

Jul.-10

Decision threshold

Sept.-10 Nov.-10

Jan.-11

Isère downstream

Mar.-11 May-11

Isère upstream

In 2010, ILL began taking annual reed samples in the Isère river, 11 km downstream of
the facility. Of all the radionuclides likely to
be discharged by Grenoble’s nuclear facilities, only carbon-14 is detected with a specific activity of 320 ± 140 Bq/kg of carbon.
Given the associated uncertainty, this measurement is difficult to interpret even though
it is higher than the current backgroundradiation in terrestrial environments(230 Bq/kg of carbon).

F igure VI.61 – Tritium activity in surface water samples taken upstream anddownstream of ILL (Bq/L).
Table VI.33 – Activity levels measured in the sediment samples taken in the Isère river downstreamof ILL in Grenoble (Bq/kg dry).

Radionuclide

Grenoble

Sassenage
At Saint-Égrève dam

Cs

7.8 ± 1.7

5.9 ± 0.8

Other gamma-emitting radionuclides (124Sb, 125Sb, 110mAg, 134Cs,
54Mn, 58Co, 60Co, 106Ru)

nm

< 11

Am

nm

0.087 ± 0.032

Pu

nm< 0.06Pu

nm0.16 ± 0.06

137

241

238

239+240

Cesium-137 is found in all of the samples,at levels comparable to those measured in
the Rhône river, outside the influence of
nuclear facilities' discharge. Its presence in
the Isère downstream from Grenoble’s
nuclear facilities is therefore mainly due topast atmospheric fallout (the Chernobyl
accident and nuclear weapons testing).
Tra c e s o f a r t i f i c i a l t ra n s u ra n i u mradionuclides (241Am and 239+240Pu) due tofallout from nuclear weapons testing arealso regularly detected.

Continental aquatic fauna
In 2010, low cesium-137 activity levels were
measured in the annual fish samples takenin the Isère river near Grenoble’s nuclear
sites (0.063 ± 0.013 Bq/kg wet). The othergamma-emitting radionuclides likely to bedischarged by these facilities remained
below the decision thresholds of themeasuring devices used.

Ground water
ILL is located on the Grenoble alluvial plain,
which is completely flat. Its flatness is dueto the flow of the Isère glacier, with the
Drac’s ice flowing through the Isère’s transverse valley. The ground water is generally
close to the surface.
ILL monitors the layer’s radioactivity using
three piezometer networks whose mediantritium concentration is approximately
2.5 Bq/L, with a maximum value of 5.2 Bq/L
measured in November 2010 (Figure VI.62).
These values should be viewed in relation to
those measured in the Isère, which are of asimilar size.

6

Bq/L

5
4
3
2
1
0

Nov.-09

Jan.-10

Mar.-10

ILL piezometers

May-10Jul.-10

CEA piezometers

Sept.-10

Nov.-10CNRS piezometers

Jan.-11

Mar.-11 May-11

Decision thresholdFigure VI.62 – Tritium activity in ground water near the ILL site (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011249

Monitoring of Research Centers and Nuclear Naval Bases

VI.2 Nuclear naval
bases
Four of France’s military ports house naval
nuclear bases. These nuclear facilities are allin or near major urban areas (Toulon, Brest
and Cherbourg). In addition, these ports
open onto bays with fragile ecosystems. Like
all facilities, the French navy has its own laboratories specializing in radiological monitoring that take ground, atmospheric andmarine samples in the port area and analyze
them.
Note: the results of the marine aquaticcompartment (sea water, sediments, andmarine fauna and flora) are presented in
Chapter IV (“Coast”).

3,422

1,223

Brest and Île-Longue
military ports

Atmospheric compartment
Atmospheric aerosols

Brest military port, in northwestern France,is the base of the French Atlantic Squadronand Strategic Oceanic Force (FOST) andFrance’s nuclear-powered attack submarines. Ever since France’s nuclear-poweredballistic missile submarines (SNLE) cameinto existence in 1970, they have also been
based at Île Longue submarine base. Whenever an nuclear submarin returns to the baseafter a patrol, it is withdrawn from operation for several weeks of maintenance. The
main mission of Île Longue, however, consists in fitting each submarin with its sixteen
intercontinental missiles (each of which can
carry six nuclear warheads) when it has justbeen built in Cherbourg or after a twoyearly major refit in Brest.

1,435

1,573

Apart from the readings taken during theperiod of the Fukushima accident, the monitoring of beta activity levels (Figure VI.65)
has not revealed any abnormal values. The
gamma spectrometry measurements haveshown that, with the exception of naturalradionuclides (7Be, 210Pb, 228Ac and 235U), no
artificial radionuclides were present in theenvironment.
In the Brest military port’s environment, significant cesium‑134, cesium‑137 andiodine‑131 activity levels were observed
between the end of March and the beginning of May 2011 (Table VI.34). These findings can be attributed to air masses passing
over France after being contaminated by the
Fukushima nuclear power plant accident. An
increase in the gross beta activity between
the end of March and the end of April 2011
was also observed (Tables VI.34 and VI.35,
and Figure VI.65). This can be attributed tothe presence of artificial radionuclides linked
with the Fukushima accident.
For more information
Chapter III – The Fukushima Accident
Rainwater
Traces of lead-212 and lead-214 alone areoccasionally measured in the rainwater
samples taken near the Brest military port.
The iodine-131 measured in the rainwaterin March 2011 can be viewed in relation toreleases linked with the Fukushima accident.
For more information
Chapter III – The Fukushima Accident

1,637
LASEM
IRSN

Atmospheric
Marine aquatic
Terrestrial

Figure VI.63 – Brest military port: sample distribution by data producer and by compartment.
1,210

506

189

515
SPR Île Longue

Atmospheric
Marine aquatic
Terrestrial

Figure VI.64 – Île Longue military base: sample distribution by data producer and bycompartment.

250

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

VI.2
Activity (mBq/m3)
4
Fukushima accident

3

2

1

0
Jan.-10

Apr.-10

Jul.-10

Oct.-10Jan.-11

Apr.-11Significant measurement (> DL)F igure VI.65 – Time plot of gross beta activity of atmospheric aerosol samples
taken near Brest, Île Longue and Cherbourg military ports (mBq/m3).
Table VI.34 – Activity levels measured in Brest military port’s environmental aerosols (mBq/m3).

Radionuclide typeRadionuclide

Mean activity (mBq/m3)

Gross activity

Gross beta activity

0.20 ± 0.01
0.45 ± 0.01*

Cesium-134

0.006 ± 0.001*

Cesium-137

0.005 ± 0.001*

Iodine-131

0.067 ± 0.006*

Artificial radionuclides during the periodof the Fukushima nuclear power plant accident* Measurements taken during the period of the Fukushima nuclear power plant accident between March 22 and May 6, 2011.
Table VI.35 – Beta activity indices of the Île Longue military base’s environmental aerosols (mBq/m3).

Radionuclide typeRadionuclide

Mean activity (mBq/m3)

Gross activity

Gross beta activity

0.18 ± 0.01
0.60 ± 0.01** Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

Terrestrial compartment
The military ports of Brest and Île Longue
are monitored by means of regular soil,
terrestrial plant and agricultural production samples (milk, meat, fruit and vegetables) taken in the immediate vicinity ofthese sites.
Terrestrial floraMonthly grass and common gorse samples
are taken near Brest military port, in Brest,
Guipavas, Plougastel-Daoulas, Roscanvel
and Crozon.
Traces of iodine-131 and cesium-134 andcesium-137 due to the Fukushima nuclear
plant accident on March 11, 2011 wereperiodically measured in the grasses
between the end of March and the beginning of April 2011 in Brest military port’s

environmental monitoring stations. Theseradionuclides have also been measured at
the beginning of April 2011 in the common
gorse samples taken at Guipavas Airport,
Pointe des Espagnols in Roscanvel and Le
Fret in Crozon. Only iodine-131 has beenmeasured in the common gorse samples
taken in the Quatre Pompes submarine basein Brest. The iodine-131 activities measured
in the different samples vary between
0.14 ± 0.1 Bq/kg dry and 14.5 ± 1.4 Bq/kg
dry.
For more information
Chapter III – The Fukushima Accident
Except during the Fukushima accident
period, no artificial gamma-emitting radionuclides that could be attributed to thesemilitary bases’ activities has been measured
in the grass and common gorse samples.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011251

Monitoring of Research Centers and Nuclear Naval Bases

Soils
Annual soil samples are taken in the areasurrounding these sites. Apart from the presence of natural radionuclides, these soil samples’ analytical results have indicated thepresence of cesium-137, at activity levels
comparable to those found throughout
France. This can be attributed to past atmospheric fallout from nuclear weapons testing
and the Chernobyl accident (Table VI.36).

Table VI.36 – Activities measured in soil samples taken around the Brest military base(Bq/kg dry).

Radionuclide

Guipavas
AirportBrest
French Naval
Laboratory
lawn

Roscanvel
Pointe desEspagnols

CrozonLe FretCrozonPointe deRenardCs

4.28 ± 0.3

6.23 ± 0.3

28.4 ± 0.8

0.3 ±
0.13

5.84 ± 0.28

Csnm

< 0.47< 0.6< 0.19

nm

I

nm

<1

< 0.9

<1

nm

Co

< 0.17< 0.22< 0.24< 0.2< 0.13

137

134

131
60

Agricultural production and foodstuffs
Milk
Monthly cow’s milk samples are taken at
three farms in Daoulas, Guipavas and Crozon.
This monitoring was supplemented by aone-off goat’s milk sample taken on April 5,2011 to assess the effects of the Fukushima
nuclear power plant accident on March 11,2011 upon metropolitan France. The milk’smeasured radioactivity is mainly due to natural potassium-40, whose mean activity
concentration is 42.3 ± 0.3 Bq/L in cow’s
milk and 47.4 ± 2.1 Bq/L in goat’s milk.
The presence of iodine-131 in the three
cow’s milk samples taken at the beginningof April 2011, which had activity concentrations of between 0.10 ± 0.03 and0.34 ± 0.04 Bq/L, is linked with the Fukushima nuclear power plant accident. Similarly,
low iodine-131 and cesium-137 activity levels have been measured in the cow’s milk
from Plougastel-Daoulas, with activity concentrations of 0.78 ± 0.05 and0.036 ± 0.026 Bq/L, respectively.

Ag< 0.18< 0.23< 0.26< 0.21< 0.13K

647 ± 19865 ± 19469 ± 12495 ± 23475 ± 17Ac

56 ± 738.7 ± 3.6

54 ± 4.8nm

62 ± 8Pb

53.1 ± 1.9

41.1 ± 1.2

55.2 ± 1.6

nm60.9 ± 2.2

110m
40
228

212

Pb

48.7 ± 2.1

34.9 ± 1.4

44.8 ± 1.5

nm33.2 ± 1.5

Th

49 ± 2232 ± 1136 ± 12nm

41 ± 17Unm

4.2 ± 0.5

5.4 ± 0.6

nm

4.64 ± 0.28

214
234

235

nm: not measured

Fruit and vegetables
Normally, no artificial gamma-emitting radionuclides are measured in the fruit and vegetables grown around Brest military port.
The measured radioactivity is mainly due tonatural potassium-40, whose activity levels
are shown in Table VI.37. The lettuce sample
taken on April 26, 2011 in Guipavas had alow cesium-137 specific activity of
0.039 ± 0.036 Bq/kg wet, which could be
attributed to the Fukushima nuclear power
plant accident that occurred the previous
month.

No artificial gamma-emitting radionuclides
have been measured outside this period.
Meat
The annual radioactivity analysis of rabbits
reared in Plougastel-Daoulas has shown that
there are no artificial radionuclides in theflesh, skeletons or viscera.

252

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

 able VI.37 – Mean potassium-40 activities
T
measured in the fruit and vegetables producednear the Brest military base (Bq/kg dry).

Species

ActivityApple

46.9 ± 2.2

Lettuce114.2 ± 2.4

Leek

98 ± 1.9

Cabbage71.5 ± 2.8

Turnip121.5 ± 4.4

Parsley271 ± 12

VI.2
Cherbourg
military port

973

156

638

166

Cherbourg military port, on France’s northern coast, houses the French defense procurement agency (DGA) and is mainly
responsible for building or dismantling thenuclear-powered attack and ballistic missile
submarines built by the French shipbuilding
directorate (DCN). It also provides the
French naval forces and visiting foreign ships
with logistics support.

325
LASEM
IRSN

Atmospheric compartment
Atmospheric aerosols
Apart from natural radionuclides, no artificial radionuclides have been measured in
Cherbourg military port’s environment(Table VI.38). Monitoring of the beta activity index (Figure VI.65) has not revealed any
abnormal values.

Atmospheric
Marine aquatic
Continental aquatic

Figure VI.66 – Cherbourg military port: sample distribution by data producer and by compartment.

Table VI.38 – Natural radionuclide activities measured in Cherbourg military port’s environmental
aerosols (mBq/m3).

Radionuclide type

Natural radionuclides

Aquatic compartment

Radionuclide

Mean activity (mBq/m3)

Beryllium-7

2.03 ± 0.03

Potassium-40

0.053 ± 0.003

Actinium-228

0.0024 ± 0.0003

Uranium-235< 0.0036

Ground water
Traces of actinium-228 (Figure VI.67), thallium-208, bismuth-214, lead-212 and lead214 produced in the natural thorium anduranium-238 decay chains are occasionallymeasured in the ground water.
Tritium is measured in the ground waterwith activity levels of approximately
5.5 Bq/L; these vary between the decisionthreshold and 10.4 Bq/L during the period
under study (Figure VI.68).

1.4

Bq/L

1.2
1
0.8
0.6
0.4
0.2
0
Nov.-09
Jan.-10
Mar.-10Significant activity (> DT)

May-10Jul.-10

Sept.-10

Nov.-10F igure VI.67 – Actinium-228 activity measured in ground water in the Homet zone near Cherbourg
harbor (Bq/L).

12

Bq/L

10
8
6
4
2
0
Nov.-09

Jan.-10

Mar.-10May-10Significant activity (> DT)

Jul.-10

Sept.-10 Nov.-10

Jan.-11

Mar.-11May-11

Decision thresholdF igure VI.68 – Tritium activity measured in ground water in the Homet zone near
Cherbourg harbor (Bq/L).

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

253

Monitoring of Research Centers and Nuclear Naval Bases

Toulon military port

890

1,502

568

Toulon military port, on France’s southerncoast, is the main French naval base,
together with Brest. It mainly services mostof France’s naval action force, including its
nuclear-powered attack submarines. Furthermore, 37 surface ships are based at Toulon;
these include the aircraft carrier “Charles-deGaulle” (France’s largest nuclear-poweredsurface vessel).

Atmospheric compartment
Atmospheric aerosols
In Toulon military port’s environment, an
increase in the beta activity index was measured between the end of March and the endof April 2011 (Table VI.39), which can be
attributed to the presence of artificial radionuclides released in the Fukushima nuclear
power plant accident.
Apart from this finding, no other abnormalbeta activity index values have been
observed.

158

158
44
Atmospheric
Marine aquatic
Continental aquatic
Terrestrial

LASEM
IRSN

Figure VI.69 – Toulon military base: sample distribution by data producer and by compartment.

Table VI.39 – Beta activity indices of Toulon military port’s environmental aerosols (mBq/m3).

Radionuclide typeRadionuclide

Mean activity(mBq/m3)

Gross activity

Gross beta activity

0.18 ± 0.01
0.33 ± 0.01** Measurements taken during the period of the Fukushima nuclear power plant accident between
March 22 and May 6, 2011.

Rainwater
Iodine-131 was measured in the rainwater
samples taken in March and April 2011. Thismeasurement can be linked with the
Fukushima accident. No significant activity
levels have been measured outside thisperiod.

Terrestrial compartment

Agricultural production and foodstuffs
Fruit and vegetables
No artificial gamma-emitting radionuclides
have been measured in the fruit and vegetables grown around Toulon military port. The
measured radioactivity is mainly due to natural potassium-40, whose activity levels areshown in Table VI.40.

Terrestrial flora
Regular samples of shrubs (mastics andcypresses) and aromatic herbs are taken
around Toulon military port. Analysis ofthese samples has not revealed any abnormal activity resulting from the Toulon site’s
nuclear activities.
Only a few traces of iodine-131 have beenmeasured in a mastic sample taken on
April 4, 2011 with an activity of 4 ± 1.9 Bq/
kg dry; these can be attributed to the Fukushima nuclear power plant accident in Japanon March 11, 2011.
For more information
Chapter III – The Fukushima Accident254 able VI.40 – Mean potassium-40 activities
T
measured in the fruit and vegetables produced near
the Toulon military base (Bq/kg dry).

Species

ActivityGrape

154 ± 5

Tomato80 ± 2.4

Lettuce77.1 ± 1.8

Zucchini

136.1 ± 4.1

Potato184 ± 6IRSN – Report on the Radiological State of the Environment in France in 2010–2011© Areva NC

VI.2

Figure VI.70 – Taking plant samples in the Marcoule site’s environment.

IRSN – Report on the Radiological State of the Environment in France in 2010–2011

255

Monitoring OF Facilities that use Sources of Natural or Artificial Radioactivity

256

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

VII
Monitoring OF
Facilities thatuse Natural
or Artificial
Sources ofRadioactivity
VII.1 Rhodia Electronics & Catalysis plant in La Rochelle© O. Seignette/M. Lafontan/IRSN

VII.2 Industrial ionization facilities

Monitoring OF Facilities that use Sources of Natural or Artificial Radioactivity

In addition to the principal nuclear fuelcycle (Chapter V) and research (Chapter VI)
operators, a number of industrial sectors
use raw materials containing naturally
occurring radionuclides or employ ionizing
radiation sources for a range of applications.
Some of these facilities are classified as
basic nuclear installations (INB) or environmentally regulated facilities (ICPE), and are
therefore subject to regulatory environmental radioactivity monitoring.

Industrial facilities
operating with raw
materials that containnaturally occurring
radionuclides
A number of modern and traditional industrial activities generate large volumes of lowlevel radioactive waste: radium-bearing
waste. As its name indicates, this type ofwaste contains trace amounts of radium andradium progenies from the uranium decay
chain, which occur as trace elements in the
Earth's crust. Some radium-bearing waste
occurs as a result of clean-up activities atcontaminated sites formerly involved in theradium industry, which flourished during the
pre-war period. More recent sources of such
waste include the processing of very lowlevel radioactive mineral ores such as monazite, which contains rare earths and theiroxides in variable proportions. The terms
rare earths and lanthanides refer to agroup of around fifteen chemical elementswith similar structures and properties.
Monazite ore is particularly rich in rareearths, notably cerium, terbium and europium. Rare earths are used in an extensive
range of applications including ceramic andglass-making, magnets, petrochemical catalysts, metalworking, cathode ray tubes andliquid crystal displays. Cerium is required forthe manufacture of particle filters for dieselengined vehicles. Monazite ore is also naturally rich in thorium and radium. In France,
Rhodia has used this ore at its plant in La
Rochelle, and it has also been used industrially at other locations, where thoriumcontaminated process waste sometimes
remains. Examples include sites in Serquigny, Thann and Pargny-sur-Saulx in
nor thern and eastern France (seeChapter III.3).

The level of radioactivity in such radiumbearing waste tends to range from a few tens
to a few thousands of becquerels (Bq) per
gram. The principal radionuclides are longlived alpha emitters. Radium-bearing waste isclassified as low-level long-lived waste (LLWLL). This category of waste will be subject tospecial conditioning and disposal requirements, currently being researched by ANDRA.
This chapter focuses on the case of the Rhodia Electronics & Catalysis (previously Rhodia
Terres Rares) plant, which used monazite
until 1994. The site has been subject to regular environmental radioactivity monitoring,
including atmospheric and groundwater
monitoring.

cereals and fresh fruit and vegetables, andpasteurizing and eliminating bacteria in fishand meat. Gamma radiation sterilization isused to eradicate harmful insects, for example. Multiple applications involving sterilization of objects such as medical devices andsurgical instruments also exist. Gamma ray
treatments are also used in the ethnologicaland archeological fields, to preserve andrestore artworks and other artefacts.
The Ionisos group currently operates a network of ionization centers, respectively
located in Pouzauges, Sablé-sur-Sarthe andDagneux, and the Isotron group operates afacility in Marseille (Figure VII.1).

Industrial
ionization facilities
Several industrial ionization facilities exist inFrance. These use gamma radiation tosterilize medical equipment or treat
foodstuffs.
Irradiating food products destroys microorganisms with no need to heat them. This
process can be used to extend product shelf
lives by preventing bulbs and tubers from
germinating, eliminating parasitic insects inIonisos – Sablé-sur-Sarthe
Ionisos – Pouzauges
Rhodia – La Rochelle

Ionisos – Dagneux

Isotron– MarseilleIndustrial ionization facilities
Industrial mineral ore processing plant
Figure VII.1 -Geographical location of the facilities covered in this chapter.

258

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

VII.1

From 1946 to 1994, the plant used monazite, a raw material that containes rare earths
and trace natural radioactivity. In 1998, Rhodia acquired the chemicals business ofRhône-Poulenc. Monazite has not been processed directly in La Rochelle since 1994.
Rhodia now receives concentrates from
China, where they have been processed tolargely strip them of their naturally occurring
radionuclides. However, activities at the La
Rochelle site over a sixty-year period generated a significant quantity of radium-bearing
waste.
Rhodia stores approximately 20,000 metrictons of untreated thorium hydroxide and11,000 metric tons of thorium nitrate, essentially at its La Rochelle facility. The thorium
232 activity of these products is around
720 Bq/g and 1,650 Bq/g, respectively. Sincemonazite processing in La Rochelle ended in
1994, Rhodia no longer produces these products. These materials may be of use as a
power source for the nuclear industry if "fastneutron" reactors are developed in the future.
Rhodia also has suspensions containing
potentially recoverable rare earths.
Until 1974, the plant discharged liquid andsolid waste into the sea off Port-Neuf beach(La Rochelle bay). Prior to 1991, the plantshipped part of its solid waste to ANDRA's
CSM waste disposal facility, and thereafter totemporary storage facilities at the CEA center in Cadarache. Rhodia owns approximately
13,300 metric tons of waste, in the form of:• radium-bearing waste ("RRA") almost
200 tons of which are stored in La Rochelle(with a total average specific activity ofaround 1,600 Bq/g);• general solid waste ("RSB") consisting of
spoil contaminated with ore leaching resi-

Figure VII.2 - Rhodia plant in La Rochelle.

dues and miscellaneous waste (including
packaging and scrap metal), of which
8,000 tonnes are stored in La Rochelle (witha total average specific activity of around
75 Bq/g).

66

This waste is included in the provisional
inventory of waste that will be stored at
ANDRA's planned LLW-LL repository.
The radiological impact of waste containing
naturally occurring radioactive materials
derives from the presence of naturally occuring radionuclides. Certain radionuclides haveradioactive half-lives of several million years,
and will therefore have time to migrate into
the soil, surface water and ground water.
Transfers to the atmosphere are also possible
in the shorter term. This migration to thenatural environment may result in environmental contamination and radiologicalimpacts on the population. As an environmentally regulated facility (ICPE), the Rhodia
plant in La Rochelle is therefore subject toregulatory monitoring of radioactivity in theair (measured by passive dosimetry), in thewater in the liquid waste treatment pond
(1 sampling point) and in ground water(13 sampling points).

144
Aquatic compartment
Atmospheric compartment

Figure VII.4 - Rhodia Electronics& Catalysis plant in La Rochelle Number of measurements per compartment© ANDRAThe Rhodia plant in La Rochelle on France's
Atlantic coast is a "high-threshold Seveso"
facility located on the Chef de Baie industrial
estate to the west of the town center. The
site accommodates production facilities aswell as significant research and development
resources.

© RhodiaVII.1 Rhodia
Electronics &Catalysis
plant in La
Rochelle

Figure VII.3 - Radium-bearing low-levellong-lived waste stored at the Rhodia plantin La Rochelle.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011259

Monitoring OF Facilities that use Sources of Natural or Artificial Radioactivity

Aquatic
compartment

Radioactivity is also monitored at the site
perimeter using various sampling devices andmeasuring instruments. This monitoring
concerns external exposure (gamma radiation
measurements) and internal exposure by inhalation (measurement of the potential alphaenergy generated by short half-lived decay
products of radon-220 and radon-222, andmeasurement of the concentration of long
half-lived alpha emitters carried in dust).
The results obtained from 22 passive gamma
dosimeters installed along the site perimeterare sent to the National Environmental Radioactivity Measurement Network (RNM). The
measured values range between 110 nSv/hand 417 nSv/h, with a mean value in theregion of 230 nSv/h. These results must becompared with IRSN's mean values for the
town of La Rochelle (78 nSv/h) and for the
Poitou-Charentes region (119 nSv/h). Certain
results are significantly abouve the regional
background level, reflecting the signature leftby the plant's activities, particularly waste
storage. Rhodia erected buildings in which tostore untreated thorium hydroxide, in orderto decrease the dose rates associated withthis storage activity.
For more information
Chapter IV – Atmospheric compartment

Each year, two sampling campaigns are conducted using referenced piezometers. The
data is analyzed in order to monitor the following parameters: 232Th or total thorium,
238U or total uranium,226Ra, 228Ra, lead, dissolved manganese, dissolved mercury, dissolved nickel and ammonium. All liquid
waste from the plant's chemical network is
carried to the treatment station, where it istreated and made compliant with applicablestandards before being discharged into thesea in La Rochelle bay. Checks are performedat point B to determine the waste's radiological and physical-chemical properties.

irsn FOCUS •Atmosphericcompartment

260

The La Rochelle facility extracts water fromthe industrial water table via a borehole(known as the Puits de Vaugouin) locatednear the plant. The ground water is monitored using piezometers in various locations
on the Rhodia site.
Most of the measurement results for radium
226 (a decay product of uranium-238) at
the water monitoring points at this siterange between the decision threshold(0.0044 Bq/L) and 0.06 Bq/L. These activity
levels are representative of or similar to thenatural background level. Only the radium226 readings measured by piezometers A, B

and D (ground water) exceed 0.1 Bq/L,
revealing a signature related to the facility's
activities. The highest value (0.25 +/0.075 Bq/L) was measured in April 2010.
The activity levels for radium 228 (a decay
product of thorium-232) measured in thewater samples range between the decisionthreshold (0.014 Bq/L) and the maximum
value of 0.48 Bq/L. The vast majority of
results are below the decision thresholds.
The other activity measurements are moderate, although the peak values measured atpoints B, D and F2 reflect the signature of
the site's activities. The highest radium 228
activity value measured in the water treatment pool (point B) in 2010 was 0.13 +/0.03 Bq/L.
Uranium content values are below or close
to the guide value of 30 µg/l of uranium
recommended by the WHO for water
intended for human consumption. The activity levels measured in the water treatment
pool (point B) in 2010 were below or close
to the decision thresholds and not indicativeof any impact by the site's activities.

Radiological impact of sediment dredging
in the port of La Rochelle
In 2009, the municipal council in La Rochelle
initiated a project to expand the town's
Minimes marina. This entailed dredging
approximately 1,000,000 m3 of sediment tobe deposited in the Antioche trench. La
Rochelle council commissioned IRSN toprovide technical support by assessing theradiological impact of the planned work on
workers and the population. A core drilling
campaign was conducted between July 20
and August 7, 2009. A total of 111 samplesof the sediments to be dredged werecollected at 31 sampling stations, followedby two samples at two reference stations
located in Fier d’Ars (an area not subject toindustrial impacts) and five samples ofbeach sand. These samples were collected
and analyzed in accordance with an IRSNapproved protocol. The results were

submitted to IRSN, enabling the Institute toperform the requested assignment.

away, which produces rare earths from thorium-bearing monazite).

This exhaustive assessment revealed that the
choice of reference stations was appropriate, that the activity levels measured inbeach sand reflected the activity of any
radionuclides present in the (small) sandy
fraction of the sediments to be dredged(approx. 5 Bq.dry for the thorium-232 anduranium-238 chains). The activity levels
measured in this sediment were not significantly different from those measured in sediment at the reference stations(approximately 30 Bq.kg-1 dry for the thorium-232 and uranium-238 chains),
although a few specimens revealed sporadic,
moderate industrial effects (attributable towaste from the Rhodia plant located 3 km

The radiological impacts on workers
assigned to the sediment dredging operations and on the general population were
estimated based on the activity measurements made on the sediment samples. The
maximum effective dose calculated forworkers assigned to sediment dredging
operations is 0.012 mSv. The maximum
effective dose calculated for the populationgroup of adult professional fishermen who
consume large amounts of fish or seafood is0.035 mSv.year-1. Although based on pessimistic assumptions, the calculated doses
are low, and well within the limit of
1 mSv.year-1.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

VII.2
VII.2 Industrial
ionization
facilities
Industrial ionization facilities use gamma
radiation (mainly from cobalt-60 sources) tosterilize medical devices and treat foodproducts.
In such facilities, the irradiation process takes
place in a chamber containing very highly
radioactive cobalt-60 sources. The products
to be irradiated are placed on trays on a conveyor belt, which carries them into and outof the irradiation chamber through a "labyrinth" (Figure VII.5). The irradiation chamber
contains a pool in which the cobalt-60
sources are stored while not being used forirradiation phases. The water in this pool acts
as a screen, blocking radiation from thesources. Products are irradiated with thesources raised out of the water.
The cobalt 60 sources consist of rods supported by one or more source holders. The
source holders are raised and lowered by asystem of mechanically operated winches
and cables.
Ionizers pose very little risk to the general
population and the environment. The main
potential risk relates to the exposure of
employees to ionizing radiation. This risk isProtection chamber

managed by installing radiation protection thick walls in the irradiation chamber forwhen the ionizer is in operation and thewater in the storage pool at other times - andimplementing safety measures to control
employee access to the irradiation chamberand manage source movements.
Although classified as basic nuclear installations, ionizer facilities are subject to regulatory environmental radioactivity monitoring
to prevent contamination.

Facilities operated
by the Ionisos group
Ionisos provides radiation treatment
services using either a cobalt-60 source(for gamma radiation) or an electron
accelerator.
The Ionisos group operates mainly in thefollowing three markets:• sterilization: sterilization of single-use
medical devices; sterilization and decontamination of packaging, raw materials
and end products for pharmaceutical andcosmetics, sterilization and decontamination of laboratory equipment;• radiation chemistry: packaging film
cross-linking, glass tinting and modification of plastic components to alter theirproperties;

Irradiation source• ionization for food processing applications: germination-inhibiting treatment,
disinfection and debacterization of dried
and frozen products as well as fresh
produce.
Ionisos operates four facilities in France:• An electron particle accelerator in Chaumesnil, southeast of Paris;• Three gamma irradiation centers, respectively located in Dagneux near Lyon, Pouzauges in western France and in
Sablé-sur-Sarthe in eastern Brittany.
These facilities, classified as basic
nuclear installations, are subject toenvironmental monitoring.
The only radioactive waste produced atthese facilities is very low-level waste(VLLW) resulting from the various operations performed on the water in the pool inwhich the cobalt-60 source is stored. This
waste is packed in hermetically sealed containers and stored in dedicated enclosed
storerooms pending dispatch to ANDRA'svery low-level waste disposal facility in Morvilliers in eastern France. Only a small quantity (< 1 m3) of VLLW is produced each year.
This waste does not interact with waterways
and ground water. The ground water system
is nevertheless subject to monthly radioactivity checks to ensure that the water isuncontaminated.

Pool

Conveyor

Control station
Loading area

© Chromatiques/IRSN - Source: IRSN

Unloading area

Figure VII.5 - Overview of an industrial ionizer.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

261

Monitoring OF Facilities that use Sources of Natural or Artificial Radioactivity

Ionisos irradiation facility in Dagneux

Ground water is monitored to track thegross beta activity index. In addition to thismonitoring, gamma spectrometer measurements on these monthly samples are made,to quantify any gamma-emitting radionuclides released from the site (only cesium-137 and cobalt-60 measurements are submitted to the national environmental radioactivity measurement network (RNM).

© Ionisos

Gross beta activity levels range between
the decision threshold (<0.03 Bq/L) and
0.074 +/- 0.041 Bq/L (i.e. the highest value
measured in December 2010). The grossbeta activity readings do not indicate thatthe ground water has been particularly
affected by the site's activities, and are far
below the baseline value of 1 Bq/L stipulated
in the public health code applicable to water
intended for human consumption. Similarly,
the results of the gamma spectrometry measurements did not reveal any detectable
cesium-137 or cobalt-60 activity (the measured values were below the decision thresholds of the instruments used, averaging<0.09 Bq/L).

© Ionisos

Basic nuclear installation No. 68 (Figure
VII.6) is located in Dagneux, 25 km east of
Lyon in south-east France. This INB houses
three irradiation units:• Irradiation units D1 and D2, which are nolonger in service;• Irradiation unit D3, which was built in 1972
and remains in operation.

Figure VII.6 - Ionisos irradiation unit in Dagneux.

Ionisos irradiation facility
in Sablé-sur-Sarthe

system. Products are carried on an automated overhead conveyor and treateddirectly on full pallets or in big-bags with no
Basic nuclear installation No. 154 (Figure human intervention.
VII.7) is located in Sablé-sur-Sarthe, near thetowns of Laval, Angers and Le Mans. This INB, Ground water is monitored to track thewhich began operating in 1992, is equipped gross alpha and gross beta activity index.
In addition to this monitoring, six-monthly
with a pallet irradiation unit.
radium 226 and gamma spectrometry meaThe gamma radiation treatment process surements are performed on these samples,(using a cobalt-60 source) treats pallets in to determine the quantity of gamma-emittwo independent trains arranged on either ting radionuclides potentially released by theside of a flat source. The center has the facility.
capacity to treat 50,000 pallets per year. The
plant operates using a fully automated The average gross beta activity level is
0.36 Bq/L, which is not indicative of any particular impact of the site's activities onground water. Similarly, the gross alpha activity readings, ranging between 0.061 and
0.070 Bq/L, are below the baseline value of
0.1 Bq/L stipulated in the public health code
applicable to water intended for human consumption. The measurement results forradium-226 at the water monitoring point at
this site range between the decision threshold (< 0.016 Bq/L) and a maximum value of
0.026</cf> Bq/L. These activity levels are
representative of or similar to the natural
background level. Similarly, the results of the
gamma spectrometry measurements did notreveal any detectable cesium-137 orcobalt-60 activity (the measured values were
below the decision thresholds of the instruments used, averaging <0.06 Bq/L).

Figure VII.7 - Ionisos irradiation unit in Sablé-sur-Sarthe.

262

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

VII.2
Ionisos irradiation facility inPouzauges
Basic nuclear installation No. 146 (Figure
VII.8) is located in Pouzauges , 38 km southof Cholet in western France. This INB is
equipped with a pallet irradiation unit. Products are loaded into baskets suspended froman automated overhead conveyor system.

Isotron facility
in Marseille© Ionisos

Six-monthly ground water samples are collected using a piezometer. The results of the
gamma spectrometry measurements did notreveal any detectable cobalt-60 activity in2010 or 2011 (the measured values were
below the decision thresholds in the regionof 0.2 Bq/L).
Figure VII.8 - Ionisos irradiation unit in Pouzauges.

Isotron France SAS is a sterilization services
provider based in Marseille. The company
offers a range of services to manufacturers,
including sterilization of medical devices andpackaging, debacterization, insect eradicationand microbial decontamination.
Isotron is registered as a data provider with
the RNM network, owing to its operation of
INB No. 147 in Marseille. The company has
begun submitting data relating to the sixmonthly samples collected in January andJune 2011 at two ground water extraction
points (P1 and P2). The results of these measurements had not been submitted to RNM
by the date limit for processing data relating to the reference period covered by thisassessment.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011263

French Population Exposure to Ionizing Radiation

264

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

VIII
FRENCH POPULATIONEXPOSURE toionizing radiation

VIII.1 Average exposure of the population in France
VIII.2 Assessing the biological effects of radioactivity on livingorganisms
VIII.3 Doses received by the population as a result of nuclear
activities
VIII.4 Assessment of the radiological quality of drinking waterin France
VIII.5 Dosimetric assessment for French Polynesia© O. Seignette/M. Lafontan/IRSN

VIII.6 Assessment of the dosimetric impact of the Fukushima
accident on the French population

French Population Exposure to Ionizing Radiation

VIII.1Average
exposure of
the populationin France* Emissions from facilities and fallout fromatmospheric nuclear testing

0.5

Total = 3.7 mSv/year

1.4(Source: IRSN, 2010 estimate)

Radon
Radon is a naturally occurring radioactivegas. It results from the disintegration of
uranium and radium found in the Earth's
crust (Figure VIII.2). Originating primarily
in granitic and volcanic subsoil and certain
construction materials, radon is foundeverywhere on the Earth's surface.
Lung cancer is the reason for vigilance withregard to radon, which sometimes builds up
in homes and other enclosed spaces. Radonand its solid decay products enter the lungs
along with inhaled air. These decay products
emit alpha radiation which can cause cancer.

Migration to the atmosphere depends on
two factors:• Weather conditions are among the factors that can cause radon concentrations
to vary over time at a particular location.
Depending on soil composition, weather
conditions (wind, sun, rain, cold, etc.) willaffect the migration of radon from the soil
into the atmosphere.
• Soil and rock properties: radon concentrations vary across a region, dependingon the natural uranium content of thesubsurface. Granitic ground tends to:. : . :.

Radioactive decay products in theform of dust that can settle
in the lungs:. :. :.
206
Lead:. :. :.

:. : . :.

. :. :. :.

Materials
in the earth's
crust
238
Uranium:. : . :.

. :. :. :.

Radon gas

222
Radon

226
RadiumFigure VIII.2 - Radon - from the soil into the atmosphere

IRSN – Report on the Radiological State of the Environment in France in 2010-2011:. :. :.

:. :. :. :218
Polonium214
Lead:. :. :. ::. :. :.

:. :. :.

:. : . :.

:. : . :.

214
Polonium

Radon, from soil to atmosphere266:. :. :. :Atmosphere214
Bismuth. :. :. :.

IRSN • FOCUS

Figure VIII.1- Average exposure to ionizing radiation of the population in France:. :. :. :Exposure to natural radioactivity accounts
for an average of 65% of total annual
exposure.

Radon
Telluric radiation
Cosmic radiation
Water and foodstuffs
Other*
Medical:. :. :. :The French population is exposed to natural radioactivity from several sources:• radon, (see IRSN Focus), a gaseous decay
product of uranium, may build up in
homes, making a significant contribution
to the mean dose (approx. 1.4 mSv per year
per person). Exposure levels vary by a factorof 15 between the most and least exposed
departments;• naturally occurring radionuclides present in the ground emit terrestrial radiation resulting in an average external
exposure (to 238U, 235U, 232Th, 40K, etc.) in theregion of 0.5 mSv per year per person. In
France, this exposure is subject to a variability factor of 5;• cosmic radiation causes external exposure, which varies with altitude. The average dose is 0.28 mSv per year per person.
At sea level, this value is around 0.27 mSv
per year per person, rising to 0.38 mSv inthe departments situated at the highest
mean altitude;• exposure by ingestion of naturally occurring radionuclides present in food andwater represents 0.23 mSv per year per person, of which 0.18 mSv is attributable topotassium-40. This exposure depends on foodintake and soil type.

1.3. :. :. :.

Exposure due to naturalradioactivity

0.2
0.03

. :. :. :.

All sources of natural and artificial radioactivity contribute to exposure levels. This
exposure of the French population isassessed by IRSN (Figure VIII.1). French citizens receive an average total annual dose of
approximately 3.7 mSv. This value, which
varies according to geographical locationand lifestyle, should be treated as a macroscopic indicator; it is not applicable to any
particular group of people.

0.3

VIII.1
Exposure
due to artificial
radioactivity
The principal source of exposure to artificial radioactivity relates to the use of medical sources, particularly radiation-based
diagnostic techniques (X-ray imaging, mammograms, scanner photography, etc.); such
sources account for an average of 1.3 mSv
per year per person. This dose is obviously notreceived uniformly by the population. Individual figures vary from less than 0.1 mSv tovalues well in excess of 1mSv per year perperson, depending on the medical procedures
to which patients are subject.

release more radon than sedimentary
land, due to the higher concentration ofnaturally occurring uranium.
Measurement campaigns and subsequentstatistical interpretations have been carriedout to estimate so-called "domestic" radon
exposure (i.e. exposure to radon in homes)(see IRSN atlas). The average measuredradon activity level in France has been estimated at 63 Bq/m3, with approximately half
the results less than 50 Bq/m3, 9% greaterthan 200 Bq/m3 and 2.3% above 400 Bq/m3(source: IRSN).

Industrial activities and nuclear facilities innormal operation account for only a verysmall fraction of the French population's total
radiation exposure. The calculated doses forthe most heavily exposed local populations
do not exceed a few tens of μSv per year perperson(1 μSv = 0.001 mSv), principally
ingested in food products (>90%).

Fukushima accident on the French population are described in VIII.6.

At national level, the average effective
dose attributable to residual consequences of the Chernobyl accident andatmospheric nuclear testing is estimated to be between 0.01 mSv and0.03 mSv per year per person (source:
IRSN). The Institute's assessment of thedosimetry impact of consequences of thequerels per liter to several thousand. The
highest activity concentrations are normally found where the water reservoir isformed by uranium-rich rocks.
Understanding the nature of the geologicalformations in a region makes it possible tomap the areas in which high concentrationsof radon in buildings are most likely tooccur. Such a map provides a useful technical foundation to guide the implementation of a radon risk management strategy,
combined with data resulting from measurement campaigns conducted to detectradon in buildings. To this end, the French
Nuclear Safety Authority tasked IRSN withdefining and implementing a method formapping the radon potential of the groundthroughout metropolitan France. These
maps (example: Figure VIII.3) cannot be
used to predict radon concentrations insidebuildings, and are therefore no substitute for
onsite measurements.

In open air, radon dissolved in water is readily volatile. As a result, gaseous radon rapidly migrates into the atmosphere. The
activity concentrations of radon in water
vary considerably, ranging from a few bec-

Communes concernées« un potentiel
source» moyenou élevé
Municipalities
subject topar
a moderateor highsourcepotential
Municipalities
affected bythat facilitatetransfer ofthelasurface
Communes concernées
parcofactors
des cofacteurs
facilitantthe
le transport
duradonradontovers
surface© IRSN

Radon is also present in all natural surface
water and ground water, at variable activity concentrations. Radon originates in twoways:• the first, less significant formation process
is radioactive decay of dissolved radium226;• the second process involves the dissolution of radon present in rock in whichwater sits or circulates, enabling it to travelto the water table or the surface. The radon
concentration of water depends on the radon
content of the rock from which it migrates,
the geochemical conditions, and how long
the water remains in the rock.

Figure VIII.3 - Map of municipalities with at least some areas subject to moderate
and/or high radon potential, due to the "source potential" of the underlying geologicalformations (shown in green) or as a result of aggravating factors such as faults, undergroundmine workings and hydrothermal vents (shown in purple).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011267

French Population Exposure to Ionizing Radiation

The effects on individuals resulting fromexposure to radionuclides are not measured directly. They are quantified using
the effective dose for the entire body. The
standard measurement unit for this doseis the sievert (Sv), or more often its subunits: the millisievert (1 mSv = 0.001 Sv)
and the microsievert (1 µSv = 0.000001 Sv).
With some radionuclides, the dose can also
be calculated for a specific organ when theorgan is more sensitive to the effects ofradiation than the whole body (such as
iodine for example, for which the target
organ is the thyroid gland).
A distinction is made between external andinternal exposure, depending on how theradiation comes into contact with theorganism. External exposure is when an individual is exposed to sources of radiationthat remain outside the body (for example,
exposure to radionuclides in the air or insoil deposits); the received dose depends
on exposure time. In the case of internal
exposure, the radionuclide enters the organism - normally through ingestion or inhalation. The resulting internal radiation thencontinues after the radionuclide has entered
the body, gradually decreasing based on theradioactive half-life of the incorporated
radionuclide and the rate at which it iseliminated.
In the case of internal exposure caused
by a radionuclide with a long half-life, thecommited dose is calculated. This dose
indicates, at the time of exposure, all thedifferent "future" doses the individual will be
exposed to over the entire time periodrequired to completely eliminate the radionuclide. In cases where the radionuclide willremain in the body, the calculated period
will be the lifetime of the individual, ranging
from 50 years (for an adult) to 70 years (foran infant under 1 year old).

Dosimetric estimates
determined using transfer
modelsVIII.3 Doses
received
by thepopulation
as a resultof nuclear
activities

The total effective dose attributable to the predicted liquid and atmospheric emissions from afacility is assessed taking into account exposure
pathways and dose coefficients for each radionuclide and each exposure pathway.

No overall monitoring method able toexhaustively determine the doses received by
the population as a result of nuclear activities
currently exists (ASN, 2011). Radioactive liquid waste from basic nuclear installations is
accurately inventoried, however. In addition,
the area around these facilties is subject toenvironmental radioactivity monitoring.
Based on the collected data, the dosimetricimpact of this discharge on populations livingin the immediate vicinity of the facilities canthen be calculated using models that simulate transfers to the environment. The dosimetric impacts vary, depending on the typeof facility and the lifestyles of the studied
population groups, from a few microsieverts
per year to a few dozen microsieverts.

This calculation entails simulating the transfers to humans of radioactivity present in liquid and gaseous waste. It also includes
assumptions relating to the lifestyles of therelevant populations (concerning theirdietary habits, for example). Figure VIII.4
shows the potential routes whereby radioactivity discharged by a nuclear installation
may be transferred to humans.
From a practical perspective, when calculating
the impact of a facility's discharge on humans,
the dose is calculated by adding together theexternal exposure from artificial radioactivity
in the atmosphere (plumes), in soil deposits orin bathing water, on one hand, and the internal exposure caused by inhaling contaminated air and eating contaminated foodproducts.

Gaseous emissions

Plume

Inhalation

Deposition
Gaseous waste

Ingestion

Liquid emissions

Irrigation

Liquid waste
Ingestion
Bathing
Deposition
Figure VIII.4 - Routes for the transfer to humans of radionuclides discharged in gaseous and liquidemissions from nuclear facilities

268

IRSN – Report on the Radiological State of the Environment in France in 2010-2011© Chromatiques/IRSN - Source: IRSN

VIII.2 Assessing thebiologicaleffects ofradioactivity
on livingorganisms

ASN • FOCUS

VIII.3
Simulation-based evaluation of the radiological impact of
nuclear activities
Operators are required to assess the dosimetric impact of their activities. This obligation derives, depending on thecircumstances, from either Section
L.1333-8 of the French public healthcode or the applicable regulations relating to discharge from basic nuclear installations. The result must be assessedconsidering the maximum permissible
annual dose for the general public (1 mSv/
year) defined in Section R.1333-8 of the
public health code. This regulatory limit
corresponds to the sum of the effective

doses received by the public as a result of
nuclear activities.
In practice, it should be noted that only
trace levels of artificial radioactivity aredetectable in the vicinity of nuclear facilities, and that in routine monitoring programs, most measurements are below thedecision thresholds or reflect natural background radioactivity. As a result, thesemeasurements cannot be used to estimate
doses. Nuclear facility discharge measurements must therefore be introduced intomodels that describe the transfer of radio-

activity to humans. Each operator uses its
own models. ASN would like these methods to be standardized wherever possible, and in 2009 began exploring ways toachieve this in partnership with IRSN.
Table VIII.1 contains an assessment of thedoses attributable to INBs. This table showsa few examples of effective doses received
by the most exposed reference populationgroups.

Table VIII.1 - Examples of radiological impacts of nuclear sites since 2005, taken from calculations performed by operators using discharge data
for the most exposed reference groups (operator data, in mSv).

Estimated received doses, in mSv

Most exposed reference group(population/distance fromsite in km)a

2005

2006

2007

2008

2009

2010

Areva/La Hague

Digulleville (child/2.6)

1x10-2

1x10-2

1x10-28x10-38x10-3

1x10-2GANIL/Caen

IUT (adult/0.6)

2x10-33x10-3< 6x10-3< 9x10-3 b

3x10-3< 3x10-3

EDF/Cattenom

Garche north, Warpich(2009,2010)(adult/2.15)(2009, 2010: infant/1.5)

1.6x10-3

2.1x10-3

2x10-32.4x10-3

2.5x10-3

3.3x10-3

Areva/FBFC

Riffard farm [adult/0.2]

*

*

*

6x10-48x10-4

1x10-3

EDF/Civaux

Ervaux south [adult/0.7]

*

*

*

8x10-47x10-49.7x10-4

EDF/PenlySaint-Martin Plage,Vassonville(2009,2010)[adult/1.05] [2009,2010:
fisherman/0.7]

9x10-44.5x10-4

5.4x10-4

3x10-39x10-49.7x10-4

EDF/Tricastin

Clos du Bonneau, Le Trop Long
(2009, 2010)[adult/1.25] [2009, 2010:
infant/1.25]

7x10-56x10-56.1x10-5

4x10-47x10-49.4x10-4

Areva/Tricastin(Areva NC,
Comurhex,
Eurodif,
Socatri, Set)

Les Prés Guérinés[adult (2005: child)/3;
3.1; 2.16; 1.3; 1.5]

2x10-3

1x10-3

1x10-35x10-45x10-4*

Operator/Site

a: Until 2008, only "adult" values were calculated for facilities operated by EDF. Since 2009, the dose for the most exposed of the two age-based reference groups (adultor infant) for each site is stated.
b: Value measured at the site perimeter by passive dosimeters. Several dosimeters revealed traces of radioactivity even after the facility was shut down.
The value is therefore greatly overestimated, according to the operator.

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French Population Exposure to Ionizing Radiation

ASN • FOCUS

Focus cont.

Table VIII.1 (cont.) - Examples of radiological impacts of nuclear sites since 2005, taken from calculations performed by operators
using emissions data for the most exposed reference groups (operator data, in mSv).

CEA/Saclay

Christ-de-Saclay [adult/1]

1x10-3

1x10-38x10-47x10-45x10-46x10-4

EDF/Bellevillesur-Loire

Neuvy-sur-Loire [adult/1.3]

2x10-42x10-42x10-46x10-47x10-46x10-4

Andra/Manche

Hameau de La Fosse [adult/2.5]

8x10-48x10-47x10-47x10-46x10-44x10-4

EDF/Bugey

St-Étienne d’Hières south[adult/0.45]

*

*

*

5x10-45x10-43.6x10-4

EDF/Chinon

Le Neman [adult/1.25]

2.1x10-4

2.5x10-4

1.3x10-4

4x10-44x10-44x10-4

EDF/
Fessenheim

EDF complex (Koechlin)[adult, 2010: infant)/1.2]

*

*

*

7.5x10-5

8x10-5

1x10-4

ILL/Grenoble

Fontaine (gaseous emissions) andSaint-Egrève (liquid emissions)[infant/1 (Fontaine);
1.4 (Saint-Egrève)]

*

*

*

*

1x10-4

1x10-4

EDF/CreysMalville

Chancillon farm[adult, 2010: infant)/0.85]**

1x10-52x10-58x10-6

6x10-5

CEA/Fontenayaux-Roses

Fontenay-aux-Roses [child/1.5]

2x10-5

1x10-59x10-6

9x10-6

5x10-6

4x10-6

Andra/CSA

CD24 road bridge [child/2.1]

6x10-6

5x10-6

3x10-62x10-6

5x10-62x10-6* Information not provided by the operator

The doses attributable to basic nuclear
installations for a particular year are
estimated based on the actual discharge
from each facility during the studied
year. This evaluation includes discharge
via the identified routes (e.g. stacks anddischarge pipes leading to rivers or thesea). It also includes diffuse emissions
and any sources of radiological exposure
to ionizing radiation present at the facility. These components together make up
the "source term".
Doses are estimated with respect to one ormore clearly identified reference groups.
These are uniform groups of individuals
subject to relatively uniform exposure,
who are representative of members of the270

population particularly exposed to a
specified facility's source term, based onrealistic scenarios.
This population category (adult, child or
infant) varies from site to site and fromyear to year, as does the group's distancefrom the site.
Lastly, dose estimates reflect a range ofmodeling parameters, including, for example, meteorological data (e.g. locallyobserved wind roses). Taken together,
these parameters, which are specific to agiven site, largely account for the differences observed between one site andanother, and between one year andanother.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

The radiological impact associated witheach of the featured nuclear sites ismuch less than 1% of the public exposure
limit of 1 mSv per year. ASN therefore
considers that in France, environmental
discharge from the nuclear industry has
an extremely limited radiologicalimpact.

© Cathy Vérité/IRSN

VIII.3Figure VIII.5

Dosimetric assessments
for measured
environmental activity
levelsTo ensure compliance with the assumptions adopted in the impact assessment,
operators are required to implement environmental radioactivity monitoring programs(covering water, air, soil, milk, grass, farm
produce, etc.). For many artificial radionuclides discharged by nuclear facilities, theactivity levels measured in the environment
are too low to be measured above the decision thresholds in the various environmental
compartments.
In the case of naturally occurring radionuclides and remanent radionuclides from earlier deposits, an increase in activity
attributable to current nuclear facilities isonly rarely perceptible; this applies, for example, to 90Sr, 137Cs and most 14C, as well as plutonium and americium isotopes.

Example simplified assessment
based on results from foodstuffs
When radionuclides are measured in foodproducts, the doses resulting from eating thefood are generally not attributable (at all, orto any significant extent) to current discharge from nuclear facilities. Assessments
based on measurements cannot be treatedas impact calculations, due to the lack of significant measurements (i.e. measurements
above decision thresholds).
By way of illustration, note that 70% of the
18,600 measurements relating to the biological compartment that were included in thesecalculations were below the decision thresholds. Of the 30% of significant values, only
10% related to edible products, and half ofthese results concerned 40K, a naturally
occurring radionuclide systematically present
and measurable in such samples.

The activity levels taken into account were
the average measured values. For these values, the dose attributable to a consumptionof 1 kg of each of the considered foodstuffs
was calculated. A comprehensive assessment
should include all foods in the diet and allradionuclides, which is not currently achievable using the data available in the RNM
network.
Dose coefficients relate to the effective
whole-body equivalent dose in adults. They
derive from the 1996 Euratom directive. The
doses thus evaluated are shown in Table VIII.2.
This table shows the measured activity's origin (natural, remanent or, less frequently,
anthropic signature) for the various radionuclides and their respective average activity
levels (or isotope ratios).

Table VIII.2 shows a few examples with partial calculations reflecting, for various types
of facility, the local data and the measured
radionuclides most specific to the discharge
liable to be measured in the environment.

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French Population Exposure to Ionizing Radiation

Table VIII.2 - Radionuclide concentrations measured in food products and effective doses in adults corresponding to ingestion of 1 kg (or 1 L) of each type of food

Average(Bq/kg (wet)or Bq/L)Standard deviation(Bq/kg (wet)or Bq/L)

Number ofmeasurements

La Hague

50

13

14

Cow’s milk

La Hague

22

6

85

Fish

La Hague

36

15

30

Meat

La Hague

39

16

4

Fruit

Marcoule

9

5

13

Seafood

La Hague

0.18

0.16

18

Thyme

Cadarache

0.62

0.28

20

Fish

FBFC Romans

0.16

0.05

3

Fish

La Hague

0,14

0,05

18

0.45

0.18

11

Foodstuff

Location

Seafood

Radionuclide

C

14

Co

60

Cs

137

Fish

MarcouleFish

All NPPs

0.16

0.14

15

Lettuce

All NPPs

0.29

0.51

8

Fruit

Marcoule

26

21

13

Cow’s milk

Marcoule

6

3

9

Cow’s milk

Valduc28

3

17

Seafood

La Hague

0.37

0.32

59

Cow’s milk

La Hague

0.03

0.02

14

Fish

La Hague

0.30

0.29

4

Seafood

La Hague

238

Pu

0.009

0.005

28

Seafood

La Hague

239

Pu

0.016

0.008

48

Seafood

La Hague

241

Am

0.1

-

1

Cow’s milk

France

0.051

0.025

17

0.059

0.022

85

HTO

I

129

Sr

90

272

Cow’s milk

La Hague

LettuceMalvési

234

LettuceMalvési

238

Fish

Pierrelatte

234

Fish

Pierrelatte

238

Lettuce

Pierrelatte

234

Lettuce

Pierrelatte

235

Lettuce

Pierrelatte

238

Fish

FBFC Romans

235

Fish

FBFC Romans

238

U

0.04

1

U

0.06

1

U

0.01

1

U

0.02

1

U

0.06

1

U

0.003

1

U

0.06

1

U

1.7E-4

9.7E-53U

1.3E-3

1.3E-3

6

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

VIII.3

Individual effectivedose(µSv/kg
or µSv/l ingested)

Notes on measurements

2.9E-2
1.3E-2
2.1E-2
2.2E-2The measured values for 14C are slightly higher than the
background level (due to natural and remanent activity fromatmospheric nuclear tests) for the La Hague facility, and atbackground level for the Marcoule facility.

5.5E-3
6.0E-4

Value attributable to current discharge

8.1E-32.0E-3
1.8E-3
5.9E-3

All 137Cs measurements lie within the usual range of values
unaffected by facilities (remanent activity from fallout fromatmospheric testing and the Chernobyl accident).

2.1E-3
3.8E-3
4.7E-4
1.1E-4
5.0E-4

These measurements are indicative of a slightly enhanced
tritium background level, compared with an expected value ofapprox. 1 to 3 Bq/kg (wet) without the facility's influence.

The dose values are low, ranging from 8×10-6
to 6×10-2 µSv per kg or per liter of ingested
food products, for each of the measured
radionuclides, regardless of their origin.
These results naturally reflect the veryslight specific activity or activity concentration levels added to the various biologicalcompartments of the environment by nuclear
facilities. In addition, a person would need toeat excessively large quantities of the foodconcerned before reaching the dose limit for
the general public (1 mSv/year).
Concerning the areas near to nuclear power
plants, it has been established, based on the
results of routine monitoring programs aswell as the results of supplemental studies,that almost no environmental impact attributable to emissions is detectable. For example, although it is possible to calculate
theoretical 60Co concentrations2 of around0.000 001 Bq/L of milk, the order of magnitude expected near a nuclear power plant
based on actual discharge, no technicalmeans of measuring such a low activity level
exists.

4.0E-2
3.4E-3

Values attributable to past and current emissions from the site.

3.3E-2
2.1E-3
4.0E-3

Although low, these values are indicative of an anthropic signature,as the 239+240Pu to 238Pu ratio of 0.6 is significantly greater than thatof fallout from nuclear tests (theoretically 0.03).

2.0E-2

Values attributable to past and current emissions from the site.

1.4E-3

All 90Sr measurements lie within the usual range of values
unaffected by facilities (remanent activity from historical deposits).

1.6E-3
2.1E-3
2.5E-3

Balanced values in the range of values generally observed at sites
unaffected by nuclear facilities.

4.9E-4
9.0E-4
2.9E-3
1.6E-4
2.7E-3

Although low, these values are indicative of an anthropic
signature. The 235U to 238U isotope ratio is greater than forthese two isotopes in naturally occurring uranium (0.72%).

7.8E-6
5.9E-52 ­– Assessment performed by SECRE/LME, using
the Symbiose modeling platform withactual emissions data supplied by EDF

IRSN – Report on the Radiological State of the Environment in France in 2010-2011273

French Population Exposure to Ionizing Radiation

VIII.4 Assessmentof theradiologicalqualityof drinking
water inFranceWith effect from January 1, 2005, healthchecks on the radiological quality of water
intended for human consumption is mandatory in France. This monitoring regime isoverseen by the Regional Health Agency(ARS), supported by approved laboratories
using analytical protocols accredited by
the French Accreditation Committee(COFRAC). IRSN provides technical assistance to the Nuclear Safety Authority(ASN) in this area. The Institute plays a role
in approving laboratories (application processing, onsite inspections etc.) and managing changes to the regulatory framework.
IRSN also performs analyses.
Circular ref. DGS/EA4/2007/232 of June 13,2007 defined a two-stage drinking waterradioactivity measurement strategy:• An initial phase of overall analyses, theresults of which are compared to guide values and a quality baseline. Where those values are compliant, the total indicative dose
for an annual consumption of 730 liters ofwater by an adult is assumed to be less than
the reference value of 0.1 mSv/year.
• For non-compliant values, a second phaseof analyses is triggered in order to specifically search for an naturally occurring and,
where applicable, artificial radionuclides
that may be present. The total indicative
dose is then calculated based on the measured activity levels and compared with thereference value.

Principal results
obtained by IRSN in 2010
Between 10 and 20% of analyzed water
samples require specific radionuclide
searches. The radionuclides most commonly
found in samples are radium-226 and uranium-234 and -238. More rarely, polonium-210 and lead-210 may be detected,
and in exceptional cases, radium-228.
Overall, fewer than 5% of analyzed samples were representative of a total indica-274

tive dose greater than 0.1 mS.v/year. The
highest total indicative dose calculated in2010 was 0.91 mSv per year. This result was
primarily due to the presence of lead-210
and polonium-210.

drinking water quality regulations andenforcement methods.

For more information

When the total indicative dose exceeds
0.1 mSv/year as a result of naturally occurring radionuclides present due to the ground's
geological properties, the Regional HealthAgency (supported by ASN) adopts a prudent, pragmatic approach (which may initially entail restrictions on use), taking into
consideration the number of people concerned and any available means of reducing
the radiological activity (for example bydiluting the resource or introducing treatments), as well as any difficulties and inconvenience relating to their implementation.
In the case of uranium, the activity levels
obtained for isotopes 234 and 238 provide abasis for calculating the mass concentrationof uranium, which can then be used to assess
the related chemical risk. The value thus
obtained is compared with the WHO's guideline value of 30 μg/l.
Lastly, radon 222, a naturally occurring gaseous radionuclide, may be analyzed but iscurrently not covered by the applicablenational regulations. These regulations areliable to change in the near future, in accordance with the European Union guideline
issued in 2001 and the WHO recommendation on drinking water. However, it has been
established that the principal risk associatedwith this radionuclide relates to its inhalation.
The results of the tap water radiologicalquality monitoring campaign conducted by
Regional Health Agencies between 2008
and 2009 (see DGS/ASN/IRSN report published in 2011) revealed that 99.83% of the
population received water that complied at
all times with the regulatory total indicative dose limit of 0.1 mSv/year. In addition,a historical assessment (1977-2003) carried out by IRSN in 2010 revealed that 4%of the significant measurements relating to
the presence of radon in monitored water
resources exceeded a level of 1,000 Bq/L.
Most of these results were obtained inareas already concerned by the issue ofradon from geological deposits accumulating in the air inside buildings. Althoughradon in water does not raise any shortterm health issues, DGS and ASN, supportedby IRSN, are seeking to clarify the relevant

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Figure VIII.6

www.sante.gouv.fr/eau-et-radioactivite.html

VIII.5

The total annual doses (i.e. the sum of thedoses by external exposure, inhalation andingestion) for adults and children are shownin Figures VIII.7 and VIII.8, respectively.

30
25
20
15
10
5

201
0

200
8

200
6

200
4

200
2

200
0

199
8

199
6

199
4

199
2

199
0

198
8

0

198
6

In 2010, no food product contributed morethan 1 mSv/year to the dose by ingestion. A
few foods eaten in large quantities may contribute more than 0.1 mSv/year to the dose.
This is the case for Tahitian beef, which isalso eaten on Tubuai, Mangareva and Maupiti, pork in Tahiti, copra on Rangiroa, lagoon
fish on Rangiroa and Hao, and cabbage on
Hiva Oa.

Adult

35

198
4

Population exposure to this residual artificial
radioactivity is mainly due to ingestion andexternal exposure. Exposure via inhalation is
negligible (direct fallout and resuspensionof radioactive dust are now extremely low,
and practically undetectable).

Annual effective dose in (µSv/year)
40

198
2

VIII.5 Dosimetricassessment
for French
Polynesia

Figure VIII.7 - Annual effective doses associated with artificial radioactivity
in adults in French Polynesia since 1982 (µSv/year)

Annual effective dose in (µSv/year)
40

Child

35
30
25
20

This order of magnitude comprises all threecomponents of the "additional" dose, and canbe compared with the total (natural andartificial) dose of 1,000 µSv per year on
average in the South Pacific, as establishedby the SPREP (South Pacific Regional Environment Program) in 1983. The "additional" dose
due to artificial radionuclides in French Polynesia therefore represents less than 0.5% of
the total average dose for the region.

15
10
5

201
0

200
8

200
6

200
4

200
2

200
0

199
8

199
6

199
4

199
2

199
0

198
8

198
6

198
4

0

198
2

The results reveal that the annual ranges
between the minimum and maximum values
for all five archipelagos are broadly comparable for adults and children. The overall
average for the past 20 years is approximately 3.5 µSv/year for children and 4.5 µSv/
year for adults.

Figure VIII.8 - Annual effective doses associated with artificial radioactivity
in children under five in French Polynesia since 1982 (µSv/year)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011275

French Population Exposure to Ionizing Radiation

VIII.6 ASSESSMENT
OF THEDOSIMETRYIMPACT OF THE
FUKUSHIMA
ACCIDENT ON
THE FRENCHPOPULATION
Regarding the consequences in France of the
Fukushima accident, the radionuclides of concern and the principal exposure pathways
were as follows:• I nternal exposure by inhalation ofiodine-131 in the contaminated air mass
as it moved over France (the otherartificial radionuclides, which had far
lower activity levels, represented only
marginal contributions);• Internal exposure due to eating foodcontaining traces of iodine-131 andcesium-134 and -137;• External exposure due to radioactive
deposits formed by atmospheric falloutof radionuclides emitted during the Fukushima accident.
The activity levels of airborne radionuclides
were too low to result in significant external
exposure attributable to the contaminated air
mass.
In view of the very low radionuclide activity
levels measured in the air, and the absenceof significant differences in exposure
between different areas of the country, theassessment is based on the average, minimum and maximum values acquired by IRSN
from mid-March to mid-May 2011 for France
as a whole. These assessments were based on
pessimistic assumptions.

Estimated doses due
to inhalation ofiodine-131
The average values for all measurement
results above the decision thresholds wererespectively 1 mBq /m 3 for gaseousiodine-131 and 0.2 mBq/m3 for iodine-131
in aerosol form. As iodine aerosols were measured at levels above the decision threshold
during a period of 60 days (compared with30 days for the gaseous form, which was measured with a higher decision threshold), the276

60-day value was adopted for both forms,
for the purpose of estimating the activity
concentration ingested over the period:
respectively 60 mBq.d/m3 for the gaseous
form and 12 mBq.d/m3 for aerosols.

Estimated doses due toeating food containing
traces of artificial
radionuclides

The radioactivity intake over the exposure
period is calculated by multiplying thebreathing rate by the ingested activity concentration. The dose can then be determined by multiplying the activity intake by
the dose factor, stated in Sv/Bq inhaled.

Ingestion-related doses were calculated bymultiplying the ingested radioactivity (Bq)by the ingestion dose factor (Sv/Bq
ingested). The ingested activity was calculated based on the specific activity or
activity concentration of the relevant foods(in Bq/kg or Bq/L), multiplied by a foodintake (kg/d or L/d) and by the length oftime during which traces of artificial radionuclides attributable to the Fukushima
accident were detected in the food (d).

The following parameters were estimated forthis calculation:• equivalent doses to the thyroid gland, a target organ for iodine-131, for a one-year-old
child;• effective dose for an adult.
Based on these assumptions:• the equivalent dose to the thyroid gland
due to inhalation of iodine-131 was estimated at 2 µSv for a one-year-old child;
• the effective dose due to inhalation ofiodine-131 was estimated at 0.03 µSv foran adult.
In comparison, the doses by inhalation attributable to fallout from the Chernobyl accident
in France were estimated at between 40 and
470 µSv, for the equivalent dose to the thyriod in a one-year-old child, and between 4
and 46 µSv for the effective dose in adults,
depending on the location in France.

Two scenarios were considered when performing this calculation:• "average" scenario, based on the average
activity levels of the foods and the periods
during which significant values (i.e. above
the decision thresholds) were observed;• "worst-case" scenario, based on the maximum contamination values and contamination assumed to last seven days, which is
pessimistic inasmuch as these relative concentration "spikes" in reality only concerned
each of the considered products for a brief
period (less than three days and in mostcases a single day). Concerning iodine-131
and cesium-134 (a radionuclide that is very
rarely measured above the decision thresholds), there was no background radiation
prior to the fallout from the Fukushima accident, indicating that the measured values are

Table VIII.3 - Contamination values and periods for food products determined for the purpose of
calculating doses by ingestion (Bq/kg or Bq/L)

Leafy
vegetables

Cow’s
milk
Goat'sor
sheep’s
milk

Meat

131

I
measured134

CsmeasuredCsmeasured

137Cs
attributable
toFukushima

Average values in Bq/kg(period: 22 days)

0.53

-

0.35

0.30

Maximum values in Bq/kg(period: 7 days)

2.1

-

1.14

1.10

0.24

-

0.21

0.11

0.66

0.05

0.58

0.48

0.8

-

0.12

0.07

3.1

0.1

0.58

0,53

-

-

0,12

-

-

-

0.28

0.08

Average values in Bq/L
(period: 24 days)
Maximum values in Bq/L
(period: 7 days)
Average values in Bq/L
(period: 37 days)
Maximum values in Bq/L
(period: 7 days)
Average values in Bq/kg(period: 40 days)
Maximum values in Bq/kg(period: 7 days)

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

137

VIII.6
attributable entirely to that accident. In thecase of cesium-137, the background values(due to remanent fallout from atmosphericnuclear testing and the Chernobyl accident) lie in known ranges, enabling background to be deducted from the measurement results and in turn making it possible
to consider in isolation the impact attributable to the Fukushima accident.
Table VIII.3 shows the data thus determinedfor the calculation.
Concerning the food intake, the adult value
was assessed for an individual belonging to
the "farming" socioeconomic category, basedon data for "all of France" taken from themost comprehensive INSEE survey. The foodproduced was assumed to be consumed
immediately (with no decay during storage),and the population was assumed to exclusively consume local produce, which is a pessimistic assumption. A supplemental
assessment was also produced, taking into
consideration high consumption of vegetables and meat, as well as consumption ofgoat's milk instead of cow's milk - a fairlyrare practice that was nevertheless reported
for a few families in the food survey conducted by IRSN in 2004-2005 near the Tricastin nuclear facility (this consumption
scenario is known as the "Tricastin intake").
The 1-2 year-old age range was considered
for children. The assumed food intake featured the following consumption profile:
54 g/d of leafy vegetables, 16 g/d of meat
(beef, veal, horse, lamb, rabbit, etc.) and
320 g/d of cow's milk. For children, only theequivalent dose to the thyroid gland associated with ingestion of iodine-131 was taken

into consideration, as this is the most pessimistic exposure configuration.
Cesium 134 and 137 from atmosphericfallout from the Fukushima accident were
included when calculating the effective
dose, but, in the light of the very low measured activity levels (see Table VIII.3), theircontribution to the dose was minimal.

and a rural lifestyle (10 h/d outdoors), which
is a conservative value. This theoretical estimate of ground deposition is very pessimistic, given the value determined for iodine-131
by measurements made at IRSN's Le Vésinet
facility (see report ref. IRSN-DEI 2011-01).

The calculation results for doses3 due toingestion of foods containing traces ofradionuclides attributable to the Fukushima accident are shown in Table VIII.4.
In comparison, the doses by ingestion
attributable to fallout from the Chernobyl
accident over the period from May to
December 1986 were evaluated as follows4:
the effective dose received by an adult was
between 50 and 300 µSv, depending on thelocation in France;
The equivalent dose to the thyroid gland in
one year-old children living in eastern France
was between 6.3 and 12.7 mSv on average(i.e. between 6,300 and 12,700 µSv).

External exposure
to radioactive deposits
External exposure resulting from the deposition of gamma-emitting radionuclides on the
ground depends on numerous parameters,
including the exposure time (outdoors) andthe type of surface. The resulting effective
dose for adults was assessed using the Astralcode, assuming a maximum deposit5 of 600
Bq/m2 for iodine-131 and ten times less, i.e.
60 Bq/m2 for cesium-134 and cesium-137,

Table VIII.4 - Estimated doses due to food intake, for the two studied configurations offood contamination values and periods (Table VIII.3)(µSv)

Effective dose (µSv)
Adult

Dose for "Average"
scenario
Dose for "Maximum"
scenario

Insee foodintake"Tricastin" foodintakeEquivalent doseto the thyroid
gland (µSv)
One-year-old child

0.06

0.14

25.1

0.08

0.17

43.1

3 – Ecrin database – Values are taken from
Euratom Directive 96/29 (1996 for the effective dose) and
ICRP Publication 67 (for doses to the thyroid gland).
4 – Renaud P. et al. Les retombées de l’accident
de Tchernobyl sur le territoire français Fallout inFrance from the Chernobyl accident. Lavoisier,Tec & Doc, 2007.

5 – The total ground deposit is estimated by adding
together the dry and wet deposits.
Iodine-131 deposition during rainfall was assessed
based on the volume of precipitation during the period from mid-March to mid-June (either in mm or inL/m²), multiplied by the concentration in rainwater,
i.e. 25 L/m² x 0.8 Bq/L = 20 Bq/m².
Dry deposition of iodine-131 was calculated based ona maximum volume concentration of approximately
60 mBq x d/m3 for the gaseous form, and 15 mBq x
d m3. These values must be multiplied by their respective
deposition rates of 0.1 to 0.05 m/s and adjusted by applying a conversion factor of 86,400 s/d, resulting in a dry
deposit of 580 Bq/m².
Total deposition of iodine-131 is estimated to be 580 +20 Bq/m², disregarding decay effects.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011277

French Population Exposure to Ionizing Radiation

The results of this assessment (Table VIII.5)
suggest that the dose due to external exposure to the deposit was no more than
1.6 µSv in the first year, and subequently lessthan 1 µSv/year (decreasing each year thereafter). Iodine-131 contributed to this dose
during the first two months, but was theneliminated by radioactive decay; cesium-134
decays less rapidly (half-life: 2.1 years); after
around a decade, cesium-137 will account formost of the dose (Figure VIII.9).

Assessment of thedosimetric impact of the
Fukushima accident
on the French population

These values represent less than 0.4% of
the maximum values attributable to fallout
from the Chernobyl accident (400 µSv in
the first year).

The effective dose potentially received during
the year following the accident (or a shorter
period, depending on the exposure routeconsidered) is estimated to be less than
1.8 µSv for adults. This dose attribuable to
the Fukushima accident represents less thanThe dose calculations described above are
pessimistic estimates for both adults andchildren. They provide a worst-case indicationof the Fukushima accident's potential dosimetric impact on the French population.

Table VIII.5 - Maximum total effective dose from external exposure due radioactive deposits
formed by fallout from the Fukushima accident (µSv)

After…

Total effective dose equivalent (adult)

2 months

0.4

1 year

1.6

2 years

2.5

3 years

3.3

µSv

1,6
1,4
1,2
1
0.8
0.6
0.4
0.2
0
Aug.-2011
I 131

Dec.-2011
Cs 134

Apr.-2012

Aug.-2012

Dec.-2012

Apr.-2013

Cs 137

Figure VIII.9 - Contribution of the various radionuclides to the total effective dose potentially received by an adult due to external irradiation by the deposit, for a theoretical maximum depositof 600 Bq/m2 of iodine-131, 60 Bq/m2 of cesium-134 and 60 Bq/m2 of cesium-137

278

Among children, the 1-2 year-old age bracket
is the most sensitive to iodine-131 exposure,primarily through food intake with a less significant inhalation component, resulting in an
estimated dose-equivalent to the thyroid
gland representing less than 45 µSv. In comparison, the thyroid gland is constantly
exposed to naturally occurring radioactivity, particularly potassium-40, which is naturally present in all humans, delivering an
average dose of 300 µSv/year to the thyroid
gland in children 1-2 years of age. Note thatthe dose equivalents to the thyroid gland in
one-year-old children living in eastern France
at the time of the Chernobyl accident in1986 are estimated to have been between
6,300 and 12,700 µSv on average.
In conclusion, the doses potentially received
in France in the period following the Fukushima accident are very low. These restults
confirm that at no time did the radioactivity
levels from ar tificial radionuclides(iodine-131, cesium-134, and cesium-137)
measured in the various compartments ofthe environment in France and its overseas
departments, regions and communities
pose a health risk.
For more information
Visit the IRSN website:
http://www.irsn.fr/FR/base_de_connaissances/Installations_nucleaires/La_surete_
Nucleaire /Les-accidents-nucleaires /accident-fukushima-2011/impact-monde/
Pa ge s / 2 - i m p a c t- f u k u s h i m a - f ra n c e .
aspx?dId=471c8be3-2e1f-4fe0-85f31f8aee7a5e9a&dwId=6c699d88-aa0e-4da88523-f24f19ecc83d

1,8

Apr.-2011

0.1% of the annual effective dose due to natural sources of radioactivity, which are estimated to deliver an average dose of
2.400 µSv (in France, this dose ranges from
1,000 µSV to 13,000 µSv, depending on theplace of residence and the related variations innatural radioactivity according to geology andaltitude).

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Read the report ref. IRSN-DEI 2011-01:
http://www.irsn.fr/FR/expertise/rapports_
expertise/Documents/environnement/IRSN_
Analyse-impact-Fukushima-France_012012.pdf

© Noak/Le bar floréal/IRSN

VIII.6

Figure VIII.10 - Using a telescopic boom to collect a water sample in the Gaffière river downstream from the Tricastin nuclear plant.
IRSN – Report on the Radiological State of the Environment in France in 2010-2011279

Radioactivity monitoring information sources and data distribution NETWORKS280

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

IX
Radioactivity
monitoring
information
sources and data
distribution
NETWORKS
IX.1 Internet sites and public information media© Leprieur/IRSN

IX.2 Information released under the terms of treaties
or international agreements

Radioactivity Monitoring Information Sources
and Data Distribution NETWORKS

Providing the public with information regarding environmental radioactivity isfundamental to ensuring transparency regarding nuclear activities. The Nuclear
Safety and Transparency Act, promulgated on June 13, 2006, states:“transparency in nuclear matters covers all measures implemented to uphold the
public’s right to reliable, accessible information” (Article 1). ASN, IRSN andother stakeholders in the French nuclear sector provide information in multiple
forms, both to comply with legal obligations and to address public expectations.

The website launched by the Frenchnational measurement network (RNM) on
February 2, 2010 is a major step forward in
the area of public information services. The
website, which is the leading reference formatters relating to environmental radioactivity monitoring, provides centralized accessto the environmental monitoring results of alldata providers.
IRSN has also developed an Internet site
devoted to radioactivity in the environment. In a two-pronged approach, the site
provides access not only to environmental
radioactivity monitoring results obtained by
IRSN (over one million statistics covering atime scale of more than 45 years) but also
to a very well-stocked document library(including topic sheets, reports, assessments,etc.) that can be read on multiple levels tosuit visitors' specific requirements.
The Internet site operated by the French
Nuclear Safety Authority, ASN, also provides
a wealth of information about the life of
nuclear facilities and, more generally, news
relating to nuclear safety and radiation protection in France.
In addition to complying with regulatory obligations relating to information transparency(including publishing annual reports as
required by the Nuclear Safety and Transparency Act), the principal nuclear operators
implement voluntary information policies via
multiple media (websites, leaflets aimed at thegeneral public, information leaflets presenting
environmental monitoring results, etc.).
Environmental radiological monitoringdata is shared internationally. In application of the Euratom treaty and as partof the work of the Ospar commission(Northeast Atlantic marine environment
protection commission), IRSN releases
the monitoring results obtained in thecourse of its activities on an annual
basis. This data is subsequently used in

282

studies and publications available to the
public through a variety of media.

IX.1. Public
information
websitesand other
media
Internet portal operated
by the RNM
environmental
radioactivity monitoring
network
The RNM database, which contains allenvironmental radioactivity measurements
made by monitoring partners, is accessed via
an information system that provides allstored information to experts and the generalpublic, mainly through a map-based Internet
portal:This website, managed by IRSN, enables web
users to access all the data via a single pointof entry. It also offers navigation options tosuit everyone, whatever their habitual search
practices or needs (geographical search,
subject search, advanced search, etc.). It is
designed to provide rapid, easy access tocomprehensive information relating to the
RNM network (covering regulations, operationand laboratory approvals). The site features
an educational section that explains thenature of radioactivity and how it ismeasured, describes the related biologicaleffects, etc. The aim is to equip site visitors tounderstand the measurement results available
on the site.
Each category of user (novice, experienced or

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

specialist) has access tailored to their needs.
The different user types can access all theinformation in the database in conditions
appropriate to their needs, by drilling
down from the most general information
to the most detailed. In practical terms,
users can use various integrated search toolsthat provide access to data via several routes:• Map-based searches combine browsing
tools and a dynamic key to provide rapid
access to search results;• Topic-based searches use thematic queries to enable non-specialist users toaccess results with ongoing, customized
learning support;• Multi-criteria searches enable professional
users to perform advanced searches, viewsearch results on the map and display thedetailed results.
The map tool can be used to select a region
and provide related information (such as thelocations of major nuclear facilities and sampling points). The results of such queries may
be viewed either in table form or as a chart
showing how radioactivity levels change overtime (Figure IX.1). Where multiple data providers make measurements at the same sampling point, the corresponding results areshown on the same chart, using a color codewith a different color for each data provider.
The reporting screen features a set of tabs
that enable visitors to access additional
information related to results (such as
information about radioactivity in theselected compartment, or values typicallymeasured in the environment) or download
data in spreadsheet (csv) format.
Other sections of the site help visitors tounderstand the stated measurement results(in particular aspects such as uncertainties,
detection limits and decision thresholds), measurement units, etc. Lastly, the home page
contains links enabling visitors to access therespective websites of the national measurement network stakeholders and the principal

IX.1
providers of measurement data in France.
During an average month, more than
17,500 new measurement results areadded. As a result, the national network
provides the most comprehensive view
possible of all the environmental radioactivity measurements made by the variousorganisations involved.

Information about nuclear facilities and sampling(air, water and, soil samples)

ZOOM

Measurement map: access to all browsing solutions(guided search) and to the key

ZOOM

IRSN "environmental
issues" website
IRSN has made a sustained effort in recent
years to disseminate more widely the
resultats of its environmental radioactivity
research and national environmental
monitoring activities, in particular by
publishing a wide range of information on its
Internet site.
This has involved communicating in multiple
areas, ranging from event-related information via a special publication on the home
page of the institutional website www.irsn.fr
to the dedicated "Environment" website usedby IRSN to provide the public with access toall of the results obtained in the course of its
environmental radioactivity monitoring mission.

Accurate information about the source, nature and numberof measurements available

Click

As a major radiological monitoring stakeholder, IRSN also supplies content to thenational measurement network's portal,
which began operating on January 1, 2010.
In March 2009, the Institute opened a new
portal site devoted to environmental
radioactivity: http://environnement.irsn.fr.
Visitors to this site have access toenvironmental radioactivity measurement
results obtained by IRSN, as well as a
document base (Figure IX.2):

Interactive map
An interactive map provides easy access toresults from IRSN's monitoring activities
relating to the various environmental compartments (i.e. atmospheric, aquatic, biological and mineral) at a particular location, bothin the vicinity of nuclear sites and elsewhere
in France. Every day, the mean values
obtained during the previous day at each station in the Téléray network are published.
Measurements for the other networks are
updated monthly. To date, more than one million statistics are available.

Charts and tables showing an overview of the research performed
as well as key data relating to the results
Figure IX.1 - Searching for measurement results via the map module on the nuclear measurement
network's website.

IRSN – 2010-2011 Report on the Radiological State of the Environment in France283

Radioactivity monitoring information sourcesand data distribution NETWORKS

AccessAccès toà
documentla rubriquesectiondocumentaire

AccessAccèstoau
map
modulemodulecartographique

InLaSimple
searchrecherchemode,permet
users
simplede view
consultercanresultslesby résultats
sampling
par typeandmedium,demilieuview thestaticd’échantillonage
etmeasuringl’affichage
instrumentsdes équipements
installed
in an
fixes
de mesurearea. sur
implantésle territoire.

LaInrecherche
Advancedavancée
searchmode,
permetusers can targetde cibler
searchesby date,la recherche
geographicalpar dates,
area
zonesandradionuclide
géographiques
etradionucléides.

Analysis results
Les résultats
mayalso bedes analyses
viewedin theréaliséesFrenchsontoverseas
aussi
departments
andconsultables danslesterritories
DOM-TOM.

Reportingsous
format:Restitution
forme
Measurement
table »« Tableaude mesures

Reportingsous
format:Restitution
forme
Chart
« Graphique»

Figure IX.2 - IRSN "Environment" portal - documentation and interactive map

Efforts are being made to provide access toolder data, thereby placing changing environmental radioactivity in a historical perspective, with graphical representations tomake trends easier to identify. The historical
data accessible on this site varies, dependingon the date that the sampling stations andfacilities began operating. For certain filterbased aerosol collection stations data covering a period of more than 40 years(concerning aerosol filters in particular) isavailable.

284

Document section
The site also features a database of documents
relating to environmental radioactivity inFrance, containing a wide range of publications- from brief summaries to full IRSN reports enabling visitors to find information of a natureappropriate to their particular requirements.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

In addition to annual assessment reports
relating to environmental radioactivity
monitoring in metropolitan France andFrench Polynesia, this section contains a
range of topic-based content:• radioactive atmospheric fallout (fromatmospheric testing of nuclear weapons
and the Chernobyl accident) that affected
the covered area in the past;• IRSN studies and expert assessments
relating to the radiological state of theenvironment.

IX.1
This document section is regularly
enriched with new IRSN summaries andexpert assessment reports on the radiological state of the environment and related
trends.

Internet sites of the principal
data providers andinterested parties

public to obtain additional information
about their activities, their inspection andmonitoring programs and individual expert
assessments. Certain websites also provide
access to the annual public information
report required under the terms of the
Nuclear Safety and Transparency Act . This
report includes a section relating to thenature and results of measurements ofradioactive and non-radioactive wastefrom nuclear facilities in the environment.

EDF • FOCUS

All environmental radioactivity measurement
stakeholders operate websites enabling the

EDF nuclear power plant environmental monitoring portal
EDF has developed a corporate website
devoted to nuclear energy. This portal,
accessible at http://energies.edf.com/
accueil-fr/la-production-d-electriciteedf/- nucleaire-120205.html, provides
access to information on nuclear power
plant operation and the related issues interms of environmental impacts. As well asa set of learning tools, the site contains a
number of overview reports (on environmental monitoring, in particular), that provide the general public with comprehensive,
contextualized information.

Figure IX.3 - Overview of the interactive nuclear
power plant map on the EDF website

The Internet portal developed by EDF also
features a map of nuclear power plant
locations (Figure IX.3 – Map accessible atthe following address: http://energie.edf.
com/nucleaire/carte-des-centralesnucleaires-45738.html). The map provides
access to a detailed fact sheet for eachplant (including a presentation, events,
life of the facility and publications), and to a
dedicated module describing the monitoring plan at each nuclear power plant.
Figure IX.4 shows an example with the SaintAlban nuclear power plant (the map is available at the address http://energie.edf.com/
html/energies/environnement/19/index.
html). Visitors to the site can access a simplified map of the monitoring performed in theimmediate vicinity of the power plant, showing information about the samples collected
and measurements made. Visitors may thenview a map of monitoring points in a wider
area, in a radius of 5 to 10 km from thefacility.
Figure IX.4 - Interface providing access to the overall NPP monitoring system
Example showing the environmental monitoring performed by EDF around the Saint-Alban
facility

IRSN – 2010-2011 Report on the Radiological State of the Environment in France285

Radioactivity monitoring information sourcesand data distribution NETWORKS

Selection of websites run by theleading operators (enterprises
and research organizations)
French National Radioactive Waste
Management agency (ANDRA)
http://www.andra.fr/

ANDRA's website features a detailed presentation of the environmental monitoring
activities at each of its disposal facilities:• CSM waste disposal facility
http://www.andra.fr/andra-manche/pages/
fr/menu7/le-centre-de-stockage/la-surveillance-de-l-environnement-1074.html• CSA waste disposal facility in the Aube
department
http://www.andra.fr/andra-aube/pages/fr/
menu4/le-centre-de-stockage-fma/la-surveillance-de-l-environnement-1091.html• Morvilliers VLL waste disposal facility
http://www.andra.fr/andra-aube/pages/fr/
menu4/le-centre-de-stockage-tfa/la-surveillance-de-l-environnement-1101.html• Comurhex-Pierrelatte
http://www.areva.com/FR/activites-867/lasurveillance-de-l-environnement-du-tricastin--areva-pierrelatte.html• Comurhex-Malvési
http://www.areva.com/FR/activites-870/
la-surveillance-de-l-environnement-decomurhex-malvesi.html• Eurodif
http://www.areva.com/FR/activites-876/lasurveillance-de-l-environnement-du-tricastin--eurodif-production.html• FBFC Romans-sur-Isère
http://www.areva.com/FR/activites-1040/
la-surveillance-de-l-environnement-fbfcromans.html• Tricastin fuel enrichment company
http://www.areva.com/FR/activites-3499/
la-surveillance-de-l-environnement-de-lasociete-d-enrichissement-du-tricastin.html• Socatri
http://www.areva.com/FR/activites-879/lasurveillance-de-l-environnement-du-tricastin-socatri.html

French Navy
http://www.defense.gouv.fr/marine

Areva
http://www.areva.com/
An information leaflet describes the monitoring program and presents an overview of theresults: http://www.defense.gouv.fr/content/
download /148510/1486043/file /PLAQUETTES%20des%20ports%202011.pdf

Areva's website describes the environmental
monitoring activities at each of its industrial
facilities:• La Hague site
http://www.areva.com/FR/activites-1253/
la-surveillance-de-l-environnement-de-lusine-areva-la-hague.html

286

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

French Alternative Energies and Atomic
Energy Commission (CEA)
http://www.cea.fr/

The CEA site also features a presentation of
the environmental monitoring activities inand around its sites, as well as direct accessto all of its nuclear safety and transparency
annual reports:• Cadarache
http://www-cadarache.cea.fr/carte/surveillance/index.php• Saclay
http://www-centre-saclay.cea.fr/fr/Surveillance-environnementale• Grenoble
http://www.cea.fr/le_cea/les_centres_cea/
grenoble• Marcoule
http://www-marcoule.cea.fr (rubriquesécurité environnement)• Fontenay-aux-Roses
http://http://www-dsv.cea.fr (rubriquelettre de l’environnement)
Institut Laue – Langevin
http://www.ill.eu/• The Institut Laue – Langevin website has aseparate page describing the environmental
monitoring in the area near the Institute:
http://www.ill.eu/fr/reacteur-securite-environnement/surveillance-de-lenvironnement/• The site also includes a map showing thelocations of sample points used by thefacility's monitoring program.

IX.1
Selection of websites run byorganizations with an interest inenvironmental radioactivity
monitoring
International organizations• I AEA – International Atomic Energy
Agencyhttp://www.iaea.or.at• NEA - Nuclear Energy Agency
http://www.nea.fr• I CRP - International Commission on
Radiological Protection
http://www.icrp.org• IARC – International Agency for Reseachon Cancer
http://www.iarc.fr• European Commission
http://ec.europa.eu/index_fr.htm• WHO - World Health Organization
http://www.who.int/fr/• U NSCEAR – United Nations Scientific Committee on the Effects ofAtomic Radiation
http://www.unscear.org• CTBT – Comprehensive Nuclear-TestBan Treaty Organization
http://www.ctbto.org/

NGOs, associations and learned societies• Association for Radioactivity Monitoring in Western France (ACRO)
http://www.acro.eu.org/• Independent Radioactivity Research andInformation Commission (CRIIRAD)
http://www.criirad.com• "Sortir du Nucléaire" network
http://www.sortirdunucleaire.org• Greenpeace
http://www.greenpeace.fr• N uclear Protection Assessment
Research Center (CEPN)
http://www.cepn.asso.fr• Scientific Internet portal
http://www.science.gouv.fr• French Nuclear Energy Society (SFEN)
http://www.sfen.org• French Radiation Protection Society(SFRP)
http://www.sfrp.asso.fr• SRP – Society of Radiological Protection
http://www.srp-uk.org• International Union of Radioecology(IUR)
http://www.answeb.net• WISE-Paris – World Institute of Sustainable
Energyhttp://www.wise-paris.org• WNA – World Nuclear Association
http://www.world-nuclear.org

Governmental sites• HCTISN – French High Committee forTransparency and Information on Nuclear
Safetyhttp://www.hctisn.fr• Ministry of Ecology, Sustainable Development, Transport and Housing
http://www.developpement-durable.gouv.fr• Ministry of Agriculture and Fisheries
http://www.agriculture.gouv.fr• M inistry of Labor, Employment and
Healthhttp://www.sante.gouv.fr• Ministry of the Economy, Finance andIndustry
http://www.economie.gouv.fr• M inistry of Defence and Veterans'
Affairs
http://www.defense.gouv.fr• Portal for environmental information
relating to public services
http://toutsurlenvironnement.fr

IRSN – 2010-2011 Report on the Radiological State of the Environment in France287

Radioactivity monitoring information sourcesand data distribution NETWORKS

Publications by
the French Nuclear Safety
Authority (ASN)

IRSN assessmentsof the radiological stateof the environment

ASN operates an information policy basedon a media mix designed to make information accessible to its full audience spectrum.
The website at www.asn.fr is the main sourceof information for the general public. It
relates current issues concerning nuclear
safety and radiation protection in France, andsets out ASN's position in its areas of expertise. The site also provides access to a document base relating to the life of nuclear
facilities via a simplified browser, as well as
enhanced access to data and optimized
downloads of selected new items andpublications.

Since 2004, as well as providing measurement results via Internet, IRSN has published(with a print run of more than 1,200 copies)
annual assessments of its programs to monitor radioactivity in the French environment(Figure IX.6).
This document provides an overview of themonitoring activities carried out throughout
metropolitan France, both within and outside
the area affected by nuclear facilities. IRSN
has been carrying out its monitoring mission
for many years and is in a position to comment on current results and place them inperspective with respect to past decades. A
separate chapter of the report covers any
radiological events that may have occurred in
the course of the past year.
IRSN also publishes annual assessments of its
monitoring activities in French Polynesia,
which date back to 1962.

ASN's annual report on the state of nuclear
safety and radiation protection in France is areference document containing a mine of
information regarding the activities monitored
by ASN in these two areas. ASN also publishes a quarterly journal named "Contrôle", which has more than 10,000
readers in France and other countries. In
2010, ASN published an edition with a feature on environmental radioacivity monitoring (Figure IX.5: No. 188 – July 2010).
These publications and the other materials
produced by ASN (including the ASN newsletter and information sheets and presentation leaflets aimed at the general public)
are available to view and download fromwww.asn.fr. They are also available at ASN's
public information and documentation
centre.

Figure IX.6 - IRSN assessments of the radiological state of the environment

Reports concerning theenvironment around basic
nuclear installations
Operators are subject to certain legal reporting obligations. These include general obligations (such as the Environment report that
corporations are required to produce under
the terms of the Commercial Code) as well as
requirements specific to the nuclear sector.

Figure IX.5 - "Contrôle" magazine no. 188 witha special feature on environmental
radioactivity monitoring

288

The Nuclear Safety and Transparency Act
requires all operators of nuclear facilities to
produce an annual report on their situation
and activities, in particular in the area ofradiological monitoring of the environment inand around their installations. In parallel, theregulatory framework also requires operators
to publish a monitoring annual report, inapplication of the general guidelines on basic
nuclear installations.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Annual report on monitoring ofbasic nuclear installation
operators
The Order of November 26, 1999 sets out
the general technical requirements concerning the scope and operating procedures relating to sampling activities and emissions
subject to authorization by basic nuclear
installations. Under the terms of Article 26 of
the aforementioned order, operators of
nuclear facilities are required to produce apublicly available annual report describing
the operation of their facilities and covering
all inspections and monitoring activities
required by this order and the license.
This report describes water sampling, waste
emissions, environmental monitoring andany impacts and nuisance caused. To thisend, it includes an overview of the analyses
and measurements performed over the previous year, the operator's assessment of any
anomalies or exceeded limits, and its
appraisal of the effectiveness with which
operations were managed. This report also
features an estimate - based on recorded
discharge - of the ionizing radiation doses
received during the preceding year, as aresult of the installation's presence, by thereference population groups as defined in
Article R. 1333-10 of the code.
The report is submitted to the French
Nuclear Safety Authority (ASN), to the
Regional Directorate for the Environment,
Planning and Housing (DREAL), to the
Regional Health Agency (ARS), to the Waterways Police and to the Local Information
Commission. Operators are required to publish this annual report.

Nuclear safety and transparency
reportArticle 21 of the Nuclear Safety and Transparency Act (or "TSN Act") no. 2006-686 ofJune 13, 2006, repealed by Order No. 2012-6
of January 5, 2012 – Art. 7, stipulates that
operators of basic nuclear installations must
produce an annual report describing:• Measures implemented in the area of
nuclear safety and radiation protection;• R eportable incidents and accidents
with nuclear safety and radiation protection
implications, in application of Article 54 of
the Nuclear Safety and Transparency Act(Chapter V: applicable provisions in the

IX.2

Figure IX.7 - Examples of operators' reports produced in accordance with the Nuclear Safety and Transparency Act

event of an incident or accident), that may
have occurred inside the installation's
perimeter, as well as the measures implemented to limit their development and mitigate the consequences for human healthand the environment;• Nature and results of measurements
relating to radioactive and non-radioactive
environmental emissions from the facility;• Nature and quantity of radioactive waste
stored at the site, and measures adopted tolimit its volume and effects on health andon the environment (particularly soil andwater).
This report (Figure IX.7) is submitted to thebasic nuclear installation's health, safety andworking conditions committee, which may
in turn issue recommendations. Any such
recommendations are appended to the document for publication and distribution. This
report is also released to the public. It is
submitted to the local information commission and to the High Committee for Transparency and Information on Nuclear Safety.
The type of information that must be
included in the report is defined in a decree.
Each year, ASN analyzes these documents
and the Authority's annual report includes its
principal conclusions relating to the treatment of topics specified in the law, any strategic considerations, pedagogical aspects oftransparency practices and the right toaccess nuclear-related information (Articles
19 and 21 of the Nuclear Safety and Transparency Act).

IX.2 Information
released
under theterms oftreaties orinternational
agreements
Information relating to environmental radioactivity monitoring is also provided internationally, in particular through the Euratom
treaty and the Commission for the Protectionof the Marine Environment of the Northeast
Atlantic (known as the Ospar commission).

Distribution of Frenchdata in the context of theEuratom treaty
Each year, IRSN, acting on behalf of the French
Government, submits several thousand environmental measurement results concerning
aerosol particles, water, milk and food intake
to the European Commission in order to comply with Articles 35 and 36 of the Euratom
treaty. In addition to these results, raw datafrom the Téléray network is submitted automatically every hour.

The European Commission publishes regular European overviews based on the data
contributed by the various Member States. A
public Internet portal (http://rem.jrc.ec.
europa.eu) enables visitors to view results bylogging in to the various European Commission databases.
Article 35 of the Euratom treaty stipulates
that: "Each Member State shall establish thefacilities necessary to carry out continuous
monitoring of the level of radioactivity in theair, water and soil, and to ensure compliancewith the basic standards". This Article also
asserts that "The Commission shall have theright of access to such facilities; it may verify
their operation and efficiency". Based on theright of access, the Commission delegates theinspection of facilities for the purpose of verifying their operation and efficiency to specialist inspectors in each Member State. In
this capacity, European Commission inspectors visited the Cadarache facility in June
2011, to examine the radioactivity monitoring installations deployed by the CEA (Focus).
Numerous French facilities have beeninspected in recent years, including EDF
nuclear power plants Areva's Tricastin and La
Hague facilities, disused mine workings in the
Limousin area, etc.

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289

CEA • FOCUS

Radioactivity monitoring information sourcesand data distribution NETWORKS

Verification under the terms of Article 35 of the Euratom
treaty at the Cadarache facility in June 2011

Article 35 of the Euratom treaty requires
Member States to deploy adequate
resources (in terms of facilities, equipment
and organisation, etc.) to enable constantmonitoring of the levels of radioactivity inthe atmosphere, water and soil, and toensure compliance with basic standards
intended to protect the health of workers
and the population against the dangers ofionizing radiation. The purpose of thisinspection was to assess the effectivenessof these resources.
In addition to the CEA, for which this was
the first such audit, the French Government was directly involved in the checks.
The audit was attended by representativ es from ASN, DREAL , IRSN, thenuclear safety and radiation protection
mission (MSNR) and the Euratom technical committee (CTE), as well as several
representatives from the CEA's Cadarachefacility.

290© G.Lesénéchal/CEA

A team of three inspectors from the European Commission performed an on-site
inspection at the CEA's Cadarachefacility, between June 20 and June 23,
2011. This inspection was part of the verification program stipulated by Article 35of the Euratom treaty. The main focus
was ensuring compliance with the Article
regarding the resources used to monitor
environmental radioactivity on and aroundthe site, the representativeness of thoseresources, and the means of describingand quantifying emissions from nuclear
facilities.

Figure IX.8 - Ground water monitoring at the CEA center in Cadarache

The purpose of the audit was to verify theoperation of the regulatory emissions
measurement systems and the environmental monitoring programs on andnear the site. Various installations were
inspected to demonstrate the center's
waste management processes to theinspectors, and to show them the various
environmental monitoring facilities(analytical laboratories, environmental
monitoring stations, etc.). A number ofthemes, including maintenance, calibration and data recording, archival andtransmission were also examined via
individual document-based reviews.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

In the light of this inspection, the Commission issued a strongly positive opinion
regarding the resources and organization
implemented, as well as the quality of theresults obtained. This audit has enhanced
the reputation of the CEA and France moregenerally in the area of environmental
radioactivity monitoring.

IX.2
Data submitted by IRSN
to the Ospar Commission
For around the past 15 years, IRSN has
assisted the work of the Ospar Commission,
which is the current legal instrument guiding
internation cooperation aimed at protecting
the marine environment of the Northeast
Atlantic (Figure IX-9). The Commission ismade up of representatives of the governments of the 15 contracting parties (Belgium,
Denmark, Finland, France, Germany, Iceland,
Ireland, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland andthe United Kingdom) and the European Commission.

Its mission is to preserve the marine ecosystems and safeguard human health in thenortheast Atlantic, by preventing andeliminating pollution, protecting the marine
environment against harmful effects ofhuman activities and contributing to sustainable use of the sea.
IRSN submits to the Ospar Commission
radioactivity data relating to the marine
samples collected along the Atlantic-English
Channel coast (from water, sediment, floraand fauna), which was used to establish abaseline or benchmark against which to regularly assess the progress achieved since1998 in terms of reducing the environmental
impact of human activities. The Instituteintends to continue submitting this data on
an annual basis.

Figure IX.9 - The five Ospar regions:• Region I: Arctic waters• Region II: North Sea• Region III: Celtic seas
• Region IV: Gulf of Gascony and Iberian coastal waters• Region V: Offshore Atlantic

IRSN – 2010-2011 Report on the Radiological State of the Environment in France291

Understanding Radioactivity

292

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

X
Understanding
Radioactivity
X.1 The atom and radiation
X.2 Measuring radioactivity© Leprieur/IRSN

X.3 Biological effects of radiation and thevarious exposure pathways

Understanding radioactivity

We live in an environment that is naturally radioactive.
Radioactivity is part of the universe. Without any human intervention,
it is present everywhere on Earth, in matter and even inliving creatures. It comes from several sources including
cosmic radiation, the atmosphere and the Earth's crust.
Food also contains radioactive elements suchas potassium. The human body itself contains radionuclides
and is therefore considered as a source of radioactivity. Radiation
is invisible but it can be measured using very sensitive,
high-precision instruments.

X.1 The atom andradiation
In the natural world, matter is made up ofmolecules formed by a combination of
atoms. An atom (Figure X.1) consists of:• a central nucleus made up of particles,
called nucleons, which are divided into
two types: protons and neutrons.
Nucleons are two thousand times
heavier than electrons;• a peripheral cloud of electrons moving sofast that in a fraction of a second, they
perform a multitude of orbits around thenucleus.
Certain unstable atomic nuclei have thechemical ability to spontaneously transformthemselves into another form, a disintegration process referred to as decaying. When
this occurs, the nuclei emit different typesof rays, those with the greatest amount ofenergy being strong enough to tear electrons away from the atom.
Atoms that have lost a certain number of
their electrons in this way then become positively charged. Nearby atoms that receive
these electrons become negatively charged.
Atoms that are positively or negatively
charged are called ions. The rays capable ofcausing these reactions are referred to as"ionizing radiation", otherwise known asradioactivity.
The different types of ionizing radiation(Figure X.2) are:• cosmic radiation, originating from galactic or solar sources, made up of particles
that move at speeds close to the speed oflight;• electromagnetic waves, which produce
the highest energy levels, i.e. gamma and
X-rays:294

Phosphorus nucleus (P)16 neutrons

Phosphorus atom

15 protons

15 electrons

Figure X.1 - Phosphorus atom.

> X-rays can be generated by projecting
a beam of electrons onto a metal target.
These electrons interact with electrons
from atoms in the metal, causing theirenergy level to change, and thereby generating X-rays;> gamma rays are emitted by radioactive
atoms as they decay. It takes very thicklayers of lead or concrete, for example, tostop gamma or X-rays.
• a lpha, beta plus and beta minus
ra d i a t i o n ( p a r t i c l e s e m i t t e d b yradioactive atoms when they decay):> alpha radiation, formed by a stream ofhelium nuclei (made up of two protons
and two neutrons), can be stopped by asimple sheet of paper;> beta radiation, formed by a stream ofelectrons, can be stopped by aluminumfoil;• free neutrons, which are found mainly innuclear reactors, are emitted, for example,
during fission of uranium-235 atoms. TheyIRSN – Report on the Radiological State of the Environment in France in 2010-2011

are said to be indirectly ionizing because
they generate gamma radiation or various
types of particles when they are captured
by nuclei or come into contact with them.
These neutrons are also found at flight
altitudes of long-haul and subsonic aircraft, and are responsible for 30% of thedose received by flight crews.

X.2
X.1

X- andgamma- rays

Beta
particles

Table X.1 - Examples of radioactive
periods.

Sheetof paperAlpha
particles

Sheet ofaluminum foil
Heavy
gage
concreteor leadNeutrons

Figure X.2 - The various penetrating powers of alpha, beta and gamma rays and neutrons.

X.2 Measuring
radioactivity

atoms involved, and can exceed the lifespanof a human being. As an atom decays, its
radioactivity gradually disappears as theatom evolves to a stable state, where it
becomes non-radioactive.

Radiation from radioactivity cannot bedirectly perceived by the senses as it is invisible, silent and odorless. It was therefore
impossible to detect radioactivity until
humans invented the tools required toobserve this phenomenon, making it possible todetermine the type of radiation involved andaccurately measure its intensity using various instruments.

Two researchers, Rutherford and Soddy, discovered that a radioactive substanceloses half of its radioactivity (i.e. half of theatoms in the substance decay), over a certain period of time that is specific to that
substance. This time period is called the "radioactive period" or "half-life".

Why does radioactivity
decay?
Radioactivity decays over time. The timeframe varies, however, depending on the

Half-life varies (Figure X.3) from one atom toanother (Table X.1). Depending on theradionuclides involved, it may take anywherefrom a fraction of a second to billions ofyears. Uranium-238 has a half-life ofaround 4.5 billion years. This long period
explains why it can still be found on Earth

Activity100%

Half-life

Uranium-238

4.47 billion years

Potassium-40

1.3 billion years

Uranium-235

704 billion years

Carbon-14

5,730 years

Radium-226

1,600 years

Cesium-137

30.2 years

Strontium-90

28.8 years

Tritium

12.3 years

Cobalt-60

5.27 years

Iodine-131

8.05 days

Phosphorus-30

2.55 minutes

Helium-60.82 secondin its natural state. The radioactive period of
uranium-235 is around 700 million years,
which explains why, when compared withuranium-238, only small amounts ofu ra n i u m - 2 3 5 a r e fo u n d o n E a r t h(representing only 0.7% of natural uranium).

Understanding
radioactivity
units of measure
To measure radioactivity and its effects,
three specific units of measure are used: thebecquerel, the gray and the sievert.

Becquerel (Bq)
The radioactivity in a sample is measured
by counting the number of disintegrations ofradioactive nuclei produced per second.
Radioactivity is measured in becquerels (Bq).
1 Bq = 1 disintegration per second

50%

25%
12.5 %
Period 1
Period 2
Figure X.3 - Graph showing radioactive decay.

Chemicalelement

Period 3

TimeThis is a very small unit of measure. For
example, the activity in the skeleton of aman weighing 60 kg represents roughly
6,000 Bq of radioactive potassium. The activity of radioactive s ources is often
expressed in multiples of the becquerel (kBq,
MBq, GBq, TBq), while the activity of environmental samples is expressed in Bq, mBq
or μBq.

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Understanding radioactivity

Activity is often related to volume (activity
concentration in Bq/L or Bq/m3) (Table X.2),
mass (specific activity in Bq/kg) or surface(surface activity in Bq/m2). The old unit ofmeasure for radioactivity is the curie (Ci),defined as the activity of 1 gram of radium,i.e. 1 Ci = 37 billion Bq.
Table X.2 - Order of magnitude of activity indifferent natural radioactive sources.

Rainwater

0.5 Bq/L

Sea water

14 Bq/LMilk

70 Bq/LFish

100 Bq/kg

Human body

120 Bq/kg

Potatoes

150 Bq/kg

Sedimentary soil

400 Bq/kg

Phosphate fertilizer

3,000 Bq/kg

Granite soil

8,000 Bq/kg

This measurement indicates the number ofdisintegrations, but not the energy involvedor the effect on humans. That is why twoother units are used: the gray and the sievert (Figure X.4).

Gray (Gy)
Absorbed dose is measured using the gray(Gy), representing the amount of energy
radiated per unit of mass.
This unit can be used to measure theamount of radiation absorbed by an organism or an object exposed to radiation. The
gray replaced the rad in 1986: 1 gray = 100
rads = 1 joule per kilo of irradiated matter.

Sievert (Sv)
The impact of radioactivity on living organisms or inert matter is not directly related
to the becquerel for several reasons: thedecay of an atom of cesium does notrelease the same amount of energy as thatof an atom of iodine; the rays emitted arevery different in nature; and organisms are
not necessarily affected in the same way.
Furthermore, the effects are different
depending on the parts of the organism
affected by radiation. To take this into consideration, the absorbed dose is multiplied
by a given factor, resulting in the equivalentdose, expressed in sieverts (Sv).

296

Certain tissues and organs are thus moresensitive to radiation than others. To
account for this, the equivalent dose isweighted by a specific risk factor for eachtissue or organ, in order to obtain theeffective dose. The advantage of this systemis that all types of human exposure to ionizing radiation can be assessed according to
the same scale of risk. Because the effective
dose value is generally quite small, it isoften expressed in millisieverts (mSv).

graybecquerel

sievertThe following description gives a simplified representation of the relationship between
these three units of measure. A child throws balls at a friend. Imagine that:• the number of balls thrown is the amount of radiation emitted by a radioactive
source, in other words its activity (in becquerels);• the number of balls that hit the friend represents the absorbed dose (in grays);• the marks left on the body, which vary depending on the weight of the balls and thesensitivity of the areas affected, are the produced effect, representing the effective
dose (in sieverts).
Figure X.4

How is radioactivity
measured?
Radiation from radioactivity can not be perceived directly. Human senses cannot
detect radiation emitted by radioactive substances. All methods used to detect radiation are based on the fact that radiation
creates ionization (i.e. electrons are torn
away from atoms) and excitation (whereenergy is input to atoms, causing them topass from a ground state to an excitedstate), therefore leaving a trace within thematter itself. By calculating the number ofionizations or excitations caused by particles per unit of time, it is possible to measure the energy transmitted to matter
through radiation. This energy represents a
specific feature of the emitting radionuclide.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

The operating principle of the three mostcommonly used types of monitors (gascounters, scintillators and semi-conductors)
is the same: they all convert the photons orelectrons created by radiation into an electronic signal.
The function of most radiation monitors istherefore to separate and count the ions (orelectrons) produced by radiation passing
through the monitor. This process isachieved by subjecting the detector to anelectrical field. In general, radiation penetrates the detection zone inside the monitor, which may consist of a gas, a solid or aliquid, depending on the type of radiation to
be measured. This interaction generates aseries of discrete events involving ionizing
electrons, photons, heat, etc.
Whatever the operating mode of the monitor and the corresponding principle onwhich radiation detection is based, monitors
always consist of the same components:

X.2• a sensor capable of operating within
the range where the radiation in question interacts with matter;• an amplification system that shapes andamplifies the signal produced by the sensor;• a signal processing system, whereapplicable;• a display system that indicates:- particle flow (on a counter);- particle energy (on a spectrometer);- absorbed dose or absorbed dose rate (ona dosimeter or ratemeter).

Uncertainty
Measuring instruments, though highly sensitive, are not infinitely accurate. Simply
stated, there is no such thing as an exact
measurement. Uncertainty is a parameterassociated with the result of a meaningfulmeasurement that describes the possible
range of values in which the true value may
be found within the limits of a predefinedprobability.
Measurement uncertainty comes from thecharacteristics of the measuring device, theoperator, the measuring environment (temperature, vibrations, etc.), the measuring
procedure, and other factors. The value readon the measuring device may be anywhere
within the measurement uncertainty range,
therefore more or less close to the true
value of the quantity measured (Figure X.7).
True valueof the quantity

Figure X.5 - Radio-photo-luminescentdosimeter.

Value read

Measurement
uncertainty
Figure X.6 - Probe for continuous monitoringof ambient gamma dose rate.
Figure X.7- Readout value, true value and measurement uncertainty.

Concepts important to understanding radioactivity
measurement results
BackgroundIn metrology, background shows the countrate generated by just the environment, thecomposition of any reagents used, and theelectronics in the measuring device. Background must be removed from the raw
measured value to determine the activity
actually contained in a sample. In terms of
the environment, background represents alevel of activity that cannot be avoided,
measured at a point that is not affected byany source of artificial radioactivity.

Detection limit
and decision threshold
When searching for very low-level activity,
measurements from a sample may show aresult very close to that obtained while
determining the instrument's background(the signal detected in the absence of theradionuclide that the instrument is designed
to search for).
Given the random nature of the radioactive
decay process, results that are only slightly
higher than the background measured do
not necessarily imply that radioactivity ispresent. Similarly, results that are only
slightly lower than the background do notguarantee that radioactivity is not present.

To reach a decision, analysts must therefore
apply the concepts of decision threshold
and detection limit, which characterize themeasuring techniques used.
The decision threshold represents a countvalue for which, given the statistical fluctuations of the background, it can be statedwith a reasonable amount of certainty thata count greater than this decision thresholdvalue indicates that radioactivity is actuallypresent in the sample measured. The sample
activity and activity uncertainty can then be
calculated.

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Understanding radioactivity

If, however, the measurement from thesample gives a count lower than the decision threshold, it can only be stated, with aquantified probability of certainty, that even
if radioactivity is present but has not been
detected, it is lower than a value called thedetection limit.
Depending on the measuring techniques
used, the detection limit is approximately
equal to two times the value of the decisionthreshold.

X.3 Biologicaleffects ofradiation andthe various
exposure
pathways
Biological effects ofionizing radiation
Humans are constantly exposed to natural
and/or man-made (i.e. artificial) radiation.
Energy generated by ionizing radiation canlead to changes in the cells of living matter,and may consequently lead to lesions.

For the general public, the annual
exposure limit of 1 mSv applies todoses received from sources otherthan natural radioactivity and medical
applications.
If this limit was applied to these twosources, we would not be able to receive
a medical scan, fly in an airplane, go
mountaineering, or live in granite regions.
The maximum permissible dose of 1 mSv
per year, which represents, on an average,
roughly 40% of natural exposure, may
seem high compared to the 0.06 mSv
resulting from human activities other than
medical procedures, and even more socompared to the 0.002 mSv due tonuclear power plants. But in terms ofradiation protection, a dose of 1 mSv isconsidered as quite a small dose.
For people working with ionizing
radiation, the regulatory limit is 20 mSv
per year over a period of 12 consecutive
months (Figure X.8).

Two approaches, epidemiology and live cell
analysis, are used to study the various biological effects of radiation. The impact ofradiation on an organism varies dependingon the dose received and other various factors, such as the source (activity or intensity during operation, type of source,energy, etc.), exposure pathways (time,dose rate, etc.) and the target (tissues ororgans affected, age of the person, etc.).
There are two types of biological effects:• immediate (or deterministic) effects:
intense exposure to ionizing radiation
causes immediate effects on living organisms, such as varying degrees of burns.
Depending on the dose and organ
affected, symptoms may appear within a
few hours (as in the case of nausea andradiodermatitis) or several months later.
Secondary effects, such as fibroses andmSv
Weakest dose level currently
detected with a provencarcinogenic effectWorkers’ regulatory limit andannual permissible exposure
dose likely to be received dueto their professional activities

20
10

2.4

General public’s regulatory limit
and annual permissible
artificial exposure dose (excluding
doses received for medical purposes)

Order of magnitude forannual average exposure
doses caused by discharge from
nuclear power plants in France
Figure X.8 - Examples of effective doses and regulatory limits expressed in millisieverts (mSv) (ASN source).

298

100

IRSN – Report on the Radiological State of the Environment in France in 2010-20111

Order of magnitude
for abdominopelvic
scans

Annual average
exposure dose tonatural ionizing
radiation in France

0.1

Order of magnitude
for mammogram
images0.02

Order of magnitude
for chest X-raysof lungs

0.004
0.002

Order of magnitude forbitewing radiographs

X.3
cataracts, can even be observed years
after irradiation;• l o n g - t e r m e f fe c t s ( ra n d o m o r
stochastic effects): exposure to varying
doses of ionizing radiation can lead to
long-term effects such as cancer andleukemia. The stronger the dose, thegreater the likelihood that it will have aneffect. These effects appear several years
after exposure.
Radio-induced illnesses do not have specificfeatures. There is no biological marker that
distinguishes between, for example, lungcancer caused from smoking tobacco andradio-induced lung cancer.

What are the effects
on human healthof low-level
dose exposure?
Given that there are no directly measurable
effects of low-level exposure, the relatedrisks are estimated by extrapolating datafrom studies on survivors of the Hiroshima
and Nagasaki explosions who were exposed
to radiation, or patients who have undergone radiotherapy, where the exposure
parameters (dose, dose rate, etc.) can varysignificantly. Even if there is a relationshipbetween exposure to ionizing radiation andexcess rates of solid cancer, this relationshiphas not been proven for very low-level
doses. The effects of exposure to doses
below 100 mSv on human health are currently a topic of scientific debate.

Radiation protection
The goal of radiation protection is to prevent or reduce the risks associated with ionizing radiation. To achieve this goal,
radiation protection is based on threeimportant principles that figure in the
French Public Health Code:• justifying activities involving a risk of
exposure to ionizing radiation;• optimizing exposure to radiation so thatlevels are kept as low as possible;• limiting the radiation doses to which
individuals are exposed.
These three fundamental principles stemfrom one general precautionary principle:
the "ALARA" (As Low As Reasonably
Achievable) principle. Moreover, radiation
protection regulations specify that special
provisions are applicable to each of thefollowing three population categories: thepublic, patients and workers.

1

Technical and organizational procedures
implemented to comply with all of theseprinciples are the main focus of regulatory
monitoring carried out by public authorities.
The French Nuclear Safety Authority (ASN)
defines regulations and continuously conducts checks, on behalf of the State, toensure that the radiation protection system
is applied correctly.

2

Radiation exposure
pathways
A distinction is made between external andinternal exposure, depending on how radiation reaches the body.
• External exposure: in this case, the person is not in direct contact with the sourceof radiation and the dose received depends
only on the length of exposure. External
exposure takes place when a person is
exposed to radiation sources that areoutside their body, such as radioactive substances in the form of clouds or deposits on
the ground, sources used for industrial or
medical purposes, etc. Exposure can affectall or part of the body.
• Internal exposure: in this instace, radionuclides usually enter the body through ingestion or inhalation, but can also penetrate
through skin wounds or intraveinously (forexample during scintigraphy procedures); these cases are referred to asinternal contamination. How radionuclides spread within the body depends on
the nature of the radionuclide. Exposure
results from the presence of radioactive
atoms in tissues and organs. It therefore
continues beyond the initial moment ofabsorption, but decreases according to theradioactive period of the radionuclide
involved and its biokinetics. Exposure
periods can be short (as when taking
x-rays), or long (in the case of natural
exposure).

3

1 External exposure to radiation in the air
2 Internal exposure after inhalationand ingestion of contaminated items
3 External exposure to radiation from deposits

Figure X.9

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APPENDICES

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XI
APPENDICES
XI.1 Presentation and analysis of results
XI.2 Glossary
XI.3 References© Leprieur/IRSN

XI.4 Credits and acknowledgements

APPENDICES

XI.1 PRESENTATION
AND ANALYSIS
OF RESULTS
The results analyzed in this report andpresented in graphs and summary tables
cover the period from January 1, 2010 toJune 30, 2011, and to July 10, 2011 forresults in the RNM database. Measurements transmitted beyond that date forthe period considered could not be analyzed in this report. They can, however, be
consulted on the RNM website:www.mesure-radioactivite.fr
Results from the regular monitoring of facilities were affected by fallout in France fromthe Fukushima accident. They are therefore
shown separately so as not to interfere withresults obtained outside this period.
Monitoring results for the marine andcoastal compartment (sea water, sediments,
aquatic fauna and flora) close to nuclear
facilities are given in Chapter IV (Marine andcoastal environment) to allow analysis of all
the data available per shoreline. Similarly,
all passive and active environmental dosimetry results are dealt with in Chapter IV(Atmospheric compartment).
In addition:• The ‘<’ sign indicates that measurement
results are below the decision thresholds ofthe measuring instruments or protocols
used. In graphs, such values are represented
by empty bars (*) or lines stretching to theorigin.
• The letters ‘nm’ in the tables indicate thata parameter or radionuclide has not beenmeasured.
• The averages given are values calculated byweighting the uncertainty associated witheach individual result. An uncertainty is
associated with this average value.
• The results come with comments thatsometimes refer to measurements
obtained previously. In this case, thereport highlights certain chronologicalseries, in particular through specific ‘Focus’
articles.

302

Expression of results as
average values
In order to provide the reader with abroader, more representative perspective ofenvironmental radioactivity measurements, IRSN has chosen to express results
as a single estimator that takes into
account all values measured at a given
point over the period in question, including
values below decision thresholds. Thismethod avoids over-repetition of individual
results in tables or graphs, while remaining
scientifically rigorous.
The selected estimator is a weighted average(m), associated with an uncertainty value (um).
The method consists in taking significant values
with their associated uncertainty value, and substituting a value Y, associated with an uncertainty value Y/2, for values considered below thedecision threshold (< Y). Although this substitution method is not the most mathematicallyaccurate, it does not minimize the possible
impact of values that are not consideredmeaningful.
The best estimator for the average of a set ofvalues Yi associated with uncertainty valuesui (including the previously substituted values),
can be calculated as follows:
Weighted average:
with uncertainty value:
For the following measurement results (Bq/L)
for example:
SampleResultUncertainty

A1

130

20

A2
A3

140
< 160

10

The results table for calculating the weighted
average is as follows (Bq /L):
SampleResultUncertainty
A1
130
20
A2
140
10
A3
160
80
This average is calculated as follows:

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

The associated uncertainty is:

The weighted average for the three measurements A1, A2 and A3 is therefore equal to138.0 ± 9.0 Bq/L.

Rounding
The rounding principle applied for expressing results as an average is aimed at obtaining two significant digits for theuncertainty associated with the result.
When the third significant digit is between 0
and 5, the second digit is rounded down to
the next digit. When the third significant digit
is between 5 and 9, the second is rounded up
to the next digit. Each result is then given to
the same number of decimal places as its
uncertainty.
For the following result, for example:
23.12548 ± 1.58569 Bq/L
• The significant value for uncertainty willbe 1.6• T he result will be expressed as =23.1 ± 1.6 Bq/L
The rules for rounding measurement values
and averages is described in a document
entited: “Moyenne, arrondissage et nombrede chiffres significatifs pour les essais interlaboratoires organisés par le STEME/LEI” Technical document IRSN/STEME/DT/2009 – 07.
(Averages, rounding and number of significant digits for interlaboratory tests organized by STEME/LEI).

Conversion ofcertain resultsfor improved
understanding
For the purpose of analyzing results sent to
the RNM and providing overall, comprehensible data, while minimizing the number ofdifferent units of measure, IRSN has sometimes applied conversion factors to raw
results (for example Bq/kg wet<-> Bq/kg
dry). The conversion factors applied are takenfrom various IRSN databases, such as
En-Cours and Sylvestre.

XI.2
X.1
XI.2 GLOSSARY

National Association of Local Information
Commissions and Committees).

AASQA: Association agréée de surveillancede la qualité de l’air (Approved Air Quality
Monitoring Association).

ANDRA: Agence nationale pour la gestion
des déchets radioactifs (French National
Radioactive Waste Management Agency).

Absorbed dose: amount of energy absorbed
at a point per unit mass of inert matter orliving tissue. It is expressed in grays (Gy).
One gray represents 1 joule of absorbed
energy per kilogram of matter or tissue.

ANSES: Agence nationale de sécurité sanitairede l’alimentation, de l’environnement
et du travail (French Agency for Food,
Environmental and Occupational Health and
Safety).

ACRO: Association pour le contrôle de laradioactivité dans l’Ouest (Association forRadioactivity Monitoring in Western France).

Areva: French industrial group involved
mainly in the fuel cycle and the constructionof nuclear facilities.

Actinide: group of chemical elementswith an atomic number of at least 89(actinium has an atomic number of 89).
Four actinides occur naturally: actinium(89), thorium (90), protactinium (91) anduranium (92). Man-made actinides also
exist, namely the transuranium elements:
plutonium, americium, neptunium, andcurium. A distinction is made between
minor actinides, which cannot be recycled
to generate electricity, and major actinides,
which can be recycled, namely uranium andplutonium.

ARS: Agence régionale de santé (Regional
Health Agency).

Activation: process whereby atomic nuclei
are made radioactive by neutron or gamma
irradiation induced by a flux of neutrons orother particles.
Activity:
numberof
spontaneous
disintegrations - or decays - occurring in atomic
nuclei per unit time. The unit of activity is thebecquerel (Bq).

AS station: stationary aerosol sampling station.
ASN: Autorité de sûreté nucléaire (French
Nuclear Safety Authority).
Atom: the basic unit of matter. It is madeup of a nucleus (neutrons + protons) withelectrons orbiting around it.
Background: in metrology, refers to thecount rate induced by the environment,
reagent composition and instrument
electronics. The background must be
subtracted (using a ‘blank run’) from thegross measured value to determine thenet activity of a sample. In environmental
terms, it represents an activity levelmeasured at a given point, away from any
man-made source of radioactivity, andwhich cannot be avoided.

d’équipements
nucléaires(Nuclear
Equipment Standardization Office). The
BNEN is one of the 31 sector standardization
offices that make up the French national
standardization system headed by AFNOR.
CEA: Commissariat à l’énergie atomique etaux énergies alternatives (French Alternative
Energies and Atomic Energy Commission).
Cesium (Cs, atomic number 55): Toxic
rare metal with characteristics comparable
to those of potassium. The 134 and 137
isotopes are radioactive fission products withrespective half-lives of 2.2 and 30.17 years.
CLI: Commission local d’information (Local
Information Commission.
COFRAC: Comité français d’accréditation(French Accreditation Committee).
Comurhex: An Areva subsidiary with two
industrial sites in France. The Comurhex
Malvési plant in southwest France carries out
the first step in the conversion of uranium
concentrates taken from mining sites into
uranium tetrafluoride (UF4) for electricutilities all over the world. The conversion
process is continued at the Comurhex
Pierrelatte plant in the Rhône valley, where
uranium tetrafluoride is converted into
uranium hexafluoride (UF6), which is the last
step before enrichment.
CRIIRAD:
Commission de recherche
et d’information indépendantes sur laradioactivité (Commission for Independent
Research and Information on Radioactivity).
CSP: French public health code.

Aerosol: suspension of solid or liquid
particles - or both - in a gaseous medium,with negligible fall velocity. Under normal
conditions in the air, aerosols have diametersof less than 100 micrometers, while thefinest particles among them attain just
fractions of a nanometer.
AFNOR:
Associationfrançaisedenormalisation (French Standards Association).
Alpha radiation (symbolized as α): a highly
ionizing form of particle radiation with low
penetration consisting of helium-4 nuclei.
A simple sheet of paper can prevent its
propagation.
ANCCLI: Association nationale des comitéset commissions locales d’information (French

Becquerel (Bq): official international unitof measurement used for radioactivity. The
becquerel is equal to one transformation
per second. The most common multiples
are: mega (MBq) for 1 million becquerels,
giga (GBq) for 1 billion becquerels, andtera (TBq) for one thousand billion
becquerels. The most frequent submultiple
is the millibequerel (mBq) representing
one thousandth of a becquerel.
Beta radiation (symbolized as β): radiationconsisting of electrons with a positive or
negative charge. Propagation can be stopped
by leaving a space of a few meters aroundthe source or providing a barrier using asimple sheet of aluminum foil.

DDCSPP: Direction départementale de lacohésion sociale et de la protection despopulations (Departmental Directorate
for Social Cohesion and Public Health and
Safety).
DDPP: Direction départementale de laprotection des populations (Departmental
Directorate for Public Health and Safety).
Decision threshold: a threshold value
on a measuring instrument above which
it can be considered, with a reasonably
low probability of error, and allowing forstatistical background fluctuations, that acount indicates that radioactivity is actuallypresent in the sample measured.

BNEN: Bureau national de normalisation

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APPENDICES

Detection limit: the detection limit is thelowest activity level that can be detectedby a measuring method under definedconditions, and for a specified confidence
level.
DGAL: Direction générale de l’alimentation(Directorate General on Food Safety).
DGCCRF:
Direction générale de laconcurrence, de la consommation et dela répression des fraudes (Directorate
for Competition, Consumer Rights, andProtection Against Fraud).
DGPR: Direction générale de la prévention
des risques (Directorate General for Risk
Prevention). The DGPR is divided into
the Technological Risks Department,
which deals with radiological risks, theDepartment for the Prevention of Pollution
and for Environmental Protection, and theDepartment for Natural and Water-based
Risks.
DGS: Direction générale de la santé(Directorate General for Health).
Discharge permit: every facility in France
must apply to the Ministries of Industry,
Health, and the Environment for a discharge
permit that sets limits on the liquid andgaseous waste that may be discharged, anddefines the associated inspection conditions.
The permit is granted by government order.
Dismantling: all the operations involved
in removing the structural parts and othercomponents of a decommissioned nuclear
facility. Dismantling can be partial or total.
Dose rate: radiation intensity (energy
absorbed by matter per unit mass and time).
The SI unit is the gray per second (Gy/s).
Dosimetry: assessment or measurement of
the dose of ionizing radiation absorbed by a
substance or an individual.
DREAL:
Direction
régionaledel’environnement, de l’aménagement et dulogement (Regional Directorate for theEnvironment, Town and Country Planningand Housing).
Dose coefficient: dose received per unit
activity by an individual exposed to one ormore types of radiation. It is a general term
and its definition varies with the exposure
pathway considered:304•in the case of internal exposure (inhalation
or ingestion), the dose coefficient isrepresented by the (committed) dose perunit intake(DPUI). It is expressed in Sv/Bq;•in the case of external exposure to a plume,or immersion in water, the dose coefficient isthe dose rate per unit activity concentration.
It is expressed in (Sv/s)/(Bq/m3);•in the case of external exposure toradioactivity deposited on the surface ofthe ground, the dose coefficient is thedose rate per unit surface activity and isexpressed in (Sv/s)/(Bq/m2);•in the case of external exposure to aradioactive deposit located underground,the dose coefficient is the dose rate perunit activity concentration and is expressedin (Sv/s)/(Bq/m3).
In the case of internal exposure (DPUI),
dose coefficients take into account theradionuclides in the body following ingestion
or inhalation, the type and energy of theradiation emitted, and tissue sensitivity toradioactivity (radiosensitivity).
DPUI dose coefficients are calculated using
models that describe the path taken byradionuclides as they travel through different
parts of the body, as well as dosimetricmodels. These models incorporate the latest
available knowledge in radiobiology. Dose
coefficient tables are frequently updated.
Various databases of internal and external
dose coefficients are available, such as theEuratom 96/29 database, or the International
Commission on Radiological Protection
database. The choice of which database to
consult will depend on the exposure pathway
considered.
EDF: Electricité de France. - the Frenchnational electric utility.
Effective dose: sum of dose equivalents
delivered to an individual’s organs and bodytissues, weighted by a factor specific to eachorgan or tissue. It is expressed in sieverts (Sv).
Effluent: any radioactive or non-radioactive
gas or liquid discharged by a facility.
Electron: an elementary particle with anegative electrical charge. It is part of an
atom.

Community. The community was set up
primarily to develop nuclear energy and topool knowledge, infrastructure, and fundingof nuclear energy, and ensure the security ofatomic energy supply through a centralized
monitoring system.
EURODIF: European Gaseous Diffusion
Uranium Enrichment Consortium.
Exposure: the fact of being exposed toionizing radiation (external exposure if thesource is located outside the body, internal
exposure if the source is located inside thebody, etc.).
FANC: Federaal Agentschap voor NucleaireControle (Belgian Federal Agency for Nuclear
Control)
FBFC: Société franco-belge de fabricationde combustibles (Franco-Belgian Fuel
Fabrication Company).
Fissile: term used to describe atomic nuclei
in which fission can be induced by captureof a single neutron. The energy configurationof fissile nuclei is very close to spontaneous
fission.
Fission product: fragments of heavy
nuclei produced by nuclear fission or thesubsequent radioactive decay of nucleides
formed by this process.
Fission: the splitting of an atom’s nucleus
as a result of bombardment by neutrons.
During this reaction, neutrons and ionizing
radiation are emitted and a great amount ofheat is released. Nuclear power plants use
this heat to generate electricity.
Fuel cycle: all the industrial operations
undergone by nuclear fuel. The fuel cycle
includes: extraction and processing of
uranium ore, conversion and enrichmentof uranium, fuel fabrication, spent fuelprocessing, recycling fissile materials thathave been recovered for making new fuel,and radioactive waste management. It iscalled a ‘once-through’ cycle if the spent fuelis not recycled but considered as waste to bedisposed of directly after use in the reactor.
It is known as a ‘closed’ cycle if the spent
fuel is processed and the fissile material
resulting from processing is recycled.

EMM: French naval staff.
Euratom: treaty signed in Rome in 1957 that
established the European Atomic Energy

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Fusion: a reaction in which two light nuclei
unite to form a heavy nuclei. Energy is given
off during this reaction. Research is underXI.2
way to use the energy released by fusion to
generate electricity.
Gamma (symbol γ): high-penetration,but
low-ionization,
electromagnetic
energy emitted when radioactive elements
disintegrate. Protection is provided by
concrete or lead screens.
GCR: gas-cooled, graphite-moderated
reactor. Reactors of this type operated at
Bugey, Chinon and Saint-Laurent-des-Eauxnuclear power plants.
Gray (Gy): unit of energy transmitted tomatter per unit mass (joule/kg) during
absorption of a radiation dose.
Gross α (gross alpha activity): radioactivity
index representing the activity of alphaemitting radionuclides.
Gross β (gross beta activity): radioactivity
index representing the activity of betaemitting radionuclides.
GSIEN: Groupement de scientifiquespour l’information sur l’énergie nucléaire
(Organization of Scientists for Information
about Nuclear Energy).
Helium-4: nucleus consisting of two protons
and two neutrons. This particularly stableassembly can be emitted by heavy nuclei
as they seek stability. It is then known as analpha ray.
ICPE: Installation classée pour la protection
del’environnement(environmentally
regulated facility).

are found in fission products. All forms ofradioactive iodine (131, 132, 133, etc.) areshort-lived (for example, iodine-131 hasa radioactive half-life of 8.02 days). The
exception is iodine-129, which has a half-lifeof nearly 16 billion years.
Ionizing radiation: radiation capable ofdisplacing electrons from matter.
IRSN: Institut de Radioprotection et de Sûreté
Nucléaire (French Institute for RadiologicalProtection and Nuclear Safety).
Isotopes: elements whose atoms have thesame number of electrons and protons, but
a different number of neutrons. They havethe same name and the same chemical
properties. There are currently 325 known
natural isotopes and 1,200 artificial isotopes.
K: chemical symbol for potassium.
Potassium content is generally expressed in
mg/L or mg/kg (milligrams per liter or per
kilogram). One gram of natural potassium
has an activity (β/γ) of 31 Bq, resulting fromthe decay of 40K, a radioactive isotope with amass number of 40.
Matrix: sub-division of an environmental
compartment (atmospheric, terrestrial,
continental aquatic, or marine). Examples:rainwater, soil, vegetable produce, sediments,
mollusks.
Measurement uncertainty: parametercharacterizing the dispersion of values
attributed to the measurement of a physicalvariable.
MES: Suspended matter.

ILL:
Institut
Laue–Langevin(LaueLangevin Institute). International researchorganization located in Grenoble, France. It
possesses a 58 MW research reactor, called
the high-flux reactor (RHF, INB No. 67), used
to generate neutron beams.
INB: Installation nucléaire de base (basic
nuclear installation).
INBS: Installation nucléaire de base secrète(secret basic nuclear installation).

MOX (Mixed Oxide): a mixture of uranium
and plutonium oxides used in fabricatingsome types of nuclear fuel.
MW: megawatt.
Neutrino: elementary particle with noelectric charge and unknown mass, emitted
during weak interactions.

InVS: Institut national de veille sanitaire(French Institute for Public Health
Surveillance).

Neutron: electrically neutral fundamental
particle which, with the proton, makes up
the nucleus of an atom. The neutron causes
the nuclear fission reaction that provides theenergy used in nuclear reactors.

Iodine (I, atomic number 53): an elemental
substance whose radioactive isotopes

Noble gases: gases with no chemical affinitythat do not form compounds readily. The

noble gases are argon, helium, krypton, neon,radon and xenon.
NPP: Nuclear Power Plant.
Nuclear fuel: fissile material forming theactive part of a reactor core. In order for afission chain reaction to take place, naturaluranium, a mixture composed of 0.7%
uranium-235, which is fissile, and 99.3%
uranium-238, which is not fissile, mustfirst be enriched to 4% uranium-235. Thisuranium is used as uranium oxide, which isparticularly stable chemically.
Nucleus: the positively charged central
region of an atom. It contains almost all
the mass of the atom, although it is ten
thousand times smaller. The nucleus iscomposed of protons and neutrons boundby the strong interaction (or strong force).
Opera-Air: IRSN environmental atmosphericradioactivity monitoring network comprisingstationary aerosol samplers (AS) and very
high-volume aerosol samplers (TGD).
Outfall or discharge stack: Facilities
discharge liquid effluent through an outfall,and gaseous effluent through a discharge
stack.
Photon: elementary particle with zerocharge and zero mass that acts as a mediatorof the electromagnetic interaction.
Plutonium (Pu, atomic number 94):transuranium element. Plutonium-239 has a
half-life of 24,100 years.
Proton: positively charged elementary
particle which, with the neutron, makes up
the nucleus of an atom.
PWR: Pressurized Water Reactor. A nuclear
reactor that uses uranium or a mixture ofuranium and plutonium oxides for fuel, andordinary water maintained at high pressure(155 bar to avoid vaporization) as coolant.
French nuclear power is dependent on theuse of this reactor design and the country
has more PWR units in operation than any
other country in the world.
Radiation protection: all the steps taken toprotect the population and workers from theharmful effects of ionizing radiation.
Radiation therapy: use of the destructive
power of radioactivity to destroy diseased

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305

APPENDICES

cells, while minimizing damage to thehealthy cells around them.
Radiation: electromagnetic waves (gamma)
or particles (alpha and beta particles,
neutrons) emitted when radionuclides decay.
X-rays are also electromagnetic waves but
are emitted by electron tubes. The term
‘ionizing’ radiation refers to radiation that
produces ions as it passes through matter.
Gamma, X- and ultraviolet rays and visible
light are similar but do not have the same
penetrating power or capacity to produce
ions.
Radioactive decay: natural decrease in the
nuclear activity of a radioactive substancethrough spontaneous disintegration.
(Radioactive) half-life: the time required forradionuclide activity to be halved. The halflife varies from one radionuclide to another.
Radioactive waste management: all theregulatory or technical provisions madeand operations performed concerning
radioactive waste, from generation up to
and including disposal, aimed at protecting
persons and the environment.
Radioactivity: process in which the nuclei ofcertain elements spontaneously disintegrate
to form other elements, with the emission ofionizing radiation.
Radionuclide: a radioactive isotope ofan element. Examples: 3H: tritium, aradioactive isotope of hydrogen. 14C:
carbon-14, a radioactive isotope ofcarbon.
Radon (Rn): a radioactive gas found allover the world. There are three naturally
occurring istopes (219Rn, 220Rn, 222Rn), which
are the decay products of radioelements
found in soil (235U, 232Th and 238U).
Reactor system: term used to describe typesof nuclear reactors capable of generatingenergy. A reactor system is characterizedby shared specifications, such as the type of
fuel, the moderator, the type of coolant, etc.
Reactor systems include, for example, gascooled reactors (GCR), light-water reactors,
and fast neutron reactors (FNR).
RNM: Réseau national de mesures de laradioactivité de l’environnement (French
National
Environmental
Radioactivity
Measurement Network).

306

RPL: radiophotoluminiscent dosimeter
SCL: Service commun des laboratoires(Joint Laboratory Service Unit), formerly
the DGCCRF (Directorate for Competition,
Consumer Rights, and Protection Against
Fraud) laboratories. Since 1986, the yearof the Chernobyl accident, the SCL has
regularly monitored radioactivity levels in
consumables.
SET: Société d’enrichissement du Tricastin is
an Areva subsidiary located on the Tricastin
nuclear site in the Rhône valley. SET is
the project owner for and operator of the
Georges Besse II enrichment plant.
SICN: Société industrielle de combustible
nucléaire, an Areva subsidiary, produced
nuclear fuel for gas-cooled, graphitemoderated reactors (GCRs) at two plants.
One of these plants (Annecy) has now
been converted for conventional activities,
while the other (Veurey-Voroize) is being
dismantled.
Sievert (Sv): legal unit of dose equivalent(or effective dose) used to determine thebiological effect produced by a given absorbed
dose on a living organism. The dose equivalent
is not a measurable physical quantity but isobtained by calculation. It depends on theenergy transmitted to the tissue and the typeof radiation and tissue involved.
SOCATRI: Société auxiliaire du Tricastin, an
Areva subsidiary, consists of a basic nuclear
installation (INB 138) and a cleanup anduranium recovery facility (ARU).
Spectrometry: method used to analyze theintensity of radiation emitted by a source
according to its energy level. It can both
identify radioelements and specify their‘activity’.
Spent fuel processing: all the operations
involved in extracting fissile and fertilematerials (uranium and plutonium) fromspent fuel for reuse, and for conditioning
various categories of waste in a form
compatible with storage or disposal.
SPRA: Service de protection radiologique desarmées (Armed Forces’ Radiation Protection
Department). The SPRA reports to the
French Central Directorate for Defence
Medical Services.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

Storage: temporary measure for radioactive
waste pending disposal.
Strontium (Sr, atomic number 38):
alkaline earth metal. Some of its isotopes
are very widespread in nature, in particularstrontium-90, which is taken up by bone
tissue and has a half-life of 28.15 years.
TGD station: IRSN very high-volume aerosol
sampling station.
TLD: thermoluminescent dosimeter.
Transuranium elements: group of chemicalelements heavier than uranium (atomic
number 92). The main transuranium
elements are neptunium (93), plutonium(94), americium (95), and curium (96).
U content: uranium content by weightin a matrix, regardless of its isotopic
composition. It can be measured or deduced
from the activity (expressed in Bq) of eachisotope (in which case it is called ‘U content
equivalent’).
Uranium (U, atomic number 92): chemicalelement with three naturally occurringisotopes: uranium-234, uranium-235, anduranium-238. Uranium-235 is the only
naturally occurring fissile nuclide, which is
why it is used as a source of energy.
Waste rock: rock containing such low
concentrations of mineral that it cannot be
economically processed.
Waste: any residue from a production
or transformation process or use, any
substance, material produced or, moregenerally, any good that is no longer of any
use to its owner and that is intended for
disposal.
WHO: World Health Organization.

XI.3
XI.3 REFERENCES
Analyse de l’impact de l’accident de Fukushimaen France (métropole et DROM-COM) à partir
des résultats de la surveillance renforcée dela radioactivité de l’environnement, IRSN/DEI
collective, report IRSN/DEI/2011-01.
Bilan radiologique de l’environnement français– synthèse des résultats de surveillance desréseaux de surveillance de l’IRSN, IRSN/DEI
collective, reports IRSN/DEI/SESURE 200533 (2004), 2007-30 (2005), 2007-72 (2006),
2008-48 (2007), 2009-04 (2008), 2010-06(2009).
Bilan de la surveillance de la radioactivité en
Polynésie française de l’IRSN en 2010 et suivi
de l’impact de l’accident de Fukushima en Polynésie française et Nouvelle-Calédonie, demars à mai 2011, P. Bouisset, report IRSN/
DEI/SESURE/2011-40.
Bilan sur la qualité radiologique des eauxdu robinet en France – 2008 à 2009, ASNDGS-IRSN report, February 2011 (available
on the ASN, DGS, and IRSN websites).
Constat radiologique régional, étude prototype “Val de Loire”, S. Roussel-Debet.,
IRSN report DEI/SESURE/2010-22.
Constat radiologique régional “Vallée duRhône” - État d’avancement fin 2010 - milieu
terrestre, S. Roussel-Debet, L Saey, D. Mourier,report IRSN/DEI/SESURE 2011-02.
Constat radiologique régional. Objectifs etméthode – Application au quart nord-est dela France, D. Claval, report IRSN/DEI/SESURE
2011-11.
Constat radiologique régional Vallée duRhône. État d’avancement du volet aquatique,
L. Saey, S. Roussel-Debet, report IRSN/SESURE 2011-34.
Constat radiologique Vallée du Rhône, rapport
final relatif au milieu terrestre, S. Roussel-Debet,
report IRSN/PRP-ENV/SESURE/2012-06.
Contribution des rapports des isotopes del’uranium à l’évaluation des rejets dansl’environnement, L. Pourcelot, report IRSN/
PRP-ENV/SESURE no. 2009-03.

État radiologique de l’environnement prochede la société 2M Process (Saint-Maur-desFossés) – Incident de contamination au tritium,
IRSN/DEI collective, report IRSN/DEI/SESURE/2011-03.
Exposition de la population française aux rayonnements ionisants, A. Rannou, B. Aubert , P.
Scanff, report IRSN/DRPH/SER 2006-02.
IRSN fact sheets “Les retombées en France desessais nucléaires atmosphériques” – available
on the IRSN website:
http://environnement.irsn.fr/document /site_21/fckfiles/File/internet_surveillance_
e nv i ro n n e m e n t / I R S N _ s e ri e _ f i c h e s _tirs_26_01_2009_web.pdf
IRSN fact sheets “Radionucléides et environnement” – available on the IRSN website: http://
www.irsn.fr/FR/Larecherche/publicationsdocumentation/fiches-radionucleides/Pages/
Fiches-Radionucleides-et-environnement-2938.aspx
Inventaire national des sites miniers – September 2007 – version 2 issued as part of theMimausa program (Program on the heritageand impact of obsolete uranium mines inFrance, created for analysis and archival purposes), report IRSN/MEEDDAT.
L’uranium, de l’environnement à l’homme, H.
Métivier, IRSN series, published by EDP Sciences, 2001.
La radioactivité de l’environnement : le bruitde fond et ses origines ; l’influence du fonctionnement normal actuel des installations
nucléaires, P. Renaud, SFRP congress, Angers,
June 2009.
La surveillance de la radioactivité del’environnement, Contrôle no. 188, review
published by ASN, the French Nuclear Safety
Authority, June 2010.
Le césium, de l’environnement à l’homme, D.
Robeau, F. Daburon, H. Métivier, IRSN series,
published by EDP Sciences, 2000.

Le réseau national de mesures de radioactivité de l’environnement, F. Leprieur, nationalradiation protection congress (SFRP), Tours,
June 2011.
Le tritium dans l’environnement, IRSN/DEI
collective, reports IRSN/DEI/2009-05 and
IRSN/DEI/2010-01.
Les retombées radioactives de l’accident deTchernobyl sur le territoire français, P. Renaud P,
D. Champion, J. Brenot, published by Lavoisier,
2007.
Livre blanc du tritium – groupe de réflexions
menées de mai 2008 à avril 2010 sousl’égide de l’ASN, Autorité de sûreté nucléaire –available on the ASN website www.asn.fr,
Publications, 2010.
Mapping of the geogenic radon potential inFrance to improve radon risk management:
methodology and first application to region
Bourgogne, G. Ielsch , M.E. Cushing , Ph. Combes ,M. Cuney, Journal of Environmental Radioactivity 101 (2010) 813-820.
French National Environmental Radioactivity
Measurement Network (RMN) website.
www.mesure-radioactivite.fr
Rapport de l’ASN sur l’état de la sûreté nucléaire et de la radioprotection en France en 2011,
ASN report, 2012.
Rapport d’analyses en appui à l’inspection
du site de Malvési – Juin 2011, L. Pourcelot,
report IRSN/DEI/SESURE no. 2011-37.
Rapport de gestion du Réseau national demesures de la radioactivité dansl’environnement, F. Leprieur et al., IRSN
report 2004-2005, 2006, 2007, 2008, 2009,2010 and 2011.
Rapport des isotopes de l’uranium dansl’environnement du site nucléaire du Tricastin,
L. Pourcelot, D. Claval, G. Gontier, report
IRSN/DEI/SESURE no. 2011-05.

Le cycle du combustible nucléaire, L. Patarin,“Génie Atomique” series, published by EDP
Sciences, 2002.
Le radon, IRSN thematic series, 2012.

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

307

APPENDICES

XI.4 CREDITS ANDACKNOWLEDGEMENTS

IRSN wishes to thank all RNM contributors(Chapter II), together with the approved
laboratories that are part of the network,for their collaboration in this joint work.

The Report on the Radiological State of theEnvironment in France in 2010-2011 is published by IRSN and coordinated by the Environmental Radioactivity Analysis andMonitoring Department (SESURE), part of
the Institute's Radiation Protection, Environment, Waste and Emergency Management
Unit (PRP).

The IRSN national monitoring program
draws on the technical skills and metrology resources of several of the Institute's
laboratories:• E nvironmental Monitoring and Assessment
Sampling Laboratory (LS3E);• A tmospheric Monitoring and Alert
Laboratory;• Laboratory for Continental and Marine
Radioecological Studies;• C herbourg-Octeville Radioecolog yLaboratory;• Sample Processing Laboratory;• Nuclear Measurement Laboratory;• Environmental Radioactivity Measurement
Laboratory;• the regional branches of the Department
for Radiological Protection Operations andAssistance;• N atural Radioactivity Assessment andAnalysis Section.

Coordination

Fabrice LEPRIEUR

PRP-ENV/SESURE/LS3E

Thomas BOISSIEUXPRP-ENV/SESURE/LS3E

Donato D’AMICOPRP-ENV/SESURE/LS2A

Analysis of IRSN and
RNM results

Christophe DEBAYLE*

PRP-ENV/SESURE/LS2A

Jean-Philippe GOYEN

PRP-ENV/SESURE

EditorFabrice LEPRIEUR*

PRP-ENV/SESURE/LS3E

GIS* mapping

Erwan MANACH

PRP-ENV/SESURE/LS2A

Olivier PIERRARD

PRP-ENV/SESURE/LS3E

Damien TOURNIEUXPRP-ENV/SESURE/LS3E

Nathalie CHAPTAL-GRADOZPDS-DEND/SACIPatrick BOUISSET

PRP-ENV/SESURE/LESE

Denis BOULAUD

PRP-ENV

Dominique BOUSTPRP-ENV/SERIS/LRC

Valérie BRUNO

PRP-ENV/SESURE

Pascale DELABBAYE

PRP-ENV/SESURE

Marie-Odile GALLERAND

PRP-DGE/SEDRAN/BRN

Géraldine IELSCHPRP-DGE/SEDRAN/BRN

Olivier MASSON

PRP-ENV/SESURE/LERCM

Guillaume MANIFICATPRP-ENV/SESURE

Jean-Marc PERESPDS-DEND

Philippe RENAUD

PRP-ENV/SESURE/LERCM

Sylvie ROUSSEL-DEBET

PRP-ENV/SESURE/LERCM

Laure TARDIEU

PRP-CRI/SIAR/GIRO NORD

The following took partin writing and/or editing
this report:

Hervé THEBAULTPRP-ENV/SESURE/LERCM
Together with ASN and the members of the RNM Steering
Committee.
Focus articles

ACRO, AFCN (Belgium), ASN, CEA, DGAL and IRSN
(SESURE, STEME, SEDRAN, SERIS)
Bruno GULDNER

IRSN/PRP-ENV/Groupe
informatique et scientifique

Laure WYCKAERTIRSN/PRP-ENV/Groupe
informatique et scientifique

RNM technical support

308

IRSN – Report on the Radiological State of the Environment in France in 2010-2011

The samples taken as part of this program
come from all over the country. This work
would not be possible without the help ofteams from many organizations, including:• the technical departments of nuclear operators and research centers;• Météo France;• the French Navy;• local government institutions and decentralized departments (town halls, prefectures, regional health agencies);• the French National Agency for Agricultural
and Marine Products (France Agrimer);• the Directorate General on Food Safety(DGAL);• t he Directorate for Competition, Consumer Rights, and Protection Against Fraud(DGCCRF).
For further information, please contact:
IRSN/PRP-ENV/SESURE
31 rue de l’Ecluse
BP 40035
78116 Le Vésinet Cedex

IRSN
Head Office31, avenue de la Division Leclerc
92260 Fontenay-aux-Roses
Design and Production: Chromatiques Éditions
Cover photo credit: H. Lepage/IRSN
Printed on paper from sustainable managed forestsand by an Imprim'Vert-certified printerHead Office31, avenue de la Division Leclerc
92260 Fontenay-aux-Roses
RCS Nanterre B 440 546 018
Telephone(+33) (0)1 58 35 88 88
Postal address
BP 17
92262 Fontenay-aux-Roses Cedex
Websitewww.irsn.fr

Pôle radioprotection environnement - déchets - crise (PRP)
Service d’étude et de surveillancede la radioactivité
dans l’environnement (SESURE)
31 rue de l’Ecluse
BP 40035
78116 Le Vésinet Cedex
Telephone(+33) (0)1 30 15 52 42