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couvIRSN/UK

IRSN
Head office: 77-83, avenue du Général-de-Gaulle – 92140 Clamart
Phone: +33 (1) 58 35 88 88
Postal address: B.P. 17 – 92262 Fontenay-aux-Roses Cedex
Web site: www.irsn.org

Institut de radioprotection
et de sûreté nucléaire

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Contents
PART I : MISSIONS AND ORGANISATION

5
page 6page 7page 8
page

Editorial
Presentation of IRSN
2002 : results of the first year of IRSN
Board of Directors and organisation chart of IRSNPART II : ACTIVITIES
page

10

Protecting human beings and environment. Networks for detecting and measuring radioactivity in the environment. Consequences of the Chernobyl accident fallout in France. A new organisation for IRSN crisis management. IRSN involvement in environment radiation protection. IRSN research programmes in marine radio-ecology. Radiation protection of populations and professionals. IRSN participation in ICRP work
. Expertise and research in neutron dosimetry. Management of accidental exposures. Understanding the ionizing radiation effects

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28

Contributing to the safety of nuclear facilities and transports. Phenix safety review. Studying the safety of PWR fuels. Safety review of nuclear power plants. Research on the PWR core meltdown accidents. Ensuring waste management safety. Expertise used for industrial risk control. Controlling criticality risk
. Assessing transport safety. Reinforcing fire protection[ IRSN ACTIVITY REPORT 2002 ]IRSN/RA2002/72 p./UK

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Ensuring non-proliferation and protection against malevolent actions. Non-proliferation of chemical weapons. Protection against malevolent actions

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Promoting international relations. An Internationally-oriented Institute. Close co-operation between France and Germany

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54

Supporting information and training. Communication based on transparency and education. Training

PART III : QUALITY AND DEVELOPMENT MEANS

56

Proceeding with quality objectives

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Human resources and labour relations: supporting the implementationand the development of IRSN

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IRSN 2002 budget

page

ANNEXES
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IRSN sites

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68

Glossary[ IRSN ACTIVITY REPORT 2002 ]IRSN/RA2002/72 p./UK

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Page 5MISSIONS AND ORGANISATION

Editorial

Jacques Repussard

Jean-François Lacronique

Director General

President of the Board of Directors

The year 2002 will remain an outstanding year for nuclear safety and radiation protection. In fact, it saw the achievementof a long “imminent” reform in the area of risk management, with the creation of a new entity on the one hand, the Nuclear
Safety and Radioprotection Institute (IRSN) for public research and expertise, and the overhaul of the structures in the publicauthorities on the other hand through the creation of the General Directorate for Nuclear Safety and Radiation Protection(DGSNR) and the Nuclear Safety Directorate for Defence (DSND). The major complementary disciplines that are radiation
protection, safety and security, have been joined together today in France, as has as the clear separation of the roles between
authorities, experts and operators.
Beyond combining the resources and personnel from IPSN (Institute for Protection and Nuclear Safety) and part of OPRI (Officefor Protection against Ionising Radiation), into the same public establishment, this reform implies several major challenges forthe new Institute.
The very wide spectrum of the Institute’s responsibilities, materialized through its five ministerial guardianships, shall require
careful management of the resources dedicated to expertise carried out to support public authorities. The contract of agreed
objectives, which will be submitted in 2004, shall consolidate this system, bringing a mediumterm viewpoint.
Furthermore, the independence in judgement which IRSN – public reference expert in its area of competence – must demonstrate,
will be ensured in the long term only if the Institute, through its research efforts, and with the support of the network of
co-operation with its peers on the international level, shows its excellence scientifically as well as the relevance of its technicalpositions.
From this viewpoint, reinforcement of the relations is necessary between expertise and research within the Institute, and thedevelopment of scientific partnerships with French operators involved in nuclear technologies, the national researchorganisations (CEA, CNRS, INSERM, IFREMER…), the institutions ensuring missions in other risk areas (INERIS, InVS, AFSSA,AFSSE, INRS...), and the foreign Institutes (GRS in Germany, NRPB in the United Kingdom, NRC in the USA...).
Lastly, the confidence granted by our fellow citizens for the national system implemented to manage risks related to radiation
implies continuous efforts to inform, openness towards the population and training development, a responsibility which IRSN
shall fully assume.
In the autumn of 2003, mostly due to preparatory work conducted until the spring by Daniel Quéniart, to whom we pay homage,a new organisation of the Institute will be implemented, with the mission to face up to all those challenges.
The nuclear safety and security issues, the requirements for health, safety and protection of the environment within theframework of the national strategy of sustainable development, create an obligation of success. Thanks to the significant andinternationally recognized amount of scientific knowledge, expertise, scientific and technical tools, of which this first annual
report provides a short overview, we can certainly achieve this success.

Jacques Repussard

Jean-François Lacronique

Director General

President of the Board of Directors[ IRSN ACTIVITY REPORT 2002 ]5

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Page 6MISSIONS AND ORGANISATION

Presentation of IRSN

> Preventing nuclear
and radiobiological risks
he Nuclear Safety and Radioprotection Institute is a
public scientific and technical expert organisation,
specialising in the assessment of risks due to ionisingradiation, particularly in nuclear facilities and duringtransport of nuclear materials.
Both main missions of IRSN are complementary: researchenhances knowledge and expertise provides technicaladvice; research represents the basis of a quality
assessment of the most complex issues.
More specifically, the main areas of activity of theInstitute cover the safety of nuclear facilities andtransport of nuclear and fissile matter, the protection ofhuman health and the environment against ionisingradiation, protection and control of nuclear matter,protection against malevolent actions and crisis
management.
IRSN maintains partnerships with nearly 30 countries andtakes part in large-scale research programmes. It takes
part in the development of international scientificand technical consensus and in the development ofinternational recommendations.

T

IRSN is a public establishment of an industrial andcommercial nature created by the law of May 9th, 2001.
Its missions and operations are defined in a decree ofFebruary 22nd, 2002.
The creation of IRSN is part of the reform regarding thecontrol of nuclear safety and radiation protection in
France, which follows the general pattern of the creationof health security agencies and clarifies the roles of thedifferent actors by separating the implementation andthe promotion of nuclear power programmes, control
authority functions and technical assessment functions.

6[ IRSN ACTIVITY REPORT 2002 ]Technical assessment functions are entrusted to IRSN,
control authority functions for facilities and civiltransport being ensured by the General Management of
the nuclear safety and radiation protection under the
auspices of the Ministries of Industry, Environment and
Health. IRSN is in charge of technical activities previously
carried out by IPSN (Institute for Nuclear Protection and
Safety) and OPRI (Office for Protection against Ionising
Radiation). It is placed under the joint guardianship ofthe Ministries of Environment, Industry, Research, Healthand Defence.
With a budget of about 250 million Euros, IRSN employs
1,500 experts and researchers, covering various disciplines
from life sciences to physics of nuclear reactors.
In 2002, IRSN had a provisional organisation, with themembers of the Board of Directors being appointed at
the beginning of 2003, as were the President of the Boardand the Director General.

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Page 7

2002: resultsof the first yearof IRSN
Daniel Quéniart
Director Advisor

From the end of February 2002 to the appointment of the Director General in March 2003, I ensured the functions of the
IRSN provisional administrator, born of the meeting of the technical teams of IPSN — now separated from CEA — and OPRI.
During this transition period, it was essential to carry on ensuring correctly all the research and expertise technicalmissions, previously conducted by IPSN and OPRI, and especially the technical support of the various administrations
concerned. The 2002 activity report seems to testify that a good technical vitality brought by the new Institute, ismaintained.
Building its operation by joining teams from two organisations with different modes of thought and management, thus
ensuring for the former OPRI and the former permanent secretary of the Inter-ministerial commission for artificial radioelements (CIREA), a clear separation between expertise functions and authority functions (now assumed by the DGSNR),
managing relations with CEA with a very large part of the personnel made available by the CEA and which can adopt
for three years their maintenance in the CEA staff, represented new and formidable challenges, even if the long lead timeof IRSN had allowed deep-rooted preparatory work conducted by the IPSN and OPRI directors.
After one year of existence, IRSN has a large part of the units and texts required for its operation:– The members of the Board of Directors, except for personnel representatives, have been appointed, by decree dated
January 3rd, 2003; the Chairman of the Board was appointed by decree dated January 21st, 2003;– Upon the suggestion of the latter, the Director General was appointed by decree dated March 17th, 2003;– The work committee held its first meeting on February 25th, 2003 and the negotiations concerning the company agreement have progressed (agreement signed by the Director General and four labour organisations on May 26th, 2003);– With the exception of the convention related to the use by IRSN of the CABRI and PHEBUS reactors, whose
implementation was difficult and which was signed on June 20th, 2003, the texts governing the daily relations between
CEA and IRSN regarding safety, personnel, premises and technical support were, with a single exception, signed
between September 2002 and February 2003; the convention regarding the transfer of means, rights and obligations
has not been yet finalised, but is now well in progress.
– A decision from the Prime Minister’s office established at 58 the number of ex-OPRI and ex-permanent secretary of
CIREA positions deployed to authority missions previously exercised by these units; for obvious reasons concerning
personnel management, this decision can only be implemented gradually, as the effective personnel movements
depend on voluntary agreements;– The income tax system of IRSN was set by the fiscal legislation branch in August 2002 and January 2003.
However, the scientific committee remains to be created and the orientation committee related to defence-related
activities has not yet met.
Above all, the pooling of cultures and the synergy of the teams remain to be improved. First steps were made in thisdirection. Common values — competence, independence, transparency, responsiveness, creativity — were defined and anorganisation draft for the new Institute was is underway. Nevertheless, the implementation of the organisation had
to be deferred in the absence of a Board of Directors; the related work have since resumed by the new management teamto give IRSN and its personnel renewed confidence after years of uncertainty.

Daniel Quéniart
Director Advisor[ IRSN ACTIVITY REPORT 2002 ]7

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Page 8MISSIONS AND ORGANISATION

Board of Directors of IRSN
Qualified personalities

Chairman
Jean-François LACRONIQUE

Jean RANNOU

President of the Board of Directors

Air Force general

Jacques VERNIERState representatives
Emmanuel DUVAL
Armament inspection manager, representing the
Minister of DefenceMarie-Claude DUPUIS
Director of the industrial environment department, Department for the Prevention of
Pollution and Hazards, representing the Ministerof the Environnement

Thierry MICHELON
Deputy Director of environment risk management, General Directorate for Health (DGS),
representing the Minister for Health

Douai Mayor

Maurice LAURENT
Former Department Manager of the National
Assembly

Dominique GOUTTE
Director of the major heavy ion accelerator

Claude BIRRAUXMember of Parliament

Personnel Representatives
The election of the personnel representatives
will be held on September 9th, 2003.

Stéphane GRIT
Branch manager of nuclear industry, General
Directorate for Energy and Raw Materials(DGMF), representing the Minister for Industry

Bernard FROIS
Director of the “Power, transport, environment,
natural resources department”, Technology
Department, representing the Minister for
Research

Philippe SIMÉON-DREVON

Government commissioner
Philippe VESSERON
Director for the Prevention of Pollution andHazards

State controller
Daniel RACINETManager of the national mission supporting
nuclear risk management, representing the
Minister for Civil Security

Jean-Denis COMBREXELLE
Director of the Labour Relations, representing
the Minister for Employment

Nicolas VANNIEUWENHUYZE
Office manager, Budget Department, representing the Minister for the Budget

André-Claude LACOSTE
Director of Nuclear Safety and Radiation
Protection

René PELLAT
Delegate for nuclear safety and radiation protection for activities and installations concerned by national defence provision

The first board of directors of the IRSN met on May 19th, 2003.

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Page 9Organisation chart on July 10th, 2003
IRSN management
Director General: Jacques REPUSSARD ● General Deputy Director: Michel BRIÈRE ●Director Advisor: Daniel QUÉNIART ● Assistant Director for Protection: Annie SUGIER ●Assistant Director for Waste Safety: Michèle VIALA ● Assistant Director to the Director in
Charge of Programmes: Catherine LECOMTE ● Assistant Director to the Director in Chargeof International Relations: Jean-Bernard CHÉRIÉ ● Secretary General: Jean-Baptiste
PINTON ● Deputy Director in Charge of Human Resources and Administrative Affairs:
Louis CROUX ● Assistant Director for Communication: Marie-Pierre BIGOT ● Head of
Quality, Safety, Security and Environment Division: Alain BARDOT ● Advisor for Radiation
Protection: Philippe HUBERT ● Official representative for crisis organisation: Bruno
DUFER ● Internal auditor: Jean-Claude SAEY.
Director of Vésinet site: Philippe JAMET ● Deputy Director: Jean-Luc PASQUIER ●Director of the Safety Assessment Department: Jean-Christophe NIEL ● Director of the
Department for the Prevention and Study of Accidents: Michel POURPRIX, interim ●Director of the Department for Human Health Protection and Dosimetry: Patrick
GOURMELON ● Director of the Department for the Protection of the Environment:
Jean-Claude BARESCUT ● Director of the Security Research Department: Joseph LEWI ●Director of the Department for the Security of Radioactive Materials: Denis FLORY.

Delegate Treasurer
Jean-Claude DALE

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Page 10

IRSN
Protecting human beingsand environment
ontributing to the protection of the environment and human health, being able to answer
precisely the authorities and public inquiries on
the impacts of ionising radiation sources on theenvironment and health, are the main objectives of
IRSN. To meet efficiently those objectives, the Instituteperforms measurements and conducts studies and also
develops research programmes to improve the state ofknowledge.

C

The most recent OPERA1 station was
implemented in Arles in March 2002.

32,000For the monitoring of workers
handling radio-elements or
exposed to such radio-elements,
IRSN performed 32,000
radio-toxicological analyses on
biological samples in 2002.

260,000
The SISERI database
implemented by IRSN lists
260,000 workers exposed toionising radiation.

1.9 million
1.9 million of dosimeters
operated by IRSN in 2002.

10[ IRSN ACTIVITY REPORT 2002 ]The areas covered are very wide. Concerning theenvironment, the objective is to measure and study
the consequences of human activities on natural environments: measurement and observation networks,
radio-ecology works in terrestrial and marine environments, study on radionuclide bio-accumulation in theenvironment, research on “natural” radioactivity…
Concerning human health, radiation protection
involves populations in general, but also workers andpatients more specifically exposed to ionisingradiation. The objective is to assess the exposure ofdifferent populations in various conditions, as forexample, by chronic incorporation of radionuclides
and the resulting risks, but also to deepen the knowledge of the physical and biological effects induced byirradiation in ordrer to develop appropriate therapeutic responses. In case of accident or incident, theInstitute uses its competencies to assess it and makessuggestions regarding the measures to be taken inorder to minimize its consequences. A crisis centre ispermanently on duty to respond to such situations.

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Page 11ACTIVITIES[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]> Networks for detecting and measuring
radioactivity in the environmentI

RSN ensures nationwide permanent monitoring of
ambient radioactivity levels in various environments (air, water, soil, food…) which people may bein contact with. Merging IPSN (Institute forProtection and Nuclear Safety) and OPRI (Ionising
Radiation Protection Agency) into a single organisation allows IRSN to have a complete and consistent
set of measurement networks. Those networks coveralerts (detection of an incident or an accident, location of anomalies), the monitoring of industrial
installations and the understanding of transfers to
the environment (phenomena modelling). This monitoring contributes to the appraisal of the doses
received by populations and to the assessment of the
impact of human, industrial or medical activities on
the environment.
Today, IRSN is based on three complementary networks:– Fully automated alert stations (Téléray, Hydrotéléray,Téléhydro and Sara) providing a real-time alert in case ofabnormal increase of radioactivity or ambient radiation;– 300 sampling stations, located in the environment,
generally near nuclear sites and around former mining
or industrial sites. This network measures natural andartificial radioactivity in the air, atmospheric dust, waterand soils. Foodstuffs and drinking water are monitored
as well as are fauna and flora. The network contributes
to check that operators observe their requirements
regarding radioactive effluent releases;– Observatories: This network, which includes 34 stations,is called OPERA1 ; it is used to measure radioactivity,
up to the level of traces, in samples collected in theenvironment. The purpose is to understand the processes controlling distribution, in time and space, of theradionuclides of natural and artificial origin comingfrom various environments, including the food chain.
The knowledge of radioactivity levels is necessary formodelling the transfer processes of radionuclides in theenvironment. This network is also used to develop
measurement databases essential for the scientificstudies on the variability of the observed radioactivity
levels.

Today, all networks cover the entire territory of France.
Every year, more than 36,000 samples are taken from thevarious compartments of the environment, including
agricultural foodstuffs. They are subject to more than
100,000 laboratory analyses, focusing on the different
alpha, beta and gamma emitters. Moreover, there arethousands of results permanently produced by continuous measurement systems (alert stations) of radioactivity in the air, atmospheric aerosols and water from themain rivers.

ALERT STATIONS

Téléray: National network measuring continuously
monitors ambient gamma radiation. In 2002, a newradiation probe was installed in the Château deVincennes, in the Paris region, bringing the number ofstations to 180. Technical improvements in electronics(modem, transmission speed…) will allow to acomplete modernisation of the network as of 2003.
A direct link was installed at the beginning of 2002
between technical the crisis centre of IRSN in
Fontenay-aux-Roses (Hauts-de-Seine) and the control
centre for intervention resources located in Le Vésinet(Yvelines).
Téléhydro: Network continuously monitoring theradioactivity of wastewater in big cities. The installation in 2002 of 4 new radiation probes in Lyon
(Rhône), Rouen (Seine-Maritime), Strasbourg (BasRhin) and Nantes (Loire-Atlantique) brings the numberof operational stations to 8.
Moreover, an autonomous and remote access mobile
device, used for punctual measurements, was produced
and has been available since the end of 2002.
Hydrotéléray: Network continuously measuring
radioactivity of water from big rivers. This network
now comprises 6 stations, including the Agen (Lot-etGaronne) radiation probe installed on the Garonneriver under the Layrac bridge.
Sara: Network measuring the alpha, beta and gamma
activities of aerosols. In 2002, 5 new radiation probes
were installed in Biarritz (Pyrénées-Atlantiques),
Montélimar (Drôme), Strasbourg (Bas-Rhin), Lille (Nord)and Brest (Finistère), bringing the number of equipment
implemented in the airport meteorological stations to 11.

1. OPERA : Observatoire PErmanent de la RAdioactivité.

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Page 12ACTIVITIES> Consequences of the Chernobyl
accident fallout in FranceT

he Chernobyl (Ukraine) accident fallout is still
subject to studies and working groups on theassessment of the catastrophe’s impact on the environment and health, and on the lessons to be drawn
for crisis management. The Institute has, for a longtime, implemented an organisation, reinforced since
the creation of IRSN, intended to bring technicalsupport to the authorities in case of nuclear accident.

Research to reinforce expertise
To improve its expertise capacities in the radioecologicalarea, IRSN develops scientific programmes. The purposeof the CAROL (CAmargue RhÔne Languedoc) programme
was thus to determine the origin of the radionuclides
present in measurable quantities in the lower Rhône
valley and to foresee their medium and long-term
development. This project covered all environments:
atmospheric, terrestrial, aquatic, continental and marine,
and was used to respond to many inquiries. As an example,
the study of the origin of the 137Cs present in soil wasused to quantify the relation between the deposits resulting
from the Chernobyl accident and the rains of the firstweek in May 1986, period during which contaminated air
masses passed over France; it led to modelling a map of137Cs deposits in France due to the accident. This map canbe superimposed to the map displaying the fallout of theatmospheric tests of nuclear weapons, reproduced frommeasures performed by OPRI since 1961. It is therefore
possible to provide data on the level and origin of thecurrent 137Cs activities in French soil.
Another application of IRSN research involves the studyof the Chernobyl accident fallout in Corsica. Upon therequest of the public authorities, three sampling andmeasurement campaigns were performed in Corsica by
OPRI and IPSN in 2001. Their purpose was to check theassessments of deposits, reproduce as far as possible foodchain contamination in 1986 using the measurements
performed at this time, and determine current foodcontamination levels. The thyroid doses likely to havebeen received by children having lived in the most contaminated areas were assessed. The study was the subjectof publications and a public introduction in Ajaccio(Corsica) in January 2002.

which may result from this. This study, performed incollaboration with French and international universities,
was used in particular to produce predictive mapping,on catchments area scale, of the surfaces likely to show
radioactivity concentration points.
STUDY GROUPS

To improve answering questions regularly asked by the
media and the public about the Chernobyl accident, IRSN
implemented a study group including personalities fromvarious areas: members of local information commissions(CLI), journalists, academics, experts from the Institute.
Reflection focuses for example on the quality andrelevancy of the measurements performed in 1986, themapping of soil contamination, the consistency of dose
calculations, the effects of thyroid contamination, etc.
The work of this group led IRSN, for its part, to produce
the modelling of a complete mapping of French soil
contamination by 137Cs. This map will be submitted to theEuropean Commission, to replace the map currently
displayed in the publications of this Commission(“European atlas”). Besides, in August 2002, the Ministerof Ecology and Sustainable Development and theMinister of Health entrusted Professor Aurengo withthe task to set a mapping of French territorial contamination following the Chernobyl accident, in order toassess the risks of population contamination and thedoses received. IRSN is actively engaged in this work.
It provided the results of the measurements it performed
from 1980 to 1999 as well as all the reports published by
IPSN (Institut for Protection and Nuclear Safety) since1986 concerning the accident.

Lastly, within the framework of a “workshop area” ofabout 1,000 m2 located in the Mercantour region(South-East mountain range), a study focused on theorigin and localisation of radioactivity concentration
points in high altitudes and on food chain contamination
Soil sampling in Corsica to measure the quantity ofCesium-137 currently present.

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Page 13[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]> A new organisation for IRSN
crisis managementn case of a nuclear or radiological accident, IRSN
deploys an organisation and resources to advise
public authorities. It is in particular able to rapidly
provide information to nuclear safety authorities(DGSNR, DSND) including technical information
about the nature and severity of an accidental
situation affecting a nuclear facility as well as its
possible development and the consequences
which might result for the population and theenvironment. In addition, it suggests appropriate
protective actions to be implemented in the field.
In case of effective release of radioelements, theInstitute collects and processes all measurement
results of performed to distinguish the contaminated area and suggests appropriate measures torestore the environment.

I

An appropriate organisation for the situation
To respond efficiently to its missions, the Institute has anorganisation enabling it to provide a diagnosis of thesituation and a forecast on its development:– An on-call team, comprising 14 agents, able to react inless than one hour on a 24/7 basis;– A technical crisis centre (CTC) in Fontenay-aux-Roses(Hauts-de-Seine), available on a 24/7 basis. In case ofcrisis, it can gather a team of 20 to 25 persons,equipped with specific means: telecommunications,documentation, computer systems and databases,
including mappings. This team transmits technicaladvice and information to public authorities in order toensure the protection of the population;– A mobile unit responsible for locally coordinating measurements, transmitting these to the CTC for all thenecessary technical elements needed to carry out its
expertise and performances
and, if necessary, health controlof the populations. It has mobile
IRSN experts aremeasuring equipment, emeravailable to be
gency vehicles and specialised
vehicles that can be usedmobilised at thedepending on the severity of thetechnical crisis
event (seven lorries, two trailer
centre.
trucks and one rail vehicle). Thisis deployed by the control centre of the intervention
resources in Le Vésinet (Yvelines), in permanent contact
with the CTC.

250

Merging IPSN and OPRI technical activities allows IRSN to
now dispose of a wide range of technical resources. In
2002, coordination of those various means was implemented, allowing their complementarities to be used to improve the Institute’s expertise in case of crisis: joining on-callteams, centralising information towards the CTC ofFontenay-aux-Roses (Hauts-de-Seine), implementing themobile unit… This synergy results in more direct and rapid
exchange between the CTC expert team and the mobile
unit in the field. Twelve crisis exercises were performed in
2002: eight concerned EDF installations, one concerned the
La Hague (Cotentin) plant, one concerned Laue-Langevin(Grenoble in Isère) institute, one concerned CEA installations in Cadarache (Bouches-du-Rhône) and one concerned a transport of nuclear materials. In addition to IRSN
staff, each of those exercises mobilizes public authorities
as well as operators locally and nationally. Those exercises
are used in particular to assess the exchange between
the various actors. Furthermore, computer tools developedby IRSN to assess the possible development of an accident
and the possible consequences on the environment and on
the populations of a release of radioactive materials aretested under these circumstances.

A CD-ROM ON NUCLEAR RISK FOR
LOCAL DECISION-MAKERS

Faced with the difficulties encountered by local actors
to represent clearly what a nuclear accident would
entail, in 2000 the Institute created a CD-ROM entitled “Information on nuclear risk and its management”.
After the preparation of the necessary technicalinformation, the definition of specifications anddesign, animated sequences were defined in 2001
with the assistance of a multimedia company. In 2002,
a call for tender enabled the selection of the company
to produce the CD-ROM. Its distribution was scheduled for June 2003.

The crisis technicalcentre in operation.

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Page 14ACTIVITIES> IRSN involvement in environment
radiation protectionW

ith the increase in environmental concerns, aninternational consensus was established on theneed to implement, beyond the protection of humanbeings, a system intended to protect the environment
against the ionising radiation effects. The assessmentof the risk associated with the presence of radionuclides
in the environment implies the development of new
research orientations in radioecology (study of thechronic accumulation of low-dose radionuclides, consideration of the multipollution phenomena (metals andradionuclides)… Within this framework, IRSN launched
two new research programmes to acquire knowledge
and develop indispensable tools for the implementation of a method to assess radioecological risks.

The ENVIRHOM programmeStarted in 2001, the purpose of the ENVIRHOM
programme is to assess the effects of chronic exposuresto very low levels by associating experts specialising in
the protection of human beings and the environment.
The attempt is to study radionuclide accumulation
phenomena in ecosystems and people in a multipollution
environment. The knowledge bases obtained will
significantly contribute to the implementation of asystem intended to protect the environment.
Another purpose of the ENVIRHOM programme is toassess the radionuclide transport from radioactivity tankcompartments that are water, soil and sediments,
towards the living environment. Furthermore, within
ecosystems, the wide diversity of those transports is
associated to the complexity of the chemical andbiological recycling mechanisms of the radionuclides
and to the food patterns of the organisms present inthose environments. The programme in particular studies
the biological changes produced in the long term.
ENVIRHOM will be used to develop dose-effect relations
between concentrations of chemical species present in
the environment and the ecological consequences
affecting individuals and the population (chemical andradiological toxicities).

14[ IRSN ACTIVITY REPORT 2002 ]The first experiences focussed on uranium andhighlighted and quantified uranium bioaccumulation
processes as well as the mechanisms implemented
according to the environment and uranium chemical
forms, for phytoplankton and invertebrates.
Other studies highlighted bioaccumulation processes andcapacities of transfer to consumers. Lastly, somebiological effects (death rate, impact on growth…) could
be associated with the exposure modalities and therefore
were used to draw dose-effect relation curves.

The SYMBIOSE programme: towards
an integrated assessment-support platform
Started in 2002, the purpose of the SYMBIOSE
programme is to develop a set of coordinated computer
tools intended to support the assessment andmanagement of the risk of radioactive contamination in
the environment. The objective is to process the impact
on both human beings and the environment from thescale of an individual to the scale of a whole population.
Depending on the situations studied, the programme canuse more or less complex and detailed models. Thus, inpreliminary forecast studies, some phenomena can betreated using simplified descriptions whereas theinterpretation of delicate real cases may require moresophisticated models. The aim of the approach used is toprocess a wide range of situations. It should allow the
dynamic modelling of radionuclide transport within andbetween the different environments forming thecontinental biosphere on time scales ranging from one
day to several dozens of years. This approach will beapplied to the waste storage, basic nuclear installations(BNI) in normal or accidental operations.
The work in 2002 focussed on restructuring existingmodels and integrating them into a modular set used
to assess the dosimetric impact on human beings, linked
to an ingestion of contaminated food from a simplified
continental biosphere.

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Page 15[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]The uranium bioaccumulationis studied in bivalves and crayfish.

A STRONG INVOLVEMENTIN INTERNATIONAL PARTNERSHIPNETWORKS

A parallel with ecotoxicology
ENVIRHOM and SYMBIOSE programmes are two complementary programmes used to assess the ecological risk
linked to radioactive substances. Since ecotoxicology has
for a long time formalized methods assessing theecological risk associated with the presence of chemical
poisons, a parallel with this area was initiated andparticularly, results in collaboration with INERIS. In fact,
in many cases of risk assessment, chemical contaminants
and radioactive contaminants cannot be consideredseparately.

In addition to these research actions, IRSN participates inthe European FASSET programme. Its main objective is to
propose systems to assess the impact of radioactive
contamination on the environment due to accidental or
chronic releases linking the release scenarios, the routesof exposure, the doses to biota’s (live organisms) and theeffects which may result from these As a single European
programme dealing with environment protection issues
in a practical way, FASSET mobilizes 15 teams from 7
European Union countries. This work will be pursued
within the framework of the European ERICA project inwhich IRSN takes part. In the end, the ERICA project shalllead to a method assessing the risk associated to thepresence of radionuclides in the environment.
Lastly, IRSN has been actively engaged in the work ofdifferent study groups on the protection of the environment, implemented by international organisations (ICRP,
AEN, UNSCEAR, IAEA…).

BREAKDOWN OF THE ASSESSMENT AND RISK MANAGEMENT CYCLE

The sources of uncertainty aretaken into account for each step.

Characterisationof the releases.

Identification of actions to achieve
an acceptable detriment level.

4
Actions

Uncertainty

1
Source3
Risk

2
Exposure

Analysis of target population exposures to substances.

Quantification of the impact
on health or ecological risk.

The Symbiose programme aims
at assessing and managing therisk of radioactive contaminationin the environment.

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Page 16ACTIVITIES> IRSN research programmes
in marine radio-ecology

I

RSN expertise regarding the assessment of the
impact of radioelements present in the environment, on human beings and ecosystems, implies inparticular the understanding and quantification of
the transfer mechanisms of the natural and artificial
radioactive substances in the marine environment.
For more than twenty years, the Institute has been
conducting marine radioecology studies, bringing
together specialists in chemistry, biology, geochemistry, sedimentology… Relations were establishedwith French and foreign research and expertiseorganisations (participation in working groups,
signature of collaboration agreements.

62 days of campaign at sea in 2002
The data obtained during sampling campaigns in sea andin the estuaries are used to design and validate transfer
models. The purpose of those models is to assessthe dispersion in the marine environment — seawater,
sediment, biota — of the radioactive substances ofnatural or artificial origin.
These campaigns use IFREMER and CNRS/INSU (Institut
National des Sciences de l’Univers) resources. IRSN’saccess to oceanographic ships and their equipment
depends on the assessment conducted by an appropriatescientific committee for both institutes in research
projects involved. The requests submitted in 2001 by IRSN
led to the scheduling of six campaigns in 2002, for aduration of 62 days at sea.
These campaigns contributed to:– Understanding and quantifying transfer mechanisms
between the sea, the atmosphere, 14C and tritium soil
(TRANSAT1 campaign);– Developing a model of dispersion at sea for contaminants, in the near field of an emission source (DISPRO2
campaign) ;– Understanding and quantifying the fixation andremobilisation mechanisms of radioelements insediments (DIAPLU3 campaign) ;– Studying the distribution of natural and artificial
radioelements contributed by the Rhône River to theMediterranean (REMORA4 campaign).

1. TRANSAT : TRANSfert eau ATmosphère.
2. DISPRO : DISpersion en champ PROche.
3. DIAPLU : comportement du PLUtonium dans la DIAgenèsedes sédiments marins.
4. REMORA : REMObilisation des RAdionucléides
dans le pro-delta du Rhône.

16[ IRSN ACTIVITY REPORT 2002 ]Improve the knowledge concerning transfers
between the sea, the atmosphere and the soil
The work of the Nord-Cotentin Radioecology Group (GRNC)
showed how important it was to deepen knowledge in
the area of transfers between the sea, the atmosphereand the soil. This led IRSN to conduct research on theunderstanding and quantification of transfers between
those three compartments. The purpose of both TRANSAT
campaigns carried out in February and August 2002 wasto quantify the transports of 14C and tritium in gaseous
form between the water, the earth and the atmosphere,
in the ecosystems of the central Manche and the Seine
river estuary. Moreover, the results obtained on 14C during
these campaigns will contribute to the more general
study of the CO2 cycle within the framework of the work
on climate change. The equipment and specifictechniques developed during these campaigns are used
to measure very low levels of 14C and tritium in the air.
These campaigns were conducted in collaboration with
the Laboratory of Science of Climate and theEnvironment (LSCE, CEA/CNRS mixed unit) and the Groupof atomic studies (GEA) of the National Navy.

Towards the modelling of contaminantdispersion in the English Channel.
The purpose of both DISPRO campaigns carried out inNovember 2002 was to determine the short and mediumterm dispersion parameters of soluble releases in the sea
through tides using the tritium controlled releases of the
La Hague power plant in the North-West of the Cotentin
region. They will allow the dispersion variations to bebetter assessed, depending on hydrodynamic conditions(release time, tidal currents, meteorological forcing).
The results obtained on the tritium used as a tracer will
be used to validate a high-resolution two-dimensional
dispersion model (110 metres), developed in collaboration
with IFREMER. 4,000 seawater samples have beencollected, as well as data on sea currents and depths.
The first results show that tritium concentrations
measured in seawater correspond to those provided by
the model.

DIAPLU mission:
the Flucha coresampler takes
samplings foranalyzing sediment.

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Page 17[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]Study the resuspension conditionsof plutonium in sediments

Study of the Rhône River influence
on sediments in the Mediterranean

The DIAPLU campaign took place in the Irish Sea from 2
to 21 July 2002. It was part of a research project intended
to determine through which processes plutonium, fixed
in sediments marked by reprocessing plant releases, canbe mobilized towards water.

REMORA campaigns study the influence of the Rhône
River inputs on the transports of natural and artificial
radioelements as well as trace metals in the Mediterranean.
They are particularly used to assess the temporal development of concentrations and quantities accumulated in
sediments of the Rhône River submarine delta (prodelta). The freshwater/salt water mixing area is the heartof complex phenomena of aggregation, flocculation andprecipitation. Those fixation phenomena generate alow dispersion of radionuclides in seawater and theiraccumulation in the Rhône River pro-delta sediments.
Resuspension phenomena, especially during east windstorms and Rhône River floods contribute to the redistribution of elements temporarily trapped in sediments.
Besides, stopping the industrial reprocessing operationsof Marcoule (Gard) site since 1997 led the IRSN teams
to perform, between 2001 and 2002, sediment sampling
campaigns in the Golfe du Lion in order to analyse
accurately the environmental response to such a change.

In fact, sediments constitute a deferred and non-point
plutonium source that will be taken into account toassess the plutonium part linked to a release and theplutonium part coming from the remobilization of plutonium contained in sediments. Plutonium concentrations
found in Irish Sea sediments marked by releases from the
Sellafield reprocessing plant enable the plutonium
dissolved in interstitial waters of sediments to bemeasured. Sampling of sediment cores and extraction ofinterstitial waters were performed in conditions keeping
the physical and chemical characteristics of the studied
environments.
The analyses of the 230 samples were used to determine
their sedimentological and geochemical characteristics aswell as the characteristics of the interstitial waters (pHvalue, redox potential…). The association modes of plutonium with the solid and reactive phases of sediments
were determined and the concentration of plutonium
dissolved in interstitial waters was assessed.
This campaign was performed within the framework of
the REMOTRANS programme of the European commission, with the collaboration of the CEFAS (The Centre forEnvironment Fisheries and Aquaculture Science, UK)and the University College of Dublin (Department ofExperimental Physics, Ireland).

The REMORA 3 campaign, conducted from October 12th
to November 5th, 2002, completes the campaigns performed in 2001 in the area under direct influence of the
Rhône River inputs (European REMOTRANS programme).
Almost 2,400 sediment samples were collected during
the three REMORA campaigns.
The REMORA 3 campaign was carried out within theframework of the EUROSTRATAFORM (EUROpean margin
STRATA FORMation), ORME (Environment Regional
Mediterranean Observatory, CNRS) and PNEC (National
Coastal Environment Programme) programmes.

Extraction of interstitialwater of sediments
sampled in sea.

REMORA mission:
localization mapof samples.

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Page 18

ACTIVITIES> Radiation protectionof populations and professionals

I

RSN is the main French technical organisation
aiming at informing citizens, increasing professionals’
awareness and advising public authorities on ionisingradiation-related risks. Its experience in the area of
workers’ radiation protection allows it to provide technical advice on draft regulations and take part in thework of various national or international organisations.

An evolution of the regulation
The protection of individuals against ionising radiation isbased upon three principles: justification of the practices,
optimisation of the protection and limitation of doses.
The whole population is concerned but in different ways
depending on whether the individual is a worker, apatient or a public figure. Two recent European directives
concern radiation protection: “96/29” for workers andthe public and “97/43” for patients.

IRSN ensures the dosimetricmonitoring of workers exposed
to ionising radiation.

Workers’ radiation protection
In France, exposure to ionising radiation of 260,000
workers in the medical, nuclear and industrial sectors ismonitored. IRSN ensures the dosimetry of 60% of these.
To do so, the Institute has laboratories specialised in themonitoring of external exposure (supply and analysis of
dosimeters) and internal exposure (radiotoxicologicalanalyses and anthropogammametry). Furthermore, IRSN
provides expertise in work stations, in order to reduce
professional exposure. In 2002, IRSN ensured the
distribution and treatment of 1,900,000 dosimeters.

SISERITo record, check and report the doses received by workers exposed to ionising radiation are the main objectives of the SISERI database. Developed by theInstitute since 2000, it is intended for use by various
radiation protection actors (occupational health physicians, “certified” persons in companies…). Ultimately,
current developments will allow remote access todata, via a secure Internet network.

Dentists 25,000
Veterinarians
4,000Classical industry
24,000Research personnel
7,500

Medecine 110,000

Miscellaneous
5,000

Distribution of the 260,000 workers subject to a monitoring of their exposure
to ionising radiation.
Nuclear industry 84,000

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Page 19[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]Patients’ radiation protection
IRSN takes part in the development of future regulation
related to the protection of patients, based upon the
reduction of exposures at an optimal level, while ensuring
the quality of the diagnostic images and the achievementof the therapeutic objectives. Its expertise focuses on thejustification of actions, protection optimisation, equipment quality control, medical screening campaigns andtraining of professionals. Within this framework, theInstitute took part in the preparation of a report on
the procedures and reference doses of radiological examinations. This system of reference aims at reducing thedosimetric differences noted for the same examination.
Furthermore, in radiotherapy, IRSN conducts research on
biological indicators which will enable the assessment of
the radiosensitivity of each patient in order to adjust
therapeutic protocols. Studies on mechanisms of induction of side effects have also been conducted in order tosuggest appropriate treatments.

Exposure to cosmic radiation
To implement the 96/29 directive, the SIEVERT system
was developed by IRSN, and its partners, the General
Directorate of Civil Aviation (DGAC), the Meudon (Hautsde-Seine) Observatory and airline companies, to provide
necessary information about cosmic radiation exposurein planes and assess radiation doses received during aflight. SIEVERT has been opened to French airlines
since August 2001 for the regulatory dosimetry of theirstaff. To date, more than twenty airlines have used thissystem and the doses have been calculated for almost
1 million flights. This service was also opened to the
public in March 2002 and it is available on Internet(www.sievert-system.org).

Control of radon in homes
Radon is a natural radioactive gas which is classified
among the carcinogenic substances for lungs. For morethan 25 years, it has been studied by IRSN which hasprovided elements to public authorities in order todevelop a prevention policy of the related risk. Thus, theInstitute produced a map of radon concentrations,published in 2000, after performing more than 12,000
radon measurements in French homes, in collaboration
with departments of the Ministry of Health. To enrich thismap, complementary measurements were performed in
2002 in eight departments and the analysis of thoseresults is currently in progress. Furthermore, a crossanalysis of the measurements with INSEE data (population density, types of homes, seasonal behaviour…)
was carried out in 2002 and it will be used to assess theradon exposure of the French population in terms ofconcentration measurements.

IRSN brings its
expertise to patients’radiation protection.

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Page 20ACTIVITIESThe modelling work intended
to distinguish radon from a miningsite from radon of natural origin.

Measurements of radon and free fractionof its daughters

By reducing the threshold of public exposure to radiation
generated by industrial practices, French regulation basedon the 96/29 European directive posed the problem of the
distinction between radon of natural origin and radon
originating from residue storage of uranium mines.
IRSN performed several measurements of radon and its
daughters, mainly bismuth 214 (214Bi), as part of a
research programme conducted in the Bessines-surGartempe (Haute-Vienne) mining site and its surroundings.
The bismuth/radon ratio proves to be far lower in theimmediate site surroundings than in the outlying
environment. This phenomenon is mainly linked toatmospheric dispersion, for which we have working
models which schematically predict that the bismuth
measured in the surrounding site is representative of theradon of natural origin only. From the measurement of
total radon, the part of radon of anthropogenic origin
emitted by the mining site may therefore be deduced.
In 2002, the method was improved, the physicalhypotheses and simplifications of the models used were
subjected to a critical analysis. The uncertainties related
to these hypotheses were assessed. Nowadays, IRSN uses
a method applicable to similar sites whose characteristics
correspond to the validity area of the method.

Radon 1.3 mSv

Pure metrology work on radon gas is intended to provide
reference values and ensure proper traceability of the gas
during the calibration of equipment. Within this framework, IRSN participated in an international intercomparison,concerning the calibration procedures, launched in 2002.
Measuring equipment, called Alphaguard, circulated in 9
European laboratories which performed its calibration.
This exercise showed good consistency in the results
obtained by the different laboratories.
The radon gas metrology is specifically completed withthe measurement of the free fraction of its daughters,
small aerosols (about one nanometre) contributing to thehealth risk. In 2001, the Institute launched a partnershipwith the University of Catalonia (Spain) and the
University of Brest (Finistère) for the development oforiginal measuring equipment, intended for thecharacterisation (measurement of particle size) of radon
daughters and particularly polonium 218. In 2002, thetwo organisms carried out an intercomparison of two
measuring systems of the free fraction of radon daughters. The resulting analysis is currently in progress and thefirst elements analysed show satisfactory consistency,with some points to be improved, in particular data processing algorithms.

Medical exposure 1 mSv

Water and food 0.2 mSv
Others (nuclear
tests, industries)
0.1 mSv
Cosmic radiation 0.4 mSv

Soil radiation 0.5 mSv

AVERAGE EXPOSURE OF THE FRENCH POPULATIONIRSN Source

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Page 21[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]> IRSN participation in ICRP workI

RSN experts participate actively in the work of theInternational Commission on Radiological Protection(ICRP) at a crucial moment in the action of this organisation, aiming to simplify and clarify the radiation protection
system in order to make it more comprehensible and more
efficient. The recommendations from this work willcomplete publication 60 dated 1990 which is used as areference for basic international standards of theInternational Atomic Energy Agency (IAEA) and for
the European directive of 1996 on radiation protection ofworkers and the public.

The mandate of the ICRP members has just been renewed
for the 2001-2005 period. IRSN is represented in themain Commission by Annie Sugier, Director for Protectionof IRSN, who has just been designated as President of thetechnical committee on the application of recommendations, succeeding to the South-African Bert Winkler.
The following IRSN experts also take part in the different
technical committees of the ICRP: Margot Tirmarche(Committee 1 — Radiation effects), Henri Métivier(Committee 2 — Derivate limits), Jean-François Lecomte(Committee 4 — Application of recommendations).

The ICRP, which was created in 1928 as a nongovernmental organisation, plays a crucial role in thedevelopment and transmission of the protection
principles against ionising radiation. The Commission
closely work with the International Commission on
Radiological Units and Measurements (ICRU) and keeps
relations with many other international organisations,
including the United Nations Scientific Committee on the
Effects of Atomic Radiation (UNSCEAR).

ICRP members during themeeting held in September
2001 at La Haye.

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Page 22ACTIVITIES> Expertise and researchin neutron dosimetryW

ith time, IRSN has developed a significant andrecognized activity of research and expertisesin the area of neutron dosimetry. Equipped withmetrology and test installations, some being uniquein the world, the Institute has a reference position
both at national and international levels.

Research and study activities
Measurements and characterisationof radiation fields in work places
The purpose of the measurements is to assess workers’
exposure to neutrons, in order to improve their radiation
protection, suggesting practices and instruments more
appropriate to their irradiation conditions. IRSN has
conducted many measurement campaigns in France(nuclear industry, army, transports of nuclear materials,
radiotherapy, air transports …), and in foreign countries(Spain, Germany, Belgium). Among recent operations,a measuring campaign of neutron dosimetry was
conducted in 2002 in an industrial production facility of
MOX fuels operated by COGEMA (ATPu work area).

Assessment of personal dosimeters
The behaviour of the personal dosimeters varies depending on the various characteristics of the neutron radiation field and environmental factors (temperature…).
Within this scope, IRSN is involved in two European
programmes. The first programme, called EVIDOS, focuseson the assessment of various available or in-study
methods for ensuring the personal dosimetry of workers,
in the real exposure conditions found in work stations ;from October 14th to 18th, 2002,
the EVIDOS programme participants were gathered around theYears of research
CEZANE and SIGMA facilities inorder to calibrate the equipment
were required
used for this programme. The
to develop the firstsecond programme, conducted
electronic dosimeterwithin the framework of EURADOS
for neutrons meeting(European Radiation Dosimetry
the international
Group), aims at harmonizing thestandards requirements. dosimetric practices in Europe;
IRSN is responsible for conducting
a state of the art study of the development and use of
personal electronic dosimeters.

10

Calibration of dosimeters with reference
radiation sources
The calibration of dosimeters is performed by the IRSN
laboratory certified by the COFRAC (French Committee
for Accreditation) and concerns photons and neutrons.
As a laboratory associated with the National metrology
bureau (BNM), IRSN plays the role of national reference
for neutron dosimetry. It is part of the cooperative
organisation between the national metrology institutes,
EUROMET, and is recognized at the international levelby the International Bureau of Weights and Measures(BIPM). As such, IRSN organizes comparisons with otherlaboratories at the national and international levels.

Research and development of new measuring
instruments and methods.
The purpose of research and development actions is toimprove the monitoring of workers’ exposure.
The research of new measuring methods is conductedwith scientific software used to simulate the experimental
conditions studied.
Models and laboratory prototypes are then made andtested on reference installations. Having neutron, but also
photon, references is crucial for IRSN to conduct researchand perform expertise as neutron fields are always
associated with photon fields in work places. In June
2002, a French industrial company marketed the firstelectronic dosimeter called “Saphydose-n” for measuring
neutron radiation. This has put into effect the success ofa study and a technology transfer conducted by IRSN,
following previous work carried out in its laboratories. This
dosimeter, whose first industrial prototype was validated
during the measuring campaign conducted by IRSN
in the EDF power plant of Dampierre-en-Burly (Loiret),
was certified in January 2002 by the CTHIR (TechnicalCentre for the Approval of Radiological Protection
Instrumentation).

First EVIDOS campaign
on CANEL: Saphydose-n.

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Page 23[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]A NEW INSTALLATION DEDICATED TO
MONOENERGETIC NEUTRONSIRSN has unique tools
in France for neutron
dosimetry such as the
CANEL moderator
device shown here.

Participation in national andinternational normative bodies
IRSN experts participates in national (Standardization
Bureau for Nuclear Equipment (BNEN)) and international
bodies, such as the International Organisation forStandardization (ISO) and the International ElectrotechnicalCommission (IEC) working groups. For ISO, the activity in2002 focused on the creation of a new standard
concerning the calibration in neutron radiation fields with“realistic” spectrums. The IEC committee on radiation
protection instrumentation, managed by IRSN, met in
Beijing (China). One of the working groups in which
IRSN participated actively examined personal and area
electronic dosimeters.

Unique installations in France
IRSN reference means for neutron dosimetry are locatedin Cadarache (Bouches-du-Rhône). Those means, uniquein France, exist in two facilities: CEZANE and SIGMA.
The CEZANE facility houses the Van-Gogh irradiator,
comprising three sources emitting neutrons of intermediate and high (fast neutrons) energy. The SIGMA
facility comprises a source emitting low energy neutrons(thermal neutrons).

In 2000, IRSN decided to acquire a new equipment toproduce monoenergetic neutrons of metrologicalquality: the AMANDE project, whose equipment will
be implemented near the CEZANE facility. This new
equipment will be used to study precisely the behaviourof radiation protection instruments depending on theneutron energy, positioning them in a neutron fieldwith well defined and precisely determined energy,
and making energy vary also in a perfectly controlledmanner. The implementation of the AMANDE project
implies the construction of an accelerator (being
manufactured by the Dutch company HVEE), therequest of authorisation for operating a facility
classified for the protection of the environment(registered in the Prefecture of the Bouches-duRhône in July 2002) and the construction of thebuilding which will house the accelerator and its test
hall (start of work scheduled in 2003). According tocurrent planning, the accelerator reception in plantshould occur in the course of 2003 and its implementation on site in 2004. Following a test period, operational production would start in 2005. In 2002, many
communication actions were carried out, especiallyfor the public inquiry required before obtaining theauthorisation for use.
With the AMANDE installation, IRSN will have acomplete set of metrological installations forneutrons and photons, which will cover all the needs
for calibration and qualification of the radiation
protection equipment used to ensure the dose monitoring of workers in the civil and military nuclear
industry and the medical field.

Moreover, the CEZANE facility houses two electrostatic
accelerators coupled to a moderator device called CANEL.
This equipment is used experimentally to produce
neutron radiation whose energy distribution is said to be“realistic”, i.e. representative of the conditions observed inwork stations. They are used to assess the performancesof dosimeters and detectors in various configurations.
Within the framework of a EUROMET (European
Metrology) collaboration between IRSN, the German(PTB) and English (NPL) primary laboratories and the
University of Barcelona (Spain) (UAB), the characteristicsof the radiation field produced by a new configuration of
the CANEL device were determined in 2002. This device,unique in the world, is also intended to become areference as an international standard project on the
production and use of “realistic” spectrums, currently
being assessed by ISO.
Installation of neutron
measuring equipment
on a Van-Goghcalibration system.

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Page 24

ACTIVITIES> Management of accidental exposuresDuring irradiation or contamination accidents orincidents, IRSN may have to contribute its
expertise to assess doses received by irradiatedpersons and to assist medical teams in charge of
their treatment. Concurrently, the Institute continues its research to improve diagnostic indicators— especially by developing new techniques for dose
assessment — and to optimise treatment of irradiatedpersons.

Complementary missions
In case of accidents, the assessment of the dose received
by an irradiated person is an important element to choose
the appropriate therapeutic strategy. This expertise work
is based on several complementary approaches, but it isessential to collect the maximum information about thecircumstances of the accident and the exposure conditions of the victims. Biological dosimetry is used to assess
the average dose received by an irradiated person fromthe scoring of unstable chromosome anomalies in thecirculating blood lymphocytes, by a cytogenetic techniquerefered as conventional. Physical dosimetry is used toassess the distribution of doses in the organism fromexperimental reconstructions or by modelling of theirradiation conditions. The dose received can also beassessed with measurements by paramagnetic electronicresonance on bone fragments. In case of contamination,
the incorporated activity, and therefore the dose, may beassessed, depending on the radionuclides, from theanthropogammametry or measurement performed onurine and stools.
In addition to work aiming at improving the previously
mentioned measuring and assessment techniques, themain purpose of research conducted by the Institute in
the management of the accidental exposures is to suggest
treatment appropriate to each situation encountered, by
taking into account the radiosensitivity of each individual
and the heterogeneous characteristic of the irradiation
accidents.

Dose reconstruction in case of accident:
modelling of the irradiated person and the source.

24[ IRSN ACTIVITY REPORT 2002 ]National incidents
Roissy (Val-d’Oise)A defective package containing radioactive materials wastransported through Charles-de-Gaulle Roissy airport.
IRSN conducted expertise studies using biologicaldosimetry for the nine persons who had handled the
package for unloading, storage and reloading in theaircraft. To obtain very accurate results, 2,000 cells
were analysed, instead of the usual 500. The number of
instable aberrations detected was abnormally high forthree of these persons, but the confidence interval of thedose received could be separated from the backgroundlevel for one of them only. Moreover, no effective relation
with the transportation of the damaged radioactive
package could be established.

Bordeaux-Gradignan (Gironde)
Upon the request of the Director for the Prevention of
Pollution and Hazards, IRSN conducted an expertise studyof the incident which occurred on January 25th, 2002,
on one of the experiment lines of the Van-de-Graaff
accelerator from the Centre of Nuclear Studies of
Bordeaux-Gradignan (University of Bordeaux 1). This incident implied an exposure to tritium of a dozen of personspresent in the related premises. The contamination levelof those individuals was assessed from tritium measurements in urines performed by OPRI. The incident analysis
allowed the possibility of drawing lessons to reinforce
the security of this type of equipment. The suggested
improvements concern the technical devices used toprevent accidental tritium degassing, the collect andcontrol of tritium releases and the protection of staff
and monitoring at the work place.

Ladoux (Puy-de-Dôme)
IRSN took part in the technical analysis of the irradiation
accident which occurred in the Michelin plant at Ladoux(Puy-de-Dôme) in June 2002, when three workers
entered a bunker dedicated to an industrial electron
accelerator for a maintenance operation. The equipment
operator accidentally activated the electron beam, which
generated the production of bremsstrahlung X-rays.
Moreover, IRSN conducted a biological dosimetry expertise
study which did not reveal any significant exposure of theworkers concerned.

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Page 25[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]Mobilization of IRSN agentsto treat a great numberof blood samples.

International incidents
Georgia

Collaboration with the Saint-Antoine hospitalon the research of therapeutics in haematology.

In December 2001, three Georgians handled strontium
electricity generators. Suffering from severe burns and acollapse of their bloodlines, they were hospitalised in
Tbilisi (Georgia) three weeks later. One of them had very
severe injuries in his back.

In 1999, IRSN created, with the Saint-Antoine university
hospital centre (Paris-VI University), a common laboratory
called Laboratoire de Thérapie Cellulaire et de Radioprotection Accidentelle (LTCRA). Its goal is to perform
experimental research in order to improve the treatmentof bone marrow failures, due either to accidental irradiation or not, using cell therapy. This therapy consists in
multiplying the cells of a patient taken from his own
organism and then re-injecting them when he or sheneeds them. This technique, applied to haematopoietic
stem cells sampled after an accidental irradiation in a
medullar area more or lessprotected from irradiation, has
shown very promising resultsin the treatment of radiationIRSN performed 20
induced aplasia. This techniqueexpertise studies using
is being applied for other cellbiological dosimetry
types, and especially forfor accident suspicions
mesenchymal stem cells which,after re-injection, are able toin 2002.
acquire the functionality of theorgan or tissue they colonize.
An aplasia patient was treated with this technique in
2002. This works was published in international reviews.

IRSN intervened upon the request of IAEA and recommended the transfer of the most injured patient to France.
He arrived in Paris in February 2002, 88 days after theaccident. He was taken in charge at the Army Hospital ofPercy (Hauts-de-Seine), where he underwent severaltransplants. The improvement of his health condition
permitted him to return to Georgia in April 2003.
IRSN provided its support to hospital teams, particularlyin performing dosimetric assessments. Two biologicaldosimetry methods were used. The assessment of theaverage dose by the conventional cytogenetic technique
was completed by the evaluation of the dose received atskin level, a technique applied for the first time in an
accident. This second dosimetry was performed by scoring
the stable translocations using the FISH (Fluorescence In
Situ Hybridization) method. The dose estimates are inagreement with the clinical data. Lastly, a dose calculation,using a modelling of the source and the patient, confirmed the consistency of the various analyses.

20

PolandUpon the IAEA’s request, IRSN intervened in 2002 in
Poland, in the management of the consequences of aradiotherapy accident having occurred in February 2001,
involving five patients. After a clinical expertise, the mostinjured patient was transferred to France and treatedin the Curie Institute. She was able to return in Poland
after undergoing several transplants. For three of the fivepatients, a dosimetry by electronic paramagnetic
resonance was performed on a rib fragment sampledduring the surgical resection in the irradiated area.
The results of those measurements were used to refine
the therapeutic strategy by confirming the possibility oftransplant.

International intercomparisonof dosimetry on the Silène
reactor: positioning of blood
samples.

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ACTIVITIES> Understanding the ionisingradiation effectsT

he work conducted on health effects of ionisingradiation is crucial to achieve the radiation
protection missions of the Institute. It will improve
the knowledge on issues where uncertainties remain.

Analytic epidemiological studies
The purpose of these studies, concerning workers andpopulations exposed to ionising radiation, is to better
quantify the risk of developing cancer depending on thedose received. Two methods are used: prospective surveys
are used to follow over time the evolution of the disease
rate within a group of exposed persons, while the casecontrol studies are used to establish a comparison
between the exposure of individuals suffering from apathology and the exposure of a “control group” notsuffering from this pathology. IRSN is currently pursuingstudies with these methods:– Monitoring of the cohort of workers from the CEA-COGEMA
group within the framework of an international study
conducted by the IARC (International Agency for
Research on Cancer);– Monitoring of the cohort of 5,098 French uranium
miners exposed to radon, completed by a case-control
study within this cohort to study the joint effect ofradon and tobacco;– Case control study on lung cancer within populations
exposed to domestic radon including 1,655 individuals(552 cases and 1,103 controls) in 4 French regions;– Study of the health consequences of the Chernobyl
accident, in particular within the framework of theFrench-German initiative, and case-control study of
the risk of leukaemia within populations living incontaminated territories on the banks of the Techa
River (Urals).

17,500Concurrently, IRSN takes
part in the RIMED project
Number of analyses(Ionising radiation in medical
performed within theenvironment): epidemiological monitoring of theframework of the ENVIRHOM
death rate among health careresearch programme intended
professionals exposed toto assess the risks ofionising radiation in France.
radionuclide bioaccumulation. Started in 2002, the feasibility
study, coordinated by InVs,
will concern 6 hospital institutions. IRSN brings to this project
its experience in the epidemiological monitoring of an active
population and the management of professional anddosimetric databases.

26[ IRSN ACTIVITY REPORT 2002 ]Lastly, with the intent to develop epidemiological studies
on patients exposed to ionising radiation for medical
purposes, IRSN started a pilot study in 2002 on 100
premature infants subject to repeated examinations
during the neonatal period. The purpose of this work,
conducted with the Trousseau Hospital, is to determine
how accurate the doses received by those infants may beevaluated, and to assess the relevancy and feasibilityof epidemiological monitoring of the related population.

Effects of chronic radionuclide ingestion
In order to improve the assessment of the risks linked tothe chronic low level incorporation of radionuclides, IRSN
launched the ENVIRHOM programme in 2000, focusing
on both biological components of the environment andhuman beings. The “human” part of this programme isconducted along four lines:– Researching the phenomena of chronic accumulationof the radionuclides;– Understanding of the biological mechanisms leading to
the phenomena observed;– Analysis of the biological effects on the immune system,
the digestive system, the central nervous system andthe reproduction system;– Implementation of new biokinetic and dosimetricsoftware and models in order to assess the uncertainties on the doses received and better take into accountthe cellular distribution of the radionuclides.
In 2002, work was focused on the first two areas and apart of the third area, the study of the biological effects
on the digestive and central nervous systems, with uranium
as radionuclide using the rat as the animal model. The
study of the consequences resulting from uranium chronic
accumulation on the fertility and embryonic development of rodents, as well as on the organism’s capacity torespond efficiently to situations frequently encounteredin public health (bacterial infections, alimentary antigens,etc.) will be performed in 2003.

Heterogeneous distribution of uranium
in a kidney proximal tubular cell.

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Page 27[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]Effects of acute irradiations
The work performed in this area concerns both the severe
effects caused by an accidental exposure, and thelong-term deleterious effects resulting from therapeutic
exposures. Historically, the studies performed by IRSN
focused on the development and operational applicationof biological dosimetry using classical cytogenetics (doseassessment from the scoring of chromosome aberrations)on the one hand, and on the other hand, the study of theradiation induced dysfunctions of the physiologicalsystems involved in the vital prognosis of the irradiatedperson: haematopoietic system, digestive system andcentral nervous system. These studies took into accountsignificant scientific advances which occurred in biology
in recent years. Today, considering these studies and thelessons drawn from the severe irradiation accidents
having occurred around the world, IRSN research activities gradually evolved towards the following topics:– Operational application of new biological dosimetry
methods to assess the dose received whatever theirradiation typology. Within this framework, dosimetricassessments were performed on skin pieces sampledduring surgery on a Georgian patient and on a Polishpatient severely irradiated, treated in the Burn
Treatment Centre (Percy Hospital) and in the Curie
Institute. The results have proven to be particularly
promising for characterizing the extent of injuries incase of localised irradiation;– Physiopathology of the effects caused by an accidental
irradiation or by the irradiation of healthy tissues
during medical examinations or treatments. The purpose
is to identify biological indicators of diagnosis andprognosis of the radiation induced pathologies and to

LIMITING THE SIDE EFFECTS
OF A RADIOTHERAPY

Radiation therapy treatments generally deliver highdoses necessary for the tumour monitoring, but also
irradiate healthy tissue contiguous to the cancerous
tissue. They may cause very disabling side effects forpatients. On this topic, still poorly appraised, IRSN
pursues research, especially in the laboratory operated
in collaboration with the Gustave-Roussy Institute, inorder to better understand the mechanisms implied in
the initiation, development and persistency of thoseside effects. The objective is to suggest preventive or
curative therapeutic strategies. The work initiated in
2002 focuses on chronic radiation enteritis.

determine possible therapeutic actions. The tissues
studied are mainly the vascular endothelium, theintestinal barrier and the skin, given their possible rolein the multi-organ failures observed;– Development of strategies for treating radiationinduced pathologies filling the cellular deficits using
cellular therapy. This work enables IRSN to bringexpertise to the medical teams treating accidentally
irradiated persons or treating patients using radiation
therapy.
All this research on health effects of ionising radiation
conducted by IRSN do not cover all the inquiries related
to this subject, in particular those related to carcinogenesis. However, they provide IRSN with a privileged position
to develop cooperative research at national and international levels.

Biological dosimetry:mapping of the dose received atskin level for one of the patients
irradiated during the accident
in Georgia.
Scoring of chromosome
aberrations with microscope.

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IRSN
Contributing to the safetyof nuclear facilities
and transports
elping to prevent accidents in nuclear facilities
or during transport and limiting the consequences of accidents which might nevertheless occur
is a major concern for IRSN.

H
Paluel unit for nuclear electricity production.

750
Technical notices transmitted
by IRSN to safety authorities
in 2002.

13
In 2002, IRSN submitted
13 assessment reports to
the French Advisory group ofExperts for nuclear reactors.

133
In 2002, IRSN transmitted
133 technical notices related
to the safety of the transportof nuclear materials.

28[ IRSN ACTIVITY REPORT 2002 ]Assessing the safety of nuclear facilities andtransports requires at all times technical knowledge,
given the evolution of facilities and the safety
approach: aging of equipment, evolution of fuels,
severe accidents, waste management, prevention ofcriticality risks, fire protection… For these technicallycomplex issues, the Institute develops and uses its
competencies in the areas of studies, expertise andresearch. Researchers and experts have the same
global objective: assessing the risks to better control
them and prevent their consequences.
The whole approach implies safety assessments andstudies used to identify issues insufficiently known aswell as research intended to increase the knowledge.
Within this framework, the Institute has for many
years developed probabilistic safety analyses (PSA)
applied to the PWRs, which are used to assess theprobability of an important event for safety and its
consequences.
The research studies have in particular resulted in aninteraction between the development of analytic
models, the development of software and the carryingout of experiments in realistic conditions.
The competencies acquired by the IRSN in the areas ofexpertise and research are also used for non nuclear
facilities. The Institute makes available to the industry
improvements of its competencies.

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Page 29[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]ACTIVITIES> Phenix safety reviewP

ut into service in 1974, the Phénix reactor isa fast neutron reactor, with sodium coolingsystems. Owing to the age of the facility and CEA(Atomic Energy Commission) wishes to continue to
use it for several years, since 1997 the licensee has
begun a renovation programme including significant
improvements in the resistance to earthquakes andsodium fires.

Significant work
The core internal structures, sodium circuits, emergency
equipment were controlled, and, in some cases, repairedon the basis of a general assessment of the equipment
aging. The requirements regarding the resistance of
nuclear facilities to earthquakes, were also redefined andthe buildings were thus reinforced, involving a significant
building project.

Risk analysis
In view of a possible restart of the reactor in 2002, IRSN
studied CEA proposals regarding methods intended tocontrol and analyze failures as well as repairs of thesteam generator modules affected by a cracking phenomenon specific to the stainless steel used for their construction. Concerning the safety of steam generators, thelicensee’s justifications were studied according to an
approach which identified the existing in-depth lines foreach important safety event.
Other issues were studied, in particular those concerning
the risks in case of sodium fire and the in-service
monitoring of the upper part of the reactor vessel. The
structure supporting the control rods (plug-cover-core)
was particularly studied, as well as the consequences ofan accident of instantaneous plugging of a fuel assembly
which is a possible initiating event of partial core
meltdown.
IRSN submitted the results of its analyses to the French
Advisory group of Experts for nuclear reactors in October
2002. This meeting was the last of a series of eight
meetings held since 1996 within the framework of thesafety review of the nuclear facility.
Among other issues studied in 2002, the Institutehighlighted the need for the licensee to have more
efficient procedures and tools for the management ofcrisis situations.
Another important issue in 2002 was the study of the fire
action plans for each building. In fact, these plans werecompletely revised by the licensee,taking into account the renovation
work performed. Several failurecommon modes of materials
In 2002, IRSN
important for safety were thustransmitted 7 technicalidentified and processed by thenotices concerning
licensee. These actions have been
the safety of the Phénix
continued in expectation of apower increase of the reactor.
fast neutron reactor
and wrote a report for
It is important to recall that theresidual operating time of thethe French Advisory
Phénix reactor is a maximum of six
group of Experts
operating cycles during which thefor nuclear reactors.
CEA (Atomic Energy Commission)planned to perform various irradiation experiences, within the framework of partitioningtransmutation work, under the law of December 30th,
1991 regarding the management of high activity andlong-life radioactive waste.

7Saint-Alban unit
for nuclear electricity
production.

Phénix in Marcoule.

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ACTIVITIES> Studying the safety of PWR fuels
I

RSN provides technical notices on new developments in fuel management requested by Electricitéde France in order to reduce production costs.
The Institute has to carry out studies and research
programmes to assess the impact of fuel evolution
on safety.

Technical stress related to economic issues
Economic considerations lead most of the electricians in
the world to strive for an increase of the burn up
fractions of the nuclear fuel they use in their facilities.
In this framework, EDF was allowed in 1998 to use theuranium oxide (U02) based fuel to a burn-up a fractionof 52,000 MWj/t on average per assembly (instead of
47,000 MWj/t previously). For the future, it forecasts
maximum burn up fractions that could reach, or evenexceed, 60,000 MWj/t.
Some electrical utilities companies, such as EDF, have forover 10 years, also used MOX type fuel (mixture of uraniumoxide U02 and plutonium oxide Pu02). The average burnup fraction of MOX fuel is today, in practice, limited to
45,000 MWj/t according to its use instructions.
The increase of the MOX burn up
fraction is also an industrial objective for EDF.

Increasing needs in terms of analysis
Another consequence of the increase of the fuel use rateis to stagger the maintenance shutdowns of the reactors,
adjusted on the fuel use cycles. This requires studying theconsequences of the new practices from the safety
viewpoint. IRSN in 2002 undertook to analyse a feasibility
case concerning the “parity” use of U02 and MOX fuels,
implying a rise of the burn-up rate of MOX fuel up to
52,000 MWj/t.
The analysis focuses on the fuel evolutions likely to havean effect on its behaviour in operation: evolution of theassembly design, use of new structural or cladding
materials. In 2002, in the framework of its expertise, IRSN
specifically studied a proposal related to the reinforced
structure assembly, intended to compensate a failure dueto the cladding perforation by “fretting”, detected during
the cycle No 8 of the Cattenom 3 unit. The cladding
corrosion phenomena are also monitored and analysedby EDF .
Assessing the safety of these technological evolutions,in particular the available safety margins, implies
developing increasingly sophisticated assessment
methods, in particular including three-dimensional
thermo-hydraulic or neutron software.

13

These evolutions led the Instituteto organize, at the beginning of the
1990s, a revision of the available
knowledge on fuel behaviour
around the world. This highlighted
the lack of knowledge concerning
the behaviour of fuels with highburn up fractions (exceeding theauthorised value set to 47,000
MWj/t) and the need to study thevalidity of the safety criteria in case of postulated
accidents, such as the loss of coolant accidents andreactivity accidents in control rod ejection.

IRSN performed
13 expertise studies
related to thedevelopment of
new fuel on
behalf of safety
authorities.

Test device in the water loop.

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Page 31[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]Research programmes
Research programmes conducted by IRSN study fuelbehaviour during postulated accidents: the accident ofaccidental reactivity injection, with the programmes
conducted on the CABRI reactor, and the loss of coolant
accident, with a study programme on the irradiatedcladding behaviour.

CABRI programmes
The first CABRI programme concerning PWR fuel was
initiated in 1993 in the sodium-cooled CABRI reactor loop,
in collaboration with EDF and with the support of the
NRC (safety authority of the United States). The purpose
was to study the behaviour of uranium oxide (U02) based
and fuels and MOX fuels in a situation of reactivity accident for high burn up fractions. 12 tests, called “REP-Na”,
were performed in the CABRI reactor, including eight on
the UO2 fuel and four on the MOX fuel. The “in-pile” tests
were completed by tests referred to as “separate effecttests” related in particular to the mechanical properties of
the irradiated clads and by the development of software
known as SCANAIR, used both for the interpretation oftest results and their transposition to reactor conditions.
The lessons drawn from this programme were used within
the framework of the expertise of the files concerning theuse of U02 fuel to a 52,000 MWj/t burn up fraction.
In order to determine the behaviour of even higher burnup fraction-fuels, IRSN in 2000 launched a new international programme called CABRI-Water Loop, mainly
conducted within the framework of the AEN of the OECD.
The tests in the CABRI reactor will be performed in a“water loop” under pressure, more representative of thethermohydraulic conditions characterizing the PWRs
that the sodium loop which has equipped this reactor
until now.

Two tests of the new CABRI international
programme in 2002
In November 2002, the first two tests of the CABRI-Water
loop programme were carried out. These are reference
tests, conducted in the existing loop cooled by liquidsodium, before being replaced by the water loop andthe reactor levelling. The first test showed no sign of clad
failure: the analysis of the experimental results is inprogress. During the second test, a late event was recorded, which could be interpreted as a deferred failure of
the test rod; the analysis of signals and their examination,
which will be performed in the laboratory, will be used toconfirm or invalidate this failure and, as appropriate,
determine its characteristics.

Exemplary international co-operation
The technical and financial partnership of the CABRIWater loop programme implies significant participationon the part of EDF and contributions from foreign
partners, who have taken part in the programme under
the auspices of the OECD (Organisation for Economic
Co-operation and Development). To date, 10 countries(safety and industrial organisations) have signed aparticipation agreement with IRSN.

CABRI RESEARCH REACTOR

The CABRI research reactor is a unique installation in
the world, used to simulate the conditions of areactivity accident in a PWR. Operational since 1978, it
was initially intended to safety studies of fast neutron
reactors (with a loop cooled by liquid sodium). Four
programmes were conducted on it, including the last
one called CABRI-RAFT, carried out in partnership with
the Japanese JNC organisation, ended in 2001. Its use
for the CABRI-Water loop programme requires, on
the one hand, an upgrading regarding safety given
the evolution of the practices, especially regarding fire
protection risks and seismic risks and, on the other
hand, the replacement of the sodium loop by awater loop.

View of the CABRI pooland core (CEA facility).

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ACTIVITIES> Safety review of nuclear power plantsT

he purpose of the safety review is to check, every
ten years, the safety level of nuclear facilities,
taking into account evolutions in safety practices(resistance to earthquakes…). 2002 was a pivotal
year, with the end of the safety review linked to thesecond decennial outage programmes and the
beginning of the safety review for the third decennial outage programmes of 900 MWe power plants.
As for the 1,300 MWe power plants, the safety
review began in 1997 for the second decennial
outage programmes scheduled from 2005 on.
In practice, the safety review process for 900 MWeand 1,300 MWe power plants is based on two mainparts: the check of the reactor’s conformity
regarding its initial safety baseline and the review ofsafety requirements. The studies initiated from the
new safety requirements may lead to the implementation of modifications intended to improve safety
during the next ten-yearly outages.

Safety review of the 900 MWe nuclear power
plants for the second ten-yearly outages
The 900 MWe power plants using pressurized water
reactors (PWR) are the oldest of the French nuclear power
plants. They were put in service between 1977 and 1987.
The safety review approach of these power plants has
been initiated from 1987 for the oldest of these. Thisapproach for all 900 MWe power plants will be completed
as second ten-yearly outages ofthese plants go along, i.e. after
20 years of production.

130

IRSN monitors
130 basic nuclear
installations(pressurized water
reactors, fuel cycle
plants…) in France.

IRSN established an overall assessment of the approach
conducted by the licensee and submitted its conclusions
to the French Standing group of Experts on February 28th
and March 14th, 2002. At this level, it did not discusselements which could raise the question concerning thecontinuation of the 900 MWe plant operations until thethird ten-yearly outages which will occur 2008 to 2015.
However, EDF still has a significant amount of work tocarry out to finalise this study. In fact, the complianceprojects initiated and the modifications planned willcompletely help to improve the safety level of thesepower plants only at the date of their second ten-yearly
outages.

Third ten-yearly outage programmes
The safety review associated with the second ten-yearly
outage programmes has been particularly long. Thus,
IRSN highlighted the need to rapidly identify the content
of the phases of the safety review linked to the third
ten-yearly outages: content definition of the safety
review and associated baseline, actual studies, controls
and implementation of the modifications. Furthermore,this process will be properly developed to meet the study
deadlines of the modifications in order to implement
them during ten-yearly outages. As the third ten-yearly
outages of 900 MWe power plants are scheduled fromthe end of 2008, the definition of this safety review waslaunched asof 2002. This step is the first of a process
which will set, by 2007, the requirements in which the
900 MWe power plants will be authorised to be still be
operated after 30 years in service.

The French Standing group ofExperts for nuclear reactors wasregularly consulted throughout
the various steps of the process
which took place over more than
10 years.

In order to close this approach on
all the 900 MWe power plants,
the DGSNR (Nuclear safety Authority) requested thetechnical notices of the French Standing group of Experts
related to the consideration of the safety requirements
resulting from the safety review of the power plants after
their second ten-yearly outage.

Reactor building (EDF installation).

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Page 33[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]Safety review of 1,300 MWe nuclear power
plantsOn March 28th, April 4th and December 19th, 2002, IRSN
submitted to the French Standing group of Experts fornuclear reactors its assessment of the safety requirement
baseline and the EDF approaches concerning thecompliance and reassessment studies for the 1,300 MWe
power plants.
It emerged that there is a need for EDF to specify somepoints, such as the functional capacity of certain
materials used in accidental situations out of postulated
and takes into account new requirements resulting fromthe classification of the materials and systems required
for safety.
Furthermore, the resistance to earthquakes of the buildings
and equipment will be reassessed, taking into account theevolution of technical rules related to seismic risk, andthe risks of explosion inside buildings shall be subjected
to a safety review for all the power plants.
The next step will consist in assessing the detailed
programme of the modifications and the results from thecompliance examination of the reactors implemented by
the licensee.

Storage pool of the PHEBUS test reactor (CEA facility).

REMOVAL OF THE RESIDUAL POWER
FROM THE USED FUEL ASSEMBLIESSTORED IN THE SPENT FUEL POOLSOF THE PWR (PRESSURIZED WATER
REACTOR)To reduce the shutdown periods of the reactors in order
to increase their availability, EDF reduced the time
between reactor shutdown and the end of fuelunloading. This leads to an increase in the residual
power which shall be removed from the spent fuel pool
during refuelling shutdown.
Therefore, the facilities participating in the safety of theirradiated assembly storage have been operated today
beyond the conditions defined in the safety reports.
This situation has been highlighted by the feedback ofexperience and the safety review performed for the
900 MWe power plants. It is processed through theimplementation of transitory operation stresses towhich final improvements are added. Within thisframework, IRSN analysed EDF proposals in order toimprove the safety of spent fuel storage and remove
the current stresses involved in the operation of spent
fuel pools of 900 MWe power plants.
The Institute analysed the material and documentary
modifications proposed by EDF in order to strengthen
the prevention, detection and management of accidental situations which could have an impact on the safetyof irradiated fuel storage. It particularly studied if the
proposed measures would make it possible to manage
a complete and prolonged loss of coolant of a spent
fuel pool and analysed the probability assessment
transmitted by EDF related to the risk of fuel dewatering in such a situation. IRSN conclusions were
submitted to the French Standing group of Experts fornuclear reactors in November 2002. It has been shownthat the control of the cooling of spent fuel stored in
the spent fuel pools of the power plants will be significantly improved when the modifications planned by
EDF will have been applied. These modifications shall be
adapted to be implemented on the most recent power
plants (1,300 and 1,450 MWe).

Nuclear power station producing electricity
in Saint-Laurent-des-Eaux.

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ACTIVITIES> Research on the PWR core
meltdown accidentsAlthough extremely unlikely, core meltdown
accidents situations which have not yet beentaken into account during initial design of theexisting power plants deserve specific precautions.
Significant research has been conducted by theInstitute on the phenomena concerned, in order tocontribute to the prevention and the mitigation of
the consequences of such accidents. Today, IRSN is amajor actor in research around the world on theaccident situations of PWR core meltdown.
The core meltdown accidents would result from a seriesof failures and could generate significant releases ofradioactive products in the environment.

Studies and research
The studies and research conducted at the Institute on
severe accidents aim at:– Identifying the possible accident scenarios and assessing their probabilities;– Studying the progress and possible consequences ofsuch accidents, including the risks of containment failure
and the possible radioactive releases.
To achieve this, IRSN develops a research strategy which
combines analytical experiments, the physical modellingof the phenomena, the development and qualification ofsoftware to be applied to reactors and the performanceof global experiments, notably in test reactors. Research
particularly studies core degradation, iodine chemistry,
aerosol behaviour and containment resistance. They are
subject to international collaboration, in particular with
the European Union, the United States, Japan, Switzerland and Russia…

A role to support public authorities
The task of the Institute is to bring technical elements
enabling the public authorities:– To assess the measures suggested by the licensees
to prevent core meltdown accidents and limit theirconsequences;– To assess retained or possible means to limit the consequences of such accidents;– To prepare emergency plans and assess in real time, incase of accident, the risks encountered in order to be ina position to take countermeasures to be implemented
for ensuring the protection of populations;– To improve crisis management with a better assessmentof the effects, measures and interventions provided forand periods of dreaded events;– To assess the acceptability of the design of possible
future reactors.
PROBABILISTIC SAFETY ANALYSES (PSA)

Published in 1990, the probabilistic safety analysis,
called “level 1”, assessed the probability of a core meltdown in a 900 MWe pressurized water reactor. It was
prolonged with a “level 2” PSA whose objective is toassess the probabilities and levels of the releases in theenvironment resulting from accidental series of core
meltdown. A first version of PSA 2 published in 2000
was based on a certain number of simplifying hypotheses, especially on the main question of the mechanicalbehaviour of containment. A modelling work for thiscontainment, including the behaviour of the concrete,
the liner and the singular areas, was used to remove in2002 the simplifying hypotheses introduced. The resultof this work will be integrated in the revised version ofthis study, whose development is in progress. Thesestudies use all the experimental knowledge and thecalculation tools available at the Institute. They are also
used to highlight points where research still seems
necessary.

FP caisson whose loop (in red) simulates a steam generator.
International relations
involve the SARNET network.

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Page 35[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]Phébus FP is the most significant
research programme in the world
regarding nuclear safety.
Operational since 1978 in the Cadarache (Bouches-duRhône) research centre, Phébus is an experimental
reactor of the CEA, which was modified in 1989 to carryout the Phébus FP programme. The Phébus FP experimental facility is a 1/5000 simulator of the main components
of a pressurized water reactor. It is used to perform global
experiments reproducing all the phenomena occurring
during a core meltdown accident and contributing to therelease of radioactive products. The Phébus FP programme
is an international programme conducted by IRSN andmobilising 35 organisations from the European Union,
the United States, Canada, Japan, South Korea andSwitzerland. In 2002, the participation in this programmeof several organisations from candidate countries to join
the European Union, was negotiated: Czech Republic,
Slovakia, Hungary, Slovenia, Bulgaria and Romania.
The Phébus FP programme includes five tests spread overabout 15 years. The first was performed in 1993 and threeother tests were also performed, respectively, in 1996,
1999 and 2000.
After the analysis of the fourth test data, a preliminary
synthesis of the Phébus FP programme, as a whole, wasdeveloped in 2002.
Three main points have emerged:– Computer codes had to be modified. This concerns thechemical forms of fission products in the primarycooling system, the presence of gaseous iodine among
the fission products released into the containment
through the break in the primary cooling system, theproduction of organic iodine in the containment. Thesephenomena must be subjected to additional experimental work;– Some unexplored phenomena appear significant: thisconcerns the degradation and re-localization of thefuel, the effect of fuel degradation on the releases offission products, the transport of representative fission
products in the primary cooling system, the iodine
chemistry in the containment when materials from thecontrol rods are present;– Modelling concerning the thermohydraulic and theaerosol behaviour in the containment, the release andtransport of the fission products are acceptable.
Furthermore, the preparation of the fifth test, planned for
2004, gave rise in 2002 to the end of the preliminary
calculation phase, in collaboration with the German, Swiss
and Japanese partners of the programme. Concurrently,
major clean-up work was conducted in the experimental
facility, before the installation of the new experimental
circuits.

Lastly, an international exercise coordinated by IRSN was
conducted under the auspices of the OECD (Organisation
for Economic Co-operation and Development). The purpose
was to test the performances of various software systems
using the second test results. This project brings together
over 30 bodies, located in 20 countries, to test 15 types ofsoftware. In 2002, new partners took part in the programmesuch as Mexico, Turkey and Croatia. They participated in
the specification of the calculations to be performed andin the analysis, which will be completed in 2003.

ASTEC, an integrated calculation tool
Developed for more than ten years with GRS (Gesellschaft
für Anlagen und Reaktorsicherheit – Germany), ASTEC is
an integrated software system. It is used to simulate acore meltdown accident in a water reactor, from theinitiating event to the possible releases of fission products
out of the containment. ASTEC is currently used within
the framework of Probabilistic Safety Assessments
performed by IRSN. It is also used for the definition of the
Phébus FP experiments. Today, ASTEC is becoming theEuropean reference for integrated system software in its
area.
The main efforts carried out in 2002 focused on the V1
version, delivered during the middle of the year. This will
now be strengthened, in particular within the frameworkof EVITA, the European ASTEC qualification project.
Furthermore, new models were developed, concerning
iodine in particular.
Lastly, the training of software users started in 2002 andinvolved concerned 40 people from all European countries.

SARNET, creation of a network of excellence on
core meltdown accidents
Conducted by IRSN, SARNET is a project which will be
submitted to the first call for tender of the 6th Framework
Programme. The purpose of this network is to better
coordinate the research efforts of European laboratories
dealing with core meltdown accidents. For IRSN, this is
the following step forward in international collaboration
already conducted in this area.
This is also an opportunity to support the ASTEC softwaresystem at the European level, in order to improve its reliability, with the feedback of experiences by European users.
Already, almost 370 researchers and doctorate students
from 52 European organisations have expressed interestin taking part in the network.

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ACTIVITIES> Ensuring waste management safetyT

he purpose of radioactive waste management is
to confine radioactivity to result in the lowest
risk possible level of risk for human beings and theenvironment. To assess the measures proposed bylicensees, IRSN will be able to evaluate their completeness and their quality, in normal or accidental
situations, for the disposal and of various waste
management options. Thus, the Institute has been
carrying out research programmes to acquire appropriate knowledge in the concerned fields.

Medium and long-term issues
IRSN studies focus in particular on:– The safety of radioactive waste treatment, conditioning,interim storage and surface disposal facilities;– The disposal possibilities in deep geological formations.
For this purpose, IRSN develops both field experiments
and modelling;– The studies of the impact on human beings and theenvironment of contaminated sites by former industrial
activities and mining sites.

Evaluation of the feasibility of a deep
geological disposal
Concerning the disposal of the high level and long-lived
radioactive wastes in geological formation, the law ofDecember 30th, 1991, scheduled the presentation of aprogress report on research for 2006. In order to prepare
a possible decision on the feasibility of deep disposal,
the Institute has identified “key points” for the safetyassessment of a disposal in the clay unit of the
Meuse/Haute-Marne site studied by ANDRA (National
Agency for Radioactive Waste Management).

In 2002, IRSN evaluated the geological and hydrogeological modelling presented by ANDRA for the
Meuse/Haute-Marne site. Within this framework, IRSN
took into account the first results of geophysical experiments carried out in the underground research laboratory
at Tournemire using a high resolution 3D seismic method
to assess the capacity of the method to detect secondary
faults in argillaceous media.

Application of the high resolution 3D seismic
method to detect faults in argillaceous media
In a very low permeability clay unit, the transport ofradionuclides preferentially occurs along faults. Therefore,
the assessment of the capacity of a clay unit to hostdeep disposal implies the detection and mapping of theexisting faults.
The high resolution 3D seismic method is a tool aiming at
detecting faults. A seismic survey coordinated by IRSN
was carried out at the Tournemire site (Aveyron).
The principle of the method is the following: vibrator
trucks shake the ground to frequencies ranging from10 to 160 Hz. The 3D propagation of the seismic waves
are reflected by the geological discontinuities. A networkof 5,600 sensors set on the surface and connected to an
acquisition unit enables information to be collect, like asonogram.
The main faults can be identified by classical geophysicalmethods. On the contrary, the secondary faults mappedat the Tournemire site cannot be identified by classicalgeophysical seismic methods (2D).
After preliminary studies, the survey took place over 3
weeks in November 2001. It mobilized almost 20 people.

Those key points highlight three types of concerns:– The general knowledge of the site: structural geology(identification of the secondary fracturing); hydrogeology (outlets and transfer times); chemical andthermal containment capacity of the clay unit;– The feasibility of the design options of a disposal:
assessment of the chemical disturbances; disposal
layout and damaging minimization; sealing andrestoring the environment continuity;– The operation and reversibility conditions of thedisposal.

Geophone used for seismic recording.

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Page 37[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]According to the first results published in 2002, theanalysis of the data did not allow the identification of
the faults in the clay unit. This preliminary result does notmean that the principle of the method is not appropriate.
In fact, progress is expected in the future, which will
enable a better resolution.

Chernobyl experimental platform

Mining waste management

In 1999, IRSN initiated co-operation with Ukrainian organisations (IGS and UIAR) and the CEA (Atomic Energy
Commission), in order to study the transport of radionuclides in the environment. The knowledge acquired
within the framework of this research greatly interested
the concerned countries. For the Ukrainians, this may be
applied to rehabilitation of the site. For the French, this isbeing used as a full-scale validation of models used forthe storage of radioactive waste or the rehabilitation ofcontaminated sites.

Waste from uranium mines contains radioactive residues
stored on site. Their concentration in radionuclides
classifies it in the category of low radioactive waste, but
its volume, its physical and chemical form and the lifetime of the radioelements contained (a period of several
thousand years) nevertheless generate questions regarding public protection.
To begin with, IRSN has to express its opinion on theprotection means implemented by the licensee after
the decommissioning of the mine. Thus, the study of thefile dealing with the radiobiological impact assessment
after the redevelopment of the last site operated, Jouac,
is currently in progress.
More generally, the expertise showed that mining activity
is at the origin of a measurable radiological marking of
the environment. In order to have more complete information, IRSN launched a programme of investigations in2002 upon the request of the Ministry of Ecology andSustainable Development. The purpose of this programmeis to assess available knowledge concerning all the sites inorder to identify the situations of significant marking orlack of information. Then, if appropriate, it can be used tocomplete the knowledge on the radiological status in theless studied mining regions and possibly to suggest
inflections to the existing measures.

Redevelopment of the mining site of COGEMA Lodeve.

In the area called the “Red Forest”, located a few
kilometres from the Chernobyl power plant, soils anddebris contaminated by the accident were buried in
rapidly dug non-waterproof trenches. Subject to theaction of the rain waters, these trenches release radionuclides in the natural environment.

An experimental platform was implemented comprisingequipment used to monitor the contamination. From thisplatform, the researchers study three different environments contaminated in various ways:– The location of the former trench, the most contaminated environment;– The unsaturated zone which extends to the surface
reaching 3.5 m in depth, and in which cracks are notcompletely filled with water;– The aquiferous formation below 3.5 m, where water fills
in the vacuums left by solid material.
Relevant results were obtained, especially in the trenchand in the aquiferous zone. This work, summarised in
2002, was used to identify the particles which mainly
contribute to the radioactivity source, characterise theirrespective dispersions and compare these observations
to the modelling. For the unsaturated zone, the forecastof the long-term migration of the radionuclides will
require the exploration of other phenomena by specificprogrammes.

Chernobyl experimental platform: installation of water sampling probes.

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ACTIVITIES> Expertise used for industrial
risk controlAll the research and expertise work conducted in
the Institute provide it with competencies whichfind applications beyond nuclear power, in particularin the area of industrial risk.

Expertise of classified facilities
As an expert recognized by the Ministry of the Environment,
IRSN conducts critical analyses of danger studies performed
by industrialists. To do so, it calls upon its competencies,
in particular in chemistry, chemical engineering, fire protection and explosion. In 2002, the Institute conductedalmost 40 critical analyses of danger studies concerningfacilities classified for the protection of the environment.
The tripling of critical analyses, compared to 2001, ismainly a consequence of the accident of the AZF plantin Toulouse (Haute-Garonne). The expertise performed
in 2002 concerned various plants:
petrochemistry, transformation chemistry, fine chemistry, agricultural and foodsystem, agro-pharmaceuticals, etc. These
In 2002, IRSN
focused on a very wide range of topics:
performed 40
risks of fire, explosion, thermal runaway,
expertise studies
toxic gas dispersion, environmental
impact. IRSN also performed less comconcerning non
nuclear industrial mon expertises such as the processing of
exemption claims for the implementafacilities.
tion of safety valves on pressurized
equipment or the determination of
domino effects on some industrial sites.

orientate the choice of technological solutions intended
to limit the impact of the olfactory pollution of industries
on the environment. IRSN works on this issue in collaboration with INERIS (National Institute of the Industrial
Environment and Hazards).
In 2002, 15 studies were conducted for industrial facilities(agricultural-food system, rendering and transformation
plants, technical land fill centres), research departments,
local communities (contaminated site services, treatment
plants) and breeding (pigs, poultry).
The Institute also takes part in training on the subject
from professionals working in air quality networks andtreatment plants, DRIRE (Regional Agency for Industry,
Research and the Environment) and DSV (Veterinary
Services Branch) members or within the framework of
DESS and DUT on the environment…

40

Expertises in olfactometry

Physics of aerosols

For over 30 years, olfactometry has used and improved
the knowledge and competencies acquired in the nuclear
sector on gas transfer and dispersion. Today, IRSN
conducts expert activity for industries producing
malodorous gas releases. The results of the olfactometricmeasurements performed by the Institute are used toPhysics and metrology of aerosols find applications outside the nuclear area. In addition, since it is little developedin France, the competencies acquired and maintained
within IRSN are today recognized all over the world.

LPG reception in
the Herrlisheim
site.

38

Panelist sniffing
the olfactometer
sniffing ports.

[ IRSN ACTIVITY REPORT 2002 ]Within this framework, the Institute is represented in
the scientific committee of the national safety research

Canalisedsampling ofan odorous
gas sample.

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Page 39[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]Air contamination
experience: suspension
during an accidental
powder drop.

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institute, which conducts work on professional risks. It
takes part in the work of the contamination prevention
and study association, bringing together agriculturalfood, medical and other industries.
In the area of professional risks, IRSN participated in a
European commission contract for the improvement of
the performance of aerosol samplers at the workplace(CALTOOL). The purpose was to test those sampling tools
to compare their efficiency in different situations anddifferent workplaces. The contract ended in 2002 and was
related in publications.
Besides, many nuclear-related activities may have wider
applications, in particular for toxic powders. A common
interest programme is in progress with COGEMA on thesuspension of powders during drops of the containers.

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In 2002, the first phase of the project was carried out andpresented to the Ministry. The development of qualitative
event trees highlighted safety elements which significantly contribute to the series of undesirable events
leading to the BLEVE on the one hand, and some difficulties to quantify the accidental series, due to the limited
representative nature of some models and the use ofgeneric data, on the other hand.
The assessment involves up to 15 persons in the Institute,with various competencies: safety, development of
Probabilistic Safety Assessments, accident phenomenology, assessment of weather variations or hazards related tohuman activities in the site environment…
The assessment and conclusions should be submitted in
May 2004.

Lastly, the international recognition of its competencies
was expressed by the granting of the “International aerosol
fellow Award” in 2002 to a researcher of the Institute.

Probabilistic assessment in a storage andfilling centre for liquefied petroleum gas
Upon the request of the Ministry of the Environment,
IRSN took on the responsibility for conducting a
Probabilistic Safety Assessment applied to a SEVESO-type
facility. The objective of this assessment is to better
understand the additional knowledge that a probabilistic
assessment could provide for the safety of these facilities.
In collaboration with the French butane and propane
committee, the site choice was made on a storage andfilling centre of liquefied petroleum gas, managed by the
Rhône-Gaz company in Herrlisheim (Bas-Rhin).
The assessment was carried out in two stages:– The definition of a study method appropriate to thefacility, in collaboration with the industrialist concerned;– The performance of the assessment per se.
The assessment consisted in identifying the various accidental series which may lead to a BLEVE (Boiling Liquid
Expanding Vapour Explosion) in case of the heating of
one of the storage capacities, inducing a fire ball, a shock
wave and projections, and assessing the probabilities ofthese series. The initiating events of the accidental series
may be process failures but also internal hazards (fire,
flooding…).

WORK CONDUCTED WITH INERIS

The collaboration between IRSN and INERIS originatesfrom the will of both organisations to develop theirsynergies.
In the area of olfactometry, the collaboration between
both organisations concerns:– Expertise combining IRSN competencies for olfactometry and INERIS competencies for physical chemistry.
Two assessments were conducted in common in 2002;– The draft of an “odours” guide, upon the request of
the ADEME (Agency for the Environment and Energy
Control) and in collaboration with other experts. This
guide will introduce all the approaches that an industrialist shall adopt to limit the olfactory pollution
resulting from his activities;– The implementation of a reflection group on theregulation, measuring techniques and future European
standard as regards olfactometry in late 2002.
Concerning fire risks, collaboration focuses on research
projects. In 2002, the work was particularly focused on
the characterisation of the fire power of various fuels.
Lastly, collaboration regarding ecotoxicology particularly focuses on research concerning the toxic effects ofuranium on the fish and the development of genotoxicity markers.

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ACTIVITIES> Controlling criticality risk
I

RSN deals with various aspects of criticality risk,
from prevention to the assessment of consequences. The purpose is above all to prevent thedevelopment of a chain fission reaction out of a
nuclear reactor, i.e. in a facility not intended for that
purpose (plant, laboratory or transport packing).
This type of reaction involves the release of neutronand gamma radiation as well as the production ofradioactive products likely to be spread out of theconcerned facility. The main consequences of a
criticality accident would therefore be to irradiate
persons who might be close to the accident site.
The Institute develops qualified computer methods
and applies them to the assessment of the measuresused to prevent criticality risk and, in case of
accident, it assesses the consequences on health andthe environment.

Technical and economical issues
Prevention of criticality risk was a major concern beginning with the very first uses of nuclear power. It led to theimplementation of restricting measures: limitation of the
product quantities, container size, water quantities used,etc.
Progress of knowledge today enables some stresses to be
reduced, while ensuring the safety of the facility ortransport packing. In this area, IRSN prepares methods,
develops software and conducts case studies. The objectiveof this work is to have accurate means to analyze thecriticality risk.
The qualification and validation of computer tools focus
on comparing calculation results based on reality andexperiences approaching critical status. The comparisonof the calculated results and experimental results is used
to establish the accuracy of calculations for specificsituations, and, if appropriate, suggest improvements ofthe calculation techniques.
Beyond research, IRSN also provides expertise, inparticular for laboratories, plants and transport. The workin analysis involves checking that prevention measures,
suggested by the licensee on the basis of calculations, areappropriate and sufficient, including cases of possible
malfunctions. For the transport of fissile materials, theverification of criticality calculations of carriers is
systematic. In the case of assessments carried out with40

[ IRSN ACTIVITY REPORT 2002 ]third-party software, counter-calculations are conducted.
Every year, over 50 files concerning the transport of fissile
materials, each corresponding to multiple contents, arestudied in the Institute.

CRISTAL, a new generation criticality-safety
package
CRISTAL is a programme conducted by IRSN, developedwith the CEA and financed by COGEMA.
Since 1999, the first version of this software has been
made available to IRSN, the CEA and major French nuclear
industrialists (COGEMA, Framatome, Technicatome). It is
used by 90 engineers and is currently being tested by EDF.
Within the framework of this programme, IRSN develops
the 3D multi-group neutron simulation code, Moret IV.
Furthermore, it is equipped with the man-machineinterface which ensures the integration of various
calculation modules, as well as the connection with users,
which is used to take into account their experience.
In 2002, a CRISTAL Web site was opened to the publicat large; there is also a Web site restricted to users sothey can share information, remarks and inquiries. Users
can also download documents or correction patches.
In addition to the development of a user community
promoting the exchange and the availability of
information, the openness of the site was intended to
implement a working organisation with users, especiallyfor maintenance.
It was updated for the first time in September 2002. The
development of the next version has been initiated. It will
include new functionalities and is slated to be deliveredin September 2003.
Lastly, IRSN participates in the International Criticity
Safety Benchmark Evaluation Project, under the auspicesof the OECD. This project consists in pooling criticality
experiences which have been conducted around theworld for over 20 years. This work is essential for thequalification of calculation systems such as CRISTAL sincein fact, almost 1,200 criticality experiences from various
sources were recalculated by CRISTAL.

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Page 41[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]A common interest programme with COGEMA
In 2002, experimental programmes were carried out within
the framework of the Common Interest Programme initiated with COGEMA as of 1996. This programme concerns
the prevention from criticality risks in fuel cycle installations and transport.
The purpose is to quantitatively assess the safety margins
related to the loss of reactivity of irradiated fuels, andto develop more accurate calculation methods intended toassess criticality risks. For those fuels, experiences havebeen conducted for six stable fission products causing halfof the reactivity loss generated by the fission products.
In addition, this programme aims at improving the criticality calculation systems to meet new needs for nuclear
facilities and the transport packing for fissile materials.
The experiments conducted on the Valduc (Côte-d’Or) site
are unique in the world.

An exercise to compare the dosimetry methods
for criticality accidents
In 2002, IRSN organised an international intercomparison
exercise of dosimetry for criticality accidents. This
operation, jointly conducted with the OECD Nuclear
Energy Agency, was performed in collaboration with the
Valduc CEA centre. It was supported by the European
Commission.

Almost thirty countries from Eastern and Western Europe,
North and South America, as well as Asia, participated inthis exercise.
It enabled each of them to test thephysical and/or biological dosimetry
techniques in experimental conditions simulating a criticality accident.

29This intercomparison had been scheduled just before the criticality accident which occurred in September
1999 in Tokaï-Mura (Japan).

60

It involved experiences conducted inthe Valduc CEA centre on the Silène
reactor, simulating different criticality
accident configurations generating
an intense release of neutron andgamma radiation.

500

The results of the final assessment
and the conclusions will be publishedwithin the framework of the “9thInternational Symposium on Neutron
Dosimetry” in Delft (Netherlands) in
September 2003. A complete session
will be dedicated to this intercomparison.

different countries

laboratories

irradiated dosimeters
for the international
intercomparison of
accident dosimetryorganised by IRSN
in 2002.

International
intercomparison of
dosimetry on the Silène
reactor: positioningof dosimeters.

Criticality dosimeters exposed around the Silène reactor.

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ACTIVITIES> Assessing transport safetyT

he use of some package types to transport ofnuclear materials is subject to an agreement
issued by the competent authority: DGSNR for civil
use transports, DSND for the transport of materials
for Defence purposes. IRSN performs studies andresearch as well as expertise on the transport ofnuclear materials.

Expertise of transport packages
Every year, the Institute transmits between 100 and
150 technical notices on the compliance of transport
packages of nuclear materials according to regulations.
In these technical notices, several aspects are considered:– The safety of the radioactive material containment;– Radiation protection of workers and of the public;– Prevention from criticality risks.
The certifications of new packages are issued for a periodof three to five years. In the case of a certification
extension, the Institute performs partial expertise only,with particular emphasis on the examination of acquired
experience. For some types of packages, the expertise
especially focuses on the radiolysis risk.

lytical experiences, it was decided to proceed on a caseby case basis and to conduct campaigns for measuring
the hydrogen concentration depending on weather
and the activity of the waste transported. This was used
to quantify the phenomena and to show that thehydrogen concentrations do not reach safety limits;– Those used for the transport of plutonium oxide (FS 47,
TN BGC-1), for which oxygen absorption, and nothydrogen production, appears.
The safety approach related to the radiolysis risk is a
gradual and cautious approach which first consists in
issuing transport authorisations for power ranges andlimited durations, and then extending these authorisations depending on the results of the experimental
programmes.
DISTRIBUTIONS OF THE 111 TECHNICAL NOTICESRELATED TO THE PACKAGES TRANSMITTED IN 2002
Foreign 10
Frenchmiscellaneous
12

COGÉMA 55

Framatome 7Radiolysis during the transport of nuclear materials
The phenomenon of radiolysis (decomposition of water
into hydrogen and oxygen by ionising radiation) may
have an impact on the safety of the transport packages,
as it may lead to an explosion. For this particular issue,
the Institute has conducted a review of the packagemodels approved or under special agreement for 10 years.
Given the diversity of the situations encountered and thecomplexity of the radiolysis phenomenon, industrialists
have been requested to base their justifications on experimental values. Industrialists performed measurements
in real conditions, in order to quantify the radiolysis
phenomenon for all packages. For this purpose, they
developed experimental programmes, including some
now which are nearing completion.
The packages concerned are divided into several categories:– Those used for under-water transport of irradiated fuels
intended for reprocessing: CASTOR S1, EXCELLOX 6,
NTL 11, NTL 15. These packages have been equippedwith new catalysts (recombining hydrogen and oxygen)used to remove the gas released by the water radiolysis.
The assessment of this equipment is in progress;– Those used for the transport of organic waste (cellulose,
various plastics, gloves…): TN GEMINI, RD 26, RD 15IIB,IU 11, DGD-D-001. Given the difficulty to conduct ana-

42

[ IRSN ACTIVITY REPORT 2002 ]CEA 10

Bio CIS 13

USING FEEDBACK FROM EXPERIENCEIRSN analyses the incidents and accidents oftransport of nuclear materials. Thus, the analysis of
the incident occurred on December 29th, 2001 at
Charles-de-Gaulle Roissy (Val-d’Oise), during atransport of radioactive products from Sweden to theUnited States led to the following conclusions:– The quality of the package preparation shall be
rigorously controlled;– The packaging of the package content will be better
specified;– The radiation protection programmes, compulsory
since July 2001 for air transports and dosimetricmonitoring of the most exposed workers, will be
rapidly implemented by the carriers.

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End of the Common interest programmewith COGEMA on the safety of the transportof nuclear materials
Started in 1996, the Common interest programme
ended in 2002 with the completion of a study on thethermal behaviour of the transport packages TN 12/2 andTN 28 VT, subject to fires of variable duration.
According to the regulation, a type-B package shall resist
a 800° C fire during 30 minutes, in order to be authorised.
The purpose of this study was to determine the realistic
durations of fire resistance of the packages for different
temperature levels.
A calculation approach was used to realistically describe
the behaviour of some package materials such as resin.
The study used three-dimensional models appropriate to
the simulation of the phenomena and especially toidentify the presence of discontinuities in the packages.
The code developed was qualified using the experimental
results obtained on a real package and on samples subject
to tests in an oven. The simulation was used to determine
the maximum durations of fire resistance of thesepackages by studying the risks of loss of seal tightness,clad failures and deformation of the internal structure of
the package.
Four temperatures were studied: 400° C, 600° C, 800° C,
1,000° C. Temperatures below 800° C concern mainly
maritime transport. The 1,000° C temperature is associatedwith tunnel-type configurations or special hydrocarbons(kerosene type).

A ship for the transport of spent fuel packages (TN12/2).

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A NEW COLLABORATIONCONCERNING RADIATIONPROTECTION IN TRANSPORTS

Dosimetric data of the SISERI database have been usedas part of a European study on the statistics oftransport flows and doses, conducted in 2002 andintended to better understand the impact of transport
on workers’ dosimetry.

The calculations related to both packages take into
account the temperature increase inside the package
after the end of the fire. For example, the containment of
the TN 12/2 and TN 28 VT packages is ensured for an
800° C fire lasting over 1 h 40, which highlights a safetymargin of about three times the regulatory duration of
30 minutes.
This study confirmed the significance to use threedimensional models despite the complexity of theirimplementation.
Within the framework of this programme, IRSN developed a very sophisticated tool intended to assess thetemperatures of the packages in various fire conditions:
THERMX-PROTÉE, now available for applications to otherpackages.

Return of vitrified residue to Japan in TN28VT transport packages.

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ACTIVITIES> Reinforcing fire protectionT

he risk of fire is a major safety concern, given theprobability of a fire in a nuclear facility andthe severe consequences that a non controlled firemight cause. The research, studies and expertise
conducted by IRSN on fires allow better assessmentof the measures taken by the licensees to ensure thesafety of their facilities and promote improvements.

A close connection between expertiseand research
The assessment of the technical measures taken by thelicensees to ensure the safety of their facilities against
fire risks revealed the existence of insufficiently known
areas requiring research actions. These actions include
experimental programmes and modelling work and theresults of this research contribute to improve the safetymeasures implemented.

Studies underlying areas of uncertainty
The studies conducted to support safety assessment
focus on all the mechanisms which can generate releasesof radioactive products following a fire. Among thesestudies, the Probabilistic Safety Assessment conducted on
the risks of core meltdown in case of fire in a 900 MWe
power plant particularly highlighted significant uncertainty areas that led IRSN to perform research to improveknowledge. This was the case for the following topics:– The combustion of electrical boxes: the CARMELA
programme provided in 2002 first results related to thissubject;– The propagation to adjoining premises via ventilationand the openings of a fire started in a close and ventilated room with the DIVA programme being initiated;– The behaviour of compartmentalisation and containment equipment (doors, fire-dampers, filters…) submitted
to stresses resulting from a fire: the STARMANIA programme, started in 2001 and continued in 2002, studies
this subject;– The “characterisation” of fuels: the action conductedby IRSN aims at improving the existing database bymeasuring certain physical properties of almost thirtymaterials.
The first lessons drawn from these research programmes
have already been used for expertise purposes, in particular for the assessment of the vulnerability of the control
rooms of nuclear power plants. Improvements have been
recommended following this assessment.

44[ IRSN ACTIVITY REPORT 2002 ]Furthermore, the examination of the operational
experience highlighted other concerns, such as the sootcorrosion aspect and the evolution of the concrete tightness submitted to a thermal flux. Those topics are subject
to thorough thinking in order to define, if appropriate,
future research programmes.
Most of the topics cited above and the results of thecorresponding research also demonstrate an interest forthe safety of the laboratories and plants. For these types
of facilities, work was initiated in 1998 in order to revise
the Fundamental safety regulation l.4.A, related to fire
protection of basic nuclear installations other than
nuclear reactors. The objective is to take into account the
progress of knowledge and to better distinguish problems
in the fire area (compartmentalisation of the premises)and problems in the containment of radioactive materials.
The new draft, discussed in November 2001 by the FrenchStanding group of Experts, was deepened in 2002 andwas subjected to application tests in a facility.

SAFETY ASSESSMENT

In 2002, the Institute studied the Fire action Plan
implemented by EDF on its installations, and submitted
its technical notices to the French Standing group ofExperts for nuclear reactors on November 7th and 21st,
2002. These technical notices highlight:– The needed evolution of the baselines, given the
research conducted within IRSN;– Improvement proposals for the CPY control room.

Test of the CARMELA
programme for studying
the combustion ofelectric cabinets.

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Research to improve scientific knowledge
The propagation of a fire to adjoining premises via
ventilation and/or the openings of a fire started ina close and ventilated room.
The DIVA facility was set up in 2002 to improve knowledge on the propagation of hot gas or particles toadjoining premises of a burning room, via the ventilation
system and the other communicating channels (doors,
openings,etc.). This facility houses three rooms leading
into a common corridor. A fourth room is used to study
the propagation to the upper stages. The premises areconnected by doors, for which leakages may be calibrated,and by an industrial-type ventilation network. The firsttests took place in 2002 and their interpretation is inprogress.
The solvent fires in the storage cells of the
COGEMA plant of La Hague (Manche).
The FLIP (Liquid fuel fires interacting with a wall) test
programme was conducted between 1996 and 2002 incollaboration with COGEMA. It concerns the developmentof a pool solvent fire (hydrogenated tetrapropylenetributyl phosphate or TPH/TBP) that might occur in aroom dedicated to the storage of this solvent. In 2002,
the focus was on the carrying out of the final tests andthe interpretation of the tests performed during theprevious years, as well as the qualification of the
FLAMMES/SIMEVENT coupled code on the basis of thosetests. A summary document was drafted following this
instructive programme (for example, on the maximum
levels and the temporal evolutions of the pressuresand temperatures for different ventilation network operations).

Solvent pool fire testof the FLIP (Liquid fuelfire interacting witha wall) programme.

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T=0,250 s

The behaviour of compartmentalisation andcontainment equipment subject to a fire.
To better assess the behaviour of the compartmentalisation elements in case of fire, in particular their resistanceto pressures which may result from these, a programme
was conducted in 2002 in the STARMANIA facility
concerning the aeraulic behaviour of fire dampers andtheir degree of mechanical resistance. Furthermore, filter
clogging, which may lead to a loss of containment of theradioactive substances, in particular by breaking the filter
medium, was studied in the BANCO facility. All the tests
performed on filters were used to develop an empiricalmodel of aeraulic resistance used in the modelling of theinteraction between ventilation and fire.
Combustion mode of electrical boxes.
The first tests of the CARMELA programme, conducted in2000 and 2001, were interpreted in 2002. A complementary experimental campaign, CARMELA Bis, was definedand prepared in 2002 to better characterise some physicalparameters used by the model developed during theinterpretation of the CARMELA tests. The programme will
be completed in 2003 by the carrying out of combustion
tests on real cabinets.
Suspension of radionuclides.
In case of fire involving radioelements, these can bereleased in the form of aerosols or gas. The determinationof the suspension factors is essential to assess thereleases of radioactive materials and the radiologicalconsequences for workers and the fire fighters. Regarding
this subject, IRSN completes and improves the BADIMIS
database concerning the suspension of particulatecontamination by different mechanisms.

Starmania facility used
to study the behaviour ofcontainment andcompartmentalisationequipment in case of fire.

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IRSN
Ensuring non-proliferationand protection against
malevolent actions
on-proliferation of nuclear, chemical and biological weapons and protection against malevolent
actions are two areas where IRSN conducts
expertise work and research. Some of its agents arealso authorised to conduct inspections. It reports inparticular to the Senior Civil Servant for Defence ofthe Ministry of Economy, Finance and Industry.

N

IRSN makes its knowledge and practices available to
the French authorities and international organisations
involved in the implementation in France of treaties of
non-proliferation of nuclear, chemical and biologicalweapons.
Control of nuclear materials during transport.

62
In 2002, IRSN performed 62
analyses in the chemical area
for the Senior Civil Servant for
Defence of the Ministry of
Economy, Finance andIndustry.

50 inspections
100 reports
IRSN assesses measurements
by operators to protect theirfacilities and nuclear matter
contained in these. Within
this framework, the Instituteperformed 50 inspections
and transmitted 100 advisor
reports to the Senior Civil
Servant for Defence in 2002.

46[ IRSN ACTIVITY REPORT 2002 ]Protecting nuclear facilities and transport of nuclear
materials against malevolent actions which may leadto radioactive releases in the environment is the aimof the struggle against malevolent actions whichbecame an even greater concern after the terrorist
attacks in September 2001.

> Non-proliferationof chemical weapons
IRSN lends its technical support to public authorities and to theindustrialists for the implementation in France of the international
controls in the non-proliferation area. Initially, only the nuclear sector
was concerned. Given the experience acquired by the Institute inthis area, the public authorities commissioned it to ensure the same
mission for the application of the Convention on the Prohibition of
the Development, Production, Stockpiling and Use of Chemical
Weapons and on their Destruction (CWC), signed in Paris in January
1993. Lastly, since 1999, the Institute has also been involved in thearea of the non-proliferation of biological weapons.

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Page 47[ N O N – P R O L I F E R AT I O N A N D P R OT E C T I O N AG A I N ST M A L E VO L E N T AC T I O N S ]ACTIVITIESThe Convention on the Banning of Chemical Weapons
entered into force in France in 1997. Since this date, theInstitute has provided expertise and undertaken technicalsupport missions requiring scientific and legal competencies, focusing on three activities:

Technical support to the authorities forinternational negotiations and for the
implementation in France of the Convention
in the civil sector.
The Institute carried out the census of industrialists
concerned by the Convention, who must declare theproducts they use. It analyses and processes their declarations.
Concerning the international relations, in 2002 IRSN
participated in the expert group implemented by theOrganisation for the Banning of Chemical Weapons,on the homogenization of the declarations. This resulted
in November 2002 in defining rules and declarationthresholds for imports and exports of the chemical
products concerned, common to all convention signatory
countries. This will imply a change in the French regulatory
texts, manuals and declaration forms. The related work
was launched in 2002.

Advice to industrialists for preparing
the declarations and international controls.
IRSN advises industrialists for preparing declarations,taking into account the characteristics of their facilities.
Preparatory visits before international inspections
represent for IRSN educational work to the industrialists.
The purpose is to make them aware of the provisions of
the legislative and regulatory Convention texts and of theconsequences for facilities: check of declarations, frequency
of inspections, access of inspectors to “sensitive” areasand information for the economic development of thecompany. IRSN performs preliminary visits of the sites inorder to facilitate the process of the inspections proper.
In 2002, the Institute performed 18 preliminary visits.

Control of nuclear materials
during transport.

Supporting the international inspections
Performed by the OPCW, the purpose of the inspections is
to check the compliance of the information transmitted
by the French authorities in the declarations. During
these inspections, IRSN, as French state representative,
plays a role of interface between inspectors and industrialists. The sites inspected are chosen by the OPCW frominformation provided in the declarations.
Until 2000, most of the inspections conducted in theworld concerned the main industrialised countries. This
represented 20 inspections for France. In April 2000, theinspection was extended to all organic chemical products,
significantly increasing the number of countries involved.
After facing some financial difficulties, the OPCW
continued as before with the same sustained inspection
pace as of the fourth quarter of 2002.

MONITORING OF TRANSPORTFOR SENSITIVE NUCLEAR MATERIALSThe Transport Operational Echelon (EOT) was createdin 1983 within the Institute to assume operational
responsibilities in the area of the management andmonitoring of transport of nuclear materials.
Within this framework, every year it examines almost
2,000 transport authorisation requests and ensuresthe monitoring of these transports on the national
territory.
This involves road, rail, sea or air transport (from or toa port or airport under French jurisdiction).
The monitoring of each transport is in keeping withthe sensitivity of the materials transported. Sometransports, among the most sensitive, follow routes
authorised by the Senior Civil Servant for Defenceof the Ministry of Economy, Finance and Industry andare monitored in real time by IRSN, with satellite
communication means.
This monitoring allows any incident, accident or event
to be detected which may delay or hinder thetransport. In such cases, the EOT takes appropriate
measures: information to authorities, initiation of
emergency of physical protection actions, transport
stop, route change, etc.
In addition to transport monitoring, the agents
authorised by the EOT conduct unannounced
transport inspections, in order to ensure thecompliance of the regulatory provisions. Crossing
conditions for highway tolls and borders, reception
and parking conditions of convoys, locking andmonitoring of vehicles during stopovers, etc. Morethan 40 inspections are conducted every year, inharbours, stations, borders and airports or near
installations authorised to have nuclear materials.

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ACTIVITIES> Protection against malevolent actions
O

ne of the Institute’s missions is to assess themeasurements taken by the industrialists toprotect their facilities and the transports of nuclear
materials against possible malevolent actions which
may cause releases of radioactive products in theenvironment. Of course, the results of those assessments remain highly confidential, but the terrorist
attacks of September 2001 reinforced the concern of
public authorities in this area.

other industrial sectors outside the realm of nuclear activity. Those events are compiled in a record of malevolent
actions, drawn up by the Institute. In 2002, suggestions
were made by the Institute to harden the typical threats,in particular by taking into account the lessons drawn
from the attacks of September 11th, 2001. Furthermore,
IRSN also suggested to the authorities draft regulatory
texts aiming at reinforcing and specifying the regulations.

Malevolent actions facilities
The assessment of the measures taken or provided for by
the operators is performed by the Institute from predefined types of threats. The purpose is to ensure that thesemeasures are sufficient and to recommend, if necessary,
the implementation of complementary measures. The
approach adopted comprises three stages:

In 2002, a particular effort was made to control access tofacilities: implementation of complementary provisions
and verification of this implementation on the sites(about thirty), as part of the Vigipirate anti-terrorist plan.
These stiffer measures of the access of persons, vehicles
and goods concerning EDF, the CEA, COGEMA, EURODIF(European uranium enrichment by gaseous diffusion
plant) and ILL (Laue-Langevin institute).

– The assessment of the sensitivity of the various facilities
and equipment. Sensitivity is characterised by thesignificance of the consequences which may result
from a malevolent action, i.e. quantities of radioactive
or chemical products which may be released in theenvironment;

Lastly, the Institute conducted experiments and studies
on the assessment of damages to buildings, storage
ponds, and ventilation systems in case of malevolent
actions.

In addition to those assessments, IRSN supports theinspections of nuclear facilities in the malevolent area.

– The assessment of the vulnerability of the equipment
considered sensitive, i.e. the assessment of the difficulty to launch a given attack on this equipment;– The research, if necessary, of complementary provisions
used either to reduce the equipment sensitivity or to
make a possible attack more difficult.
Several typical threats have been defined: their relevancy
is subject to a comparison with the lessons drawn fromevents having occurred in France or abroad, possibly inDigital simulationof an explosive
detonation.

48[ IRSN ACTIVITY REPORT 2002 ]Transport of casksof spent fuels.

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Page 49[ N O N – P R O L I F E R AT I O N A N D P R OT E C T I O N AG A I N ST M A L E VO L E N T AC T I O N S ]Digital simulation of an explosive detonation.

Transport of packing and spent fuels.

Malevolent actions against transportsof nuclear materials
IRSN conducted research, in particular concerning theresistance of packing to terrorist attacks. The purpose ofthis work is to have tools to assess the consequences ofsuch attacks, to be able to suggest appropriate technicalor regulatory developments. If the packing design
resulting from the application of the safety regulation
ensures a certain degree of defence and if various tests
were performed in the past, the approach adopted today
is more systematic with the use of digital simulation. It is
intended to focus on the tests to be performed and to
make better use of these.
Since 2000, IRSN has been developing a programme
intended to study a representative assembly of packing
subject to various types of weapons (firearms, high explosive charges, antitank weapons, etc.). The related work is
jointly conducted with the DGA and the CEA.
In the area of explosive charges, 2002 saw the completionof tests for a first packing, with the validation of associateddigital models.
Concerning perforating charges, a study was conducted
in 2002 for this same transport packing and showed thatthe results from the digital simulation were consistent
with the results from experiments.
Concurrently, collaboration was launched with the UnitedStates, the United Kingdom and Germany concerning
the possible radiation consequences of an attack of atransport of irradiated fuels with a perforating charge.

STUDY OF IMPACT OF AN AIRCRAFT
ON A POWER PLANT

Following the attacks of September 11th, 2001, IRSN
performed a study on the mechanical behaviour ofthe containment of a nuclear power plant in 2002
modelling in detail an attacker using a commercial
aircraft of currently in operation and considering
different trajectories and speeds as well as different
impact points.
The attacker model was made with the efficient assistance and collaboration of the aircraft manufacturer
which had models that needed to be adjusted to take
into account the differences between a frontal
collision and a landing crash. The important aircraft
characteristics, such as the various masses of theirdistribution, the mechanical behaviour of the different
parts of the aircraft and their connections, as well as
specific engine behaviour were taken into account.
The study conducted by IRSN provides information on
the ultimate containment capacities, regarding both
assembly stability and perforation possibilities, andmaterial needs due to the collapse of the whole
facility.

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IRSN
Promotinginternational relations
he purpose of the partnership between different
countries is to pool resources, enrich knowledge
and share competencies. It supports synergies
between research and expertise.

T

In the areas of safety, radiation protection or security,
the international openness of IRSN has grown overtime. This activity is organised along three lines:
deepening scientific and technical knowledge, participating in the creation of guides, recommendations or
standards and supporting the reinforcement of
nuclear radiation protection, safety and security
abroad.
Construction of the new “dry” storage facilityof irradiated fuels on the Chernobyl site.

29
IRSN projects with safety or radiation
protection organisations in 29 countries.
Argentina
BelgiumBrazilBulgaria
CanadaChina
Croatia
Cuba
Czech Republic
Egypt
FinlandGermany
Hungary
India
Italy

50

[ IRSN ACTIVITY REPORT 2002 ]Japan
MoroccoPortugal
Republic of Belarus
RussiaSlovak Republic
Slovenia
South Korea
Spain
SwedenSwitzerland
UkraineUnited Kingdom
United States> An internationallyoriented Institute
Deepening scientific and technical knowledge
By increasing knowledge, completing available tools, in particular
computer codes and improving methods, international co-operation
developed by IRSN in the areas of research and expertise contributes to better assess risk and improve control. Discussions andwork are conducted within the framework of bilateral or multilateral co-operation agreements or programmes launched byinternational bodies and these lead to conclusions which may besubject to international consensus.

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ACTIVITIES

Active participation in international
programmes
For the Framework Programme (FP6) of the European
Atomic Energy Community (EURATOM) for research andtraining activities, 2002 was a transition year with thecontinuation of FP5 and the launch of FP6.
For the 5th PCRD, IRSN contributed significantly in 2002
to almost twenty projects: in the area of severe accidents,
achievement of COLOSS (European project dedicated tothe study of the core damage during a severe accident)
and ENTHALPY (European base of the corium thermodynamic data); continuation of BIODOS, related to theradiation protection of workers and the public (dosimetricmodels), ICHEM (study of iodine behaviour in a reactor
containment), BORIS (study of the migration of radioelements in the soil).
With the FP6, the European Commission suggested acompletely different approach whereby the European
research space structur implies that organisations join
forces in networks of excellence, with long-term common
means and strategies, or implement wide integrated
projects. IRSN has become strongly involved in thisapproach: the implementation of the SARNET networkof excellence on the core meltdown accidents in apressurized water reactor (PWR) is the first example ofthis sort.
Lastly, within the framework of the EURADOS (European
Radiation Dosimetry Group) work, co-financed by theEuropean commission, an intercomparison exercise
regarding radiation dosimetry in the environment was
conducted in 2002. During the year, IRSN was presided
the EURADOS association, which brings together over
30 European organisations around two main objectives:to make progress in ionising radiation dosimetry and topromote the development of methods in this area.
Among major international programmes, IRSN continued
in 2002 the Phébus programme in which 35 organisations
participated and the Cabri-Water loop programme,a wide international co-operation scheme supportedby the OECD. It took part in the launch of the MCCI
programme (study of the molten core flow out of thevessel and interactions with containment concrete)bringing together 13 OECD countries.

[ I N T E R N AT I O N A L R E L AT I O N S ]Development of bilateral collaboration
2002 was the year for the renewal of the generalagreement between IRSN and the JNC (Japan Nuclear
Cycle Institute) and negotiations for the renewal of thegeneral agreement with the JAERI (Japan Atomic Energy
Research Institute). The latter will deal in particular withthe release of fission products during a severe accident
and the criticality risks in fuel cycle installations.
Furthermore, co-operation with Russian research institutes,
IBRAE (Nuclear Safety Institute of the Russian Academyof Sciences) and Kurchatov, continued in 2002 aroundcomputer codes concerning severe accidents, and thenegotiation to reach an agreement with the Belgian‘Association Vinçotte Nuclear’ (AVN) was initiated.
Lastly, negotiations were conducted with the Bulgarian,Slovenian and Romanian organisations for their participation in the Phébus FP programme.
In the radiation protection area, a co-operation agreement was signed in December 2002 between IRSN and
the Cuban CPHR (Centro de protección e higiene de lasradiaciones). Initial co-operation issues concern theimpact of the Chernobyl accident on health, the assessment of the impact of radioactivity on the environment,
the treatment of people accidentally overexposed andthe measurement of low-level radioactivity.
2002 was also a year for the reinforcement of collaboration between IRSN and Russia (Institute for Bio-physics,
Moscow, and Medical Radiological Centre, Obninsk).
A new wave of co-operation was launched in 2002 with
the IBRAE Institute in the radio-ecology area (CITRAME
project).

Taking part in the development of guides,
recommendations or standards of nuclear
radiation protection, safety and security
This activity is based on IRSN expertise and aims at
developing documents intended, for the most part, toguide nuclear actors in their practices.
In this area, IRSN participates in the work of consultative
groups, committees and working groups from the IAEA,
AEN, UNSCEAR, ICRP and the European Commission…

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ACTIVITIES

Promoting the reinforcement of radiation
protection, safety and security abroad
The safety of nuclear facilities in some foreign countries
is a major issue of IRSN international co-operation
regarding expertise. The purpose is to promote, throughconcrete collaboration, to the reinforcement of thecompetencies in the concerned countries.
Within this framework, Eastern European countries are
the subject of several collaborative projects and most ofthese are conducted in close co-operation with theGerman GRS. They particularly result in the carrying out
of assessments, the implementation or development ofregulatory systems, initiation to the use of computercodes and their transfer. In particular, IRSN participatedin the launch of the international review project of thesafety report of the unit 1 of the Russian power plantin Kursk in 2002. It took part in the implementation of
the projects related to the definitive shutdown of theChernobyl nuclear plant, reactors 1 and 2 of Kozloduy(Bulgaria) and the Ignalina (Lithuania) reactor 1, thereduction of the risks that the current sarcophagi may
have induced, as well as the overall improvements to the
Ukrainian nuclear power plants, to the Metzamor
Armenian plant and to the Ignalina reactor 2.
In Ukraine, a bilateral agreement signed with the
Ukrainian technical safety organisation (State Scientificand Technical Centre) resulted in 2002 in the launch ofcommon work on waste management, training andsafety studies. The purpose is to compare the practices
and regulations in France and the Ukraine.
Among the events in 2002, the launch in June, during theG8 summit in Kananaskis (Canada), of the “G8 international partnership of the non-proliferation of weapons of mass destruction
and related materials” led publicauthorities to request IRSN to work on
the areas of securing of nuclear materials
and radioactive sources in the RussianFederation.
In Georgia, following the accident
which occurred in December 2001 in
Lia, where 3 inhabitants were severely
exposed to radioactive sources, IRSN
performed complementary expertise

Indian Delegation at IRSN.

52[ IRSN ACTIVITY REPORT 2002 ]on one of the patients in 2002: dosimetric reproduction
and mapping of the dose received at the level of the skinarea to be transplanted. This expertise was carried out tosupport the medical management of the victim treated in
the Army Hospital of Percy (Haut-de-Seine).
It should be noted that currently relations between IRSN
and its partners (safety and radiation protection technicalorganisations, research organisations, etc.) in Eastern
Europe are developed towards more regular co-operation.
IRSN promotes those changes as well as the exchange ofcompetencies with these countries. Thus, the Institutesupported the creation, in September 2002, of the CENS(Centre for Expertise in Nuclear Safety). This network,
bringing together the safety organisations from Central
and Eastern Europe, aims at reinforcing expertise capacities
in these territories.
Beyond Europe, the reinforcement of the co-operation
with China gave rise in 2002 to the adjustmentof Chinese needs in the SESAME crisis management
system for the French-designed Daya Bay and Ling Aoplants, as well as to many exchanges in the areas of theprotection and fire fighting, the safety of experimental
reactors, etc.
With India, the co-operation agreement between IRSN
and the BARC (Bhabha Atomic Research Centre) was
extended to cover radiation protection. Moreover,exchange concerned the application of accident
computer codes for safety studies related to Indian powerreactors.

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Page 53[ I N T E R N AT I O N A L R E L AT I O N S ]> Close co-operation between
France and GermanyCo-operation between IRSN and the GRS (Gesellschaft für Anlagen und Reaktorsicherheit) began
in 1989 with the signature of a first partnershipagreement, reinforced in 1998 with the creation of aboard of directors bringing together the executivesof both institutes. The numerous joint actions,conducted for over 10 years, have contributed todefine the basis for a European approach to nuclear
safety issues.

The main actions conducted in 2002
– The implementation of the FGI (French-German initiative
for Chernobyl), programme intended to gather, in theform of databases, the technical information available
on the consequences of the Chernobyl accident, in the
Ukraine, Belarus and Russia, focusing on three issues:
sarcophagi safety, transpor of radioelements in theenvironment and public health. These databases will bemade available to public authorities, scientists andpublic.
In 2002, the sarcophagi safety database assessment
was prepared for its integration into the international
database financed by the EBRD (SIP project) within theframework of the construction of the new sarcophagi.
Concurrently, the radioecology programme was completed when the radioecological data was integrated in
the REDAC (Radioecological Database after Chernobyl)common database. Furthermore, the “health” aspect ofthe project is proceeding, with the monitoring of longterm effects of the accident on the population. Lastly,
the development of an Internet site displaying thegeneral results obtained in the three areas is in progress;– Co-operation for improving the safety of the Eastern
European nuclear plants carried out through Riskaudit,
an IRSN/GRS subsidiary, and in collaboration with theother European safety technical organisations, within
the framework of the PHARE and TACIS European
programmes and the EBRD projects;– Continuation of the common development of the ASTEC
computer code modelling core meltdown accidents;– Continuation of the co-operation concerning theexpertise of the EPR PWR project;– Development of the EUROSAFE project, intended topromote the future creation of a European expertise
pool for nuclear safety: in 2002, the fourth EUROSAFE
forum, an annual scientific and technical international
event, gathered just under 500 participants in Berlin(Germany). 50 scientific and technical presentations
were presented during this exhibition. The Eurosafe
Tribune, a magazine distributed to all forum guests waslaunched in 2002.
Lastly, an Internet site in French, German and English(www.eurosafe-forum.org) has been set up to informparticipants on the reflections and work conductedby safety and radiation protection organisations.
The implementation of the EUROSAFE approach is
conducted by a programme committee comprising 6
European safety and radiation protection organisations:
AVN (Belgium), CSN (Spain), GRS (Germany), HSE(United Kingdom), IRSN (France), SKI (Sweden). In 2002,
the EUROSAFE approach was financially supported by
the European Commission. This resulted in reinforcing
its European dimension.
Concurrently, the year 2002 saw the reinforcement of
AVN/GRS/IRSN co-operation. A first tripartite meeting
held in December in Brussels (Belgium) to reinforce
co-operation within the organisation, safety assessment
methods and safety re-examination. It focused primarilyon the assessment of organisations, the quality of theexpertise according to the new AFNOR standard andsafety re-examination.

The EUROSAFE forum
organised in 2002
in Berlin brought together
over 500 participants.

The EUROSAFE Tribune
magazine was launchedin 2001 by IRSN and the
GRS, its German partner.

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IRSN
Supporting informationand training
ommunication and information are part of the Institute's missions. To carry out these missions, a communication department was created in 2002. Its purpose is to position the Institute as an expertise andresearch organisation in the area of prevention and management of nuclear and radiological risks.

C> Communication
based ontransparency andeducation
Information mission
The Institute supports information on the risk andprevention of nuclear and radiological risks. It therefore
supports the development of a culture regarding risk inFrance. IRSN takes part in societal debates dealing withthese issues, while listening to and taking into accountpublic expectations regarding information.

Actions in 2002 targeting specific segmentsof public opinion“Keeping a close watch on nuclear energy” targeting
the general public.
For over 15 years, the travelling exhibition “Keeping a close
watch on nuclear energy” has been presented to the generalpublic and more particularly to schools. The purpose is toinform people on the risks related to nuclear power and on
the measures taken to control these. It is organised by IRSN
and DGSNR, in collaboration with local authorities. In
2002, it was presented in Blois, Bordeaux and Dijon andattracted over 10,000 visitors. Furthermore, the collectionof IRSN booklets was extended in 2002 with a publication
on radioactive waste.

Ministry of Health extended their information actions tolocal representatives.
The participation in the « Salon des maires de France »exhibition was also the opportunity to heighten awarenessof those risks among France's 36,000 mayors , in particularby distributing a letter-statement entitled “Le radon enquestion”.
Annual meetings with health, environment and safety professionals. The presence in professional forums
such as Medec (March 2002) and Pollutec (November
2002) are opportunities for the Institute to discuss withprofessionals and inform them. In the same way, theEUROSAFE forum, the European forum for safety professionals, is an exemplary partnership between IRSN and
GRS. Its implementation is conducted by a programmecommittee comprising 6 European safety and radiation
protection organisations. It is intended to promote
European convergence in terms of safety practices.
For the scientific community, several scientific media
were developed in 2002:– The first scientific and technical report of IRSN, with
3,500 copies distributed in France and abroad;Towards elected officials
With the organisation in January 2002 of a third day of
information on the risks related to radon, IRSN and the
IRSN exhibition at the “Salon des Maires” forum.

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ACTIVITIES– The Internet site dedicated to the scientific publicationsof the Institute;– A new document in the scientific collection: « Collective
dose – Indications and Contraindications ».
The relations with the media are intended to provide
information, either related to current events or to
substantive issues. In 2002, in addition to support for the
programmes and actions of the Institute, this activity
focused on the creation of IRSN, Chernobyl 16 years after.

Internally, supporting the creation of IRSN
In 2002, the internal communication launched a reflection process on the values of the new Institute within
working groups, with the intention being to achieve ashared vision of IRSN values. A survey was conducted on
personnel expectations, based on a representative sampleof the people in the Institute.

[ COMMUNICATION AND TRAINING ]INTERNET: REAL-TIME INFORMATIONThe IRSN Internet site (www.irsn.org) was set up at
the beginning of 2002. At first, it was designed as an
institutional site introducing the new Institute, and it
has gradually integrated the contents of the IPSN and
OPRI sites, enriched with new pages and a more userfriendly new home page .
A new site dedicated to IRSN research and scientificpublications was launched in 2002. It gathers thereferences for articles, conferences and theses,
published by the Institute over the last 3 years, as wellas current or future theses, and information on the
research teams and subjects being treated.
In 2002, the IRSN site recorded 165,700 visits by
44,500 different visitors, including almost 9,000 for
the scientific site alone.

Participating in training through research> Training
aking part in the teaching and training effort
through research is essential to confirm IRSN’s
mission in the area of knowledge development. Thisis also an opportunity to develop openness, both toscientific circles and universities. Over time, thisshould be an efficient means to attract young researchers and postdoctoral students to the Institute, thus
generating recruitment opportunities.

T

Supporting teaching
As regards teaching, in addition to specific contributions
by Institute agents, IRSN actively participates in training
in schools of engineering and universities:– Génie atomique (INSTN, Saclay, Essonne).
– DESS de radioprotection (Joseph-Fourier University,
Grenoble, Isère).
– Nuclear power option at the Ecole nationale supérieured’ingénieurs (ENSI) in Bourges (Cher).
– Nuclear and technologies in association option with the
École des mines de Nantes (Loire-Atlantique).
– DESS Sciences des aérosols, génie de l’aérocontamination (University of Paris-XII, Val-de-Marne).
In some cases, partnership agreements have been signed,
providing research programmes and reception of trainees.
In 2002, agreements were signed with the Joseph-Fourier
University, the ENSI of Bourges (Cher)., the University of
Caen (Basse-Normandie), the University of Paris-XII (Valde-Marne) and the University of La Rochelle (CharenteMaritime).

Every year, the Institute receives doctoral and post-doctoral
students in its laboratories. In 2002, autonomous
management of theses and post-doctoral students was
instituted, following the creation of IRSN. The theses andpost-doctoral training applications are subjected to aprocedure to assess subjects, conducted by two experts
external to the Institute. This procedure is used to checkthe relevancy of the subjects, while promoting discussions
between Institute researchers and external experts,
teachers and university professors.
In 2002, 11 theses were defended and 22 theses werestarted (including 64% co-financed by companies, local
authorities or research bursaries). On December 31st,
2002 13 post-doctoral trainings were in progress,
including several training programmes involving foreign
students (North America, South America, Asia, Eastern
Europe, North Africa).
One of the objectives of training through research is tofacilitate the transition from the academic world to theworkplace, by enhancing the concordance between
theses and professional ambitions. Over the last three
years, 56% of PhD graduates and 80% of post-doctoral
students went on to sign “open ended” contract. In 2002,a branch of the Bernard Grégory association was createdwithin the Institute, supporting researchers’ transition
from academia to the workplace, in particular by introducing them to industry.
Similarly, the organisation of the “Formation par larecherche” days brings together almost 200 people andprovides post-doctoral students with the opportunity
to present the state of progression of their work inorganised conferences.
On the IRSN scientific Internet site launched in 2002,
the thesis section is among the most consulted areas.
The use of the Internet to present completed theses,
those in progress and proposals of subjects is highly
appreciated among applicants.
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Proceeding with quality objectives
he Institute’s partners count on IRSN as an organisation recognized in the area of the nuclear andradioactivity-related risk assessment, and expect him
to prove that its technical and organisational capacities enable it to ensure the quality of its activities.

T

In keeping with this expectation, the SEQUOIA
project was launched in 2000, as a transversal andambitious project for which the first significant
stage is the certification of expertise activities
scheduled for 2004.

used to upgrade the quality system. In this phase, theactions have been conducted to cover all technical activities
of IPSN and OPRI, launched with the creation of IRSN.
The upgrading itself began in 2002. Based on a participative approach, it calls upon thematic groups, each
dedicated to the study of a process and including professionals involved in each process. The co-ordination of thisproject and the thematic groups are supported by an outside service supplier contributing acquired experience on
projects of this sort.

Similarly, the Institute is constantly updating its
accreditations for test and calibration activities.
This guarantees the impartiality and efficiency ofits methods and techniques.

In 2002, work mainly focused on the areas of management, support and expertise. For management, theemphasis was on the general quality of the organisationof the Institute, monitoring of the quality system andimprovement and the control of quality system documents.

SEQUOIA, a federative project

For support, skills development, recruitment, purchases,
sales, European research contracts and documentation(including thesis publications) were studied. Documents
were produced to cover these subjects. Some have alreadybeen applied; others are in process of implementation orvalidation.

The purpose of the project is to achieve better control of
all IRSN activities and their interaction: realisation of“products” (expertise, research, studies, etc.), management and support (purchasing, sales, human resourcesmanagement, documentation, etc.).
After a diagnostic phase which confirmed the opportunity
and the need for a project of this sort, the following
phase defined the specifications of the future Quality
management system, its scope, identification of the mainprocesses, quality organisation and the method to be

The communication and training actions essential forthe success of the Institute’s approach were listed andorganised in a support plan to enable personnel to better
understand the project.

ACCREDITATIONS (ISO 17025 STANDARD)

56

Laboratory of studies and research in external
dosimetry (Cadarache, Bouches-du-Rhône).

Calibration of instruments used in neutron dosimetry.

Laboratory of studies and research in external
dosimetry (Fontenay-aux-Roses, Hauts-de-Seine).

Calibration of instruments used in photon dosimetry.

Measurement laboratory for environmental
radioactivity (Orsay, Essonne).

Analysis of radionuclides present in all sample typesof the environment.

Physics and Metrology Laboratory for aerosols
and containment (Saclay, Essonne).

Physical tests of equipment measuring air
contamination by radioactive gas.

Study laboratory for contamination, purificationand ventilation transfers (Saclay).

Physical tests of ventilated equipment of personnel
protection against radioactive contamination.

Environment and Response Control Department(Le Vésinet, Yvelines).

Analysis of radionuclides present in all sample typesof the environment.

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Page 57[ Q UA L I TY ]QUALITY AND DEVELOPMENT MEANS

A policy in favour of accreditation

Certification in IRSN

In 2002, IRSN defined a clear policy in favour of accreditation of its test and calibration activities, particularly
when:– Results need to comply with regulatory or contractual
requirements;– Results constitute an undeniable reference;– Results are used to conduct expertise activities.

Within the framework of the SEQUOIA project, the purpose of IRSN is to obtain certification for all of its activities. Certification and certification renewal approaches
were conducted by units intervening in specific areas or
to meet originators’ requirements.

Accreditation projects have then been initiated in theareas related to radon, radium measurement in water andbiological dosimetry.

This is the case for the CTHIR (Technical Centre for the
Approval of Radiological Protection Instrumentation)
which obtained certification in 2002 and for the OAR(Radiation protection assistance office) which initiatedthe actions necessary for renewing certification obtainedin 1999.

A new accreditation baseline in 2002
In 2002, laboratories were affected by the baseline change, produced after the publication of the new ISO 17025
standards. Compliance to this new baseline implied significant changes, both at the organisational and technicallevels. This objective was met by all units which obtained
renewal of their accreditation. Today, 6 units have accreditation from the COFRAC (see box).

CERTIFICATION (2000 VERSION OF ISO 9001 STANDARD)
Technical Centre for the Approval of RadiologicalProtection Instrumentation (Saclay).

Assessment of the radiation protection
instrumentation for nuclear and medical industries
and industries using ionising radiation.

Radiation protection assistance office(Fontenay-aux-Roses).

– Acceptance and control of high efficiency filters
and iodine traps of nuclear facilities.
– Acceptance of absorbing samples of the purification
systems for radioactive gaseous effluents.
– Measurement of radon in the environment andbuildings.

Gamma spectrometrylaboratory (left) and benzene
synthesis laboratory (right):
two accredited IRSN activities.

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Page 58

Human resources andlabour relations: supporting
the implementation and thedevelopment of IRSN
ince its creation in February 2002, IRSN has
exercised its responsibilities as an employer,
previously assumed by the CEA and by OPRI. This
structured 2002 activities around three issues:– The administrative acts necessary for the exerciseof the employer responsibility and employees’
personal management;– Representative personnel authorities;– Management procedures and tools.

S

Within this context, it is essential to create an attractive
environment so that employees who participate in
the development of the new Institute find convincing
reasons to pursue their career, including those employees
made available to IRSN by the CEA and employees who
benefit from the status of established civil servants.
At the time of the creation of the IRSN, over half of theemployees contributing to IRSN activities were employedby the CEA (800 persons) and 200 were employed by theformer OPRI or were civil servants. According to theprovisions of the decree dated February 22nd, 2002,
CEA employees made available to IRSN have a three-year
period from the date of implementation of the decreeduring which they may express their desire to pursue
their career in the CEA or choose IRSN status.

Integration of OPRI personnel
Among the actions directly related to the creation of
IRSN, the integration of OPRI personnel required a programme of explanation through information meetingsand personal interviews. The purpose was to propose to
OPRI agents, a public administrative establishment,
contracts under private-sector law corresponding to thestatus of the new Institute. On December 31st, 2002,
out of 197 OPRI employees, 165 had chosen an IRSN
contract.

Representative authorities to ensure
the labour relations dialogue and negotiate
a company-wide agreement
A company-wide agreement is negotiated, according to
the provisions of the decree of February 22nd, 2002, on

58[ IRSN ACTIVITY REPORT 2002 ]the basis of the provisions of the CEA labour convention,
appropriate to the environment, size and activities of theInstitute.
This project mobilises, both General Management, which
considers it as a central aspect of the human resourcesmanagement of the company, and Human Resources
Management, which provides its experience and logisticalsupport to the numerous meetings held on this issue. This
work was particularly useful to propose and negotiate
developments in the structure and general economic
conditions for wage increases and advancement timetables of non-management employees.
The end of the year was dedicated to the preparation of
the election of personnel representatives for the various
legal and conventional authorities which will be directly
concerned by the quality of the dialogue and discussions
between employees and management.
To offer career opportunities to employees beyond IRSN
activities, conditions of mobility between the CEA and
IRSN were discussed and resulted in a draft convention
between both organisations, transmitted to the concerned ministries and to the Ministry of Budget, as provided
for in the decree of February 22nd, 2002. The convention
is intended to encourage exchanges of skills to mutuallyenrich the organisations and offer career opportunities
for employees from both bodies. The same type of agreement will be developed with other organisations specialising in areas related to IRSN activities. On December 31st,
2002, 43 IRSN employees were made available to otherorganisations, including the DGSNR.

Development and control of management
procedures and tools
In terms of compensation policies, the payroll package
adopted by the Institute was structured to take into
account the diversity of personnel statuses and it has
been operational since the end of February 2002.
Over 17 different status categories are managed by thedepartment responsible for this activity.
This structure and its management have been and remain
a demanding activity with significant dedicated resources. In Human Resources management, all employees andIRSN/RA2002/72 p./UK

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Every year, IRSN receives doctoraland post-doctoral students. Almost 50%
of post-doctoratal graduates were hiredby IRSN lasting recent years.

managers are constantly dedicated to meeting the justified expectations of every employee to receive wage slips
within deadline.
The IT system was also improved so that fees for missions
carried out are paid as soon as possible and in compliancewith the current regulatory provisions.

Permanence and quality of personnel
administration activities and the exerciseof employer’s responsibilities
In addition to the projects linked to the implementationof the new Institute, Human Resources management
carried out its basic missions so that laboratories andsupport units continue to have the means required toachieve their operational objectives. It therefore contributed by recruiting 150 people, by establishing andmanaging 266 files of temporary employees hired tosupport the various teams, by conducting induction
operations such as the reception and training of new
recruits. Management of professional travel was ensured
for France and abroad (more than 8,700 missions treated
and finalised in 2002).
In the training area, the activity represented a budget of€1.4 million in 2002, i.e. 6,000 training hours in threeareas: scientific and technical topics (70%), languages
and office process modernisation.

KEY FIGURES AND DATES(ON DECEMBER 31st, 2002)

1,437 workstations.
66% of employees with management status:
engineers and management personnel.
34% of employees have non-management status:
technicians, administrative and logistics
support personnel.
42% of employees work directly for IRSN
(602 persons).
58% of professionals are made available
to IRSN by the CEA (835 persons).
700 IRSN pay slips are produced every month.
6,000 training hours were dispensed in 2002.
8,700 missions were completed.
120 trainee files were processed.
Personnel representatives and trade union
representatives in the Works Committee were
elected on January 23rd, 2003 (first round)and on February 6th, 2003 (runoff).

In 2002, IRSN received 120 trainees, including 70% intheir fifth year of university studies or completing anengineering school. Besides, about twenty foreign contributors were received for a stay of six months on average.
These trainees come mainly from the Institute's partnerorganisations and follow training within the frameworkof IRSN international agreements.
Among the employer’s duties, the relations with all labour
organisations and administrations intervening in theregulation and control of EPICs (Public establishments ofan industrial and commercial nature) have been defined.
The production of legal and regulatory information has
been implemented and is now subject to presentations ona regular basis.
Meetings related to IRSN organisation held throughout the year 2002.

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Page 60IRSN 2002 budget

IRSN was created in 2002 as an EPIC (Établissement
Publique à Caractère Industriel et Commercial), a specificFrench status for public institutions with industrial
and commercial activities, supervised by a designatedaccountant. This resulted in changes in the Institute’s tax
obligations and necessitated the implementation of neworganizational, management and accounting tools tocomply with this new status.
This change in status immediately impacted two areas of
the financial reporting system:– Forecasting was established on the basis of a 12-month
period, but operations were carried out over a 10-month
period;– Documents were presented in the M9-5 standard
accounting format.
The Institute’s total revenues totalled €214.5 million,
with 83% being provided by the French Ministry for theEnvironment and Sustainable Development. The remainder,
i.e. 17%, was generated by services provided to third
parties or through mutually-financed programmes, inparticular with EDF and COGEMA.
Expenses for operating costs amounted to €200.4 million,
with only €25,120,486.08 in personnel costs. This low
level is due to the fact that the majority of employees
formerly with the IPSN are still employed by the CEA,
which invoices their cost to the Institute.
The transfer of OPRI and IPSN assets has not yet been
fully completed and therefore these accounting entries
are not included in the IRSN balance sheet. Similarly,
no depreciation write-offs have been entered into the2002 annual accounts.
The balance between revenues and expenses amounts to€14.1 million in underlying earnings, providing nearlycomplete organic coverage of investments, which standat €14.7 million for the fiscal year.
In operational terms, the overall balance in working
capital was reduced by €0.7 million.

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Page 61[ IRSN BUDGET ]QUALITY AND DEVELOPMENT MEANS

1 – RECONCILIATION SUMMARY OF ESTIMATES AND REALISATION
A – Profit & Loss account (in millions of euros)
Costs
Profit & Loss account
Personnel costs

Revenues

E

R

E

R

106.0

25.1

38.5

34.6

Sales: Provision of services

241.8

178.5

Public subsidies

Other operating costs

154.7

175.3

0.1

1.4

Total costs

260.7

200.4

280.4

214.5

Earnings (Profit)

19.8

14.1

—

—

280.4

214.5

280.4

214.5

Total balance on Profit & Loss account

Other operating revenues
Total revenues
Negative earnings (Loss)
Total balance on Profit & Loss accountE = Estimates 12 months – R = Realisation 10 months.

B – Cash flow (in millions of euros)
Capacity

Deficit

E

R

E

R

Earnings (Profit)

19.8

14.0

Negative earnings (Loss)+ Book value of assets sold+ Appropriations to amortisation+ and provisions

0.0

0.0

– Revenues from assets sold– Revenues from amortization– compensation– Share of subsidies transferred– to earnings– Adjustments to amortisation and provisions

Subtotal

19.8

14.0

Subtotal

Cash Inflow

19.8

14.0

Cash Outflow

E = Estimates 12 months – R = Realisation 10 months.

C – Reconciliation of cash flow to movement in net funds (in millions of euros)
Costs

Revenues

E

R

Cash Inflow
Acquisitions of tangible
and intangible assets

19.8

E

R

19.8

14

14.7

Public investment subsidies

Long-term investments
Total employees

Other resources(excluding internal transactions)
19.8

14.7

19.8

Contribution of working capital
Total balance of table

Cash Outflow

19.8

14.7

19.8

14

Total resources

0.7

Deduction from working capital

14.8

Total balance of table

E = Estimates 12 months – R = Realisation 10 months.

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Page 62QUALITY AND DEVELOPMENT MEANS

2 – PROFIT & LOSS ACCOUNT
A – Income (in millions of euros)
Earnings (before taxes)
Operating earnings

Financial Year 2002 (10 months)
213.5

Sales of merchandise
Production sales• Work• Provision of services, studies & activities

34.7

Net turnover

34.7

Closing stock• Production in progress• Services in progress• Revenues
Capitalized production
Operating subsidies

178.6

Adjustments to amortisation and provisions
Transfers of liabilities

0.1

Other revenues

0.1

Investment earnings

1

From holdings
Other securities of fixed asset receivables
Other interest and similar earnings
Adjustments to provisions and transfers of financial liabilities
Positive exchange rate differences
Net income on transfers of investment securities

1

Exceptional earnings

0

On management transactions
On capital transactions• Earnings from asset transfers• Investment subsidies transferred to the year’s Profit & Loss Account• Others
Amortisation compensation
Adjustments to provisions and transfers of non-recurrent liabilities
Total earnings

214.7

Debit balance = Loss
OVERALL TOTAL

62[ IRSN ACTIVITY REPORT 2002 ]214.5

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Page 63[ IRSN BUDGET ]B – Liabilities (in millions of euros)
Liabilities (excluding taxes)
Operating liabilities

Financial year 2002 (10 months)
200.5

Purchase costs of merchandise sold during the year
• Merchandise purchases• Fluctuation in merchandise stocks
Costs related to third parties• Purchases of supplies in hand
– Raw materials– Work– Others (studies, services)• Fluctuation in stock of supplies• Subcontracting costs• Purchases of equipment & supplies not in stock• External services

29.1
19
123.8

Taxes and similar payments– Remuneration costs– Others

0.6
2.9

Personnel costs– Wages & salaries– Social security charges

17.7
7.4

Appropriations to amortisation and provisions– On fixed capital: appropriations to amortisation– On fixed capital: appropriations to provisions– On current assets: appropriations to provisions– For contingent liabilities: appropriations to provisions
Other liabilities
Investment liabilities

0

Appropriations to amortisation and provisions
Interest and similar liabilities
Negative exchange rate differences
Net liabilities on transfers of investment securities
Non-recurrent liabilities

0

On management transactions
On capital transactions• Accounting value of transferred fixed and funded items• OtherAppropriations to amortisation and provisions• Appropriations to regulated provisions• Appropriations to amortisation and other provisions
Total liabilities
Credit balance = Profit
OVERALL TOTAL

200.5
14
214.5

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Page 64QUALITY AND DEVELOPMENT MEANS

3 – BALANCE SHEETA – Assets (in millions of euros)
ASSETS

Financial Year 2002 (10 months)
Gross

Fixed assets
Intangible assets
Initial costs
R&D costs
Concessions, patents, licences, brands, processes,
software and similar duties and costs
Goodwill
OthersIntangible assets in progress
Advances and deposits
Tangible assets
Land
Buildings & structures
Technical installations, equipment and plant
OthersTangible assets in progress
Advances and deposits

Amortisationand provisions (to deduct)

Net

1.3

1.3

0.1

0.1

0.8
4.8
3.1
4.6

0.8
4.8
3.1
4.6

Investment assets
Holdings
Receivables related to holdings
Other fixed securities
Loans
OthersTotal (I)

14.7

0

14.7

Current assets
Stock and work-in-progress
Raw materials and other supplies
Production in progress (goods & services)Work in progress
Semi-finished & finished products
Merchandise
Advances & deposits on orderss

27.6

Operating receivables
Client receivables & connected accounts
Others35.7
54.9

Miscellaneous receivables
Investment securities
SharesOther securitie
Liquid assets

27.6
0.1

35.6
54.9

47.1

47.1

0.3

0.3

Deferred charges
Prepayments
Total (II)

165.6

0.1

165.5

180.3

0.1

180.2

Charges to be allocated over several financial years (III)Loan redemption premiums (IV)
Assets translation variance (V)OVERALL TOTAL

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Page 65[ IRSN BUDGET ]B – Liabilities (in millions of euros)
LIABILITIESFinancial Year 2002 (10 months)

Shareholder Equity Funds
Allowances
Addition to allowances. State
Addition to allowances (bodies other than the State)
EquityOther additions to allowances. State
Other additions to allowances. Other bodies
Capital donations
Variance in revaluation
Reserves
Regulated reserves
OthersCarried forward
Financial year earnings (Profit or loss)

14.1

Subtotal: Net equity

14.1

Investment subsidies
Regulated provisions
Total I

14.1

Contingent liability provisions
Provision for risks
Provision for liabilities
Total II

Debts
Financial debts
Debenture loans
Loans & debts from credit institutions
Miscellaneous financial loans & debts
Advances and deposits received on current orders
Operating debts
Supplier debts and connected accounts
Fiscal & social security debts
Other
Miscellaneous debts
Debts on fixed capital and connected accounts

0

– 0.2
2.4
84.3
54.8

6.8

Other debts
Miscellaneous accruals
Deferred earnings

17.9

Total III

166.1

0.1

Liabilities translation variance (IV)OVERALL TOTAL (I+II+III+IV)

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Page 66

IRSN sites
1

Agen
B.P. 27
47002 Agen Cedex
Tel.: +33 (0) 5 53 48 01 60

239, rue Joachim-du-Bellay
49000 Angers
Tel.: +33 (0) 2 41 87 83 21

49

3 Avignon

550, rue de la Tramontane,
BP 70295 Les Angles
30402 Villeuneuve-lès-Avignon Cedex
Tel.: +33 (0) 4 90 26 11 00

8
13
2

7

6

10

11

12

5

1
3

14

66

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Page 67[ SITES ]ANNEXES

4

Beaumont-Hague

10

Bois des Rames Bâtiment 501
91400 Orsay
Tel.: +33 (0) 1 69 85 58 40

Rue du vieux chemin
B.P. 224
50442 Beaumont-Hague Cedex
Tel.: +33 (0) 2 33 01 05 61
11
5

Cadarache
B.P. 313115 Saint-Paul-lez-Durance Cedex
Tel.: +33 (0) 4 42 25 70 00

612

Fontenay-aux-roses
B.P.1792262 Fontenay-aux-Roses Cedex
Tel.: +33 (0) 1 58 35 88 88

8

Le Vésinet

Pierrelatte
B.P. 166
26702 Pierrelatte Cedex
Tel.: +33 (0) 4 75 50 40 00

77-83, avenue du Général-de-Gaulle
92140 Clamart

7

PapeeteB.P. 519 Tahiti Papeete
Polynésie Française
Tel. : 00 689 481 707

ClamartMail: B.P. 17
92262 Fontenay-aux-Roses Cedex
Tel.: +33 (0) 1 58 35 88 88

Orsay

13

SaclayB.P. 6891192 Gif-sur-Yvette Cedex
Tel.: +33 (0) 1 69 08 60 00

14

ToulonToulon Zone Portuaire de Brégaillon
B.P. 330
83507 La Seyne-sur-Mer Cedex
Tel.: +33 (0) 4 94 30 48 29

31, rue de l’Écluse - B.P. 35
78116 Le Vesinet
Tel.: +33 (0) 1 30 15 52 00
9

Octeville
B.P. 10
Rue Max-Pol-Fouchet
50130 Cherbourg-OctevilleTel.: +33 (0) 2 33 01 41 00[ IRSN ACTIVITY REPORT 2002 ]67

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Page 68

GlossaryAA

ADEME: Agency for the Environment and Energy Control(France).

CARMELA: IRSN research programme on fires in nuclear
facilities aimed at gaining further insight into electricalcabinet fires.

Aerosol: Dispersion, in very fine particles (about one
micron), of a liquid or solid in a gas (air or oxygen).
AFNOR: French standardisation institute.
AFSSE: French Agency for Environmental Safety.
Alpha (α symbol): Radiation composed of helium 4
nuclei, highly ionising but not very penetrating. A sheetof paper is sufficient to stop alpha radiation.
AMANDE: Accelerator for metrology and neutron
applications for external dosimetry.
ANDRA: National Agency for Radioactive Waste
Management (France).
ASTEC: Accident Source Term Evaluation Code, systemsof software developed in collaboration by IRSN and the
GRS to assess the physical phenomena intervening
during an accident of core meltdown of a pressurizedwater reactor.
AVN: Association Vinçotte Nucléaire (Belgium).

B
BARC: Bhabha Atomic Research Centre (India).
Becquerel (Bq): Official international unit for radioactivity measurement. The Becquerel (Bq) is equal to one
disintegration per second.

CATHARE: Advanced thermal-hydraulic code applied topressurized water reactors.
CEA: Atomic Energy Commission (France).
Cesium (Cs, atomic number 55): Noble, toxic metal whosecharacteristics are comparable to those of potassium.
CHU: French university hospital.
Primary cooling system: Reactor coolant system operating in a closed loop, comprising a series of componentsthat ensures the circulation of water used to extract theheat given off by the reactor core.
CIREA: Interministerial commission for artificial radioelements
CLI: Local information commission.
CNRS: French National Centre for Scientific Research(France).
COFRAC: French accreditation committee.
COGÉMA: Nuclear matter company (France).
COLOSS: European project devoted to the study of coredegradation in the event of a severe accident.

Beta (β symbol): Radiation composed of electronsof negative or positive charge. A few millimetre air screen
or a simple sheet of aluminium can stop this type ofradiation.

Containment building or reactor building: Leak-tightconcrete building housing the reactor pressure vessel,
the primary system, the steam generators and the main
auxiliaries ensuring reactor safety.

BIPM: International bureau of weights and measures.

Core: Area of the nuclear reactor where nuclear reactions
occur.

BLEVE: Boiling Liquid Expanding Vapour Explosion.
BNEN: Standardization bureau for nuclear equipment.
BNI: Basic Nuclear Installation.
BNM: National metrology bureau (France).
BORIS: Bioavailability of Radionuclides in Soils.
Burn up fraction: Thermal energy produced by the
nuclear fissions in a fuel mass unit. It is measured inmegawatt days per ton (MWj/t).

C
CABRI: Test reactor for fuel safety used by the IRSN.

68

CAROL: CAmargue-RhÔne-Languedoc, project forstudying the distribution of artificial radionuclides inthe Lower-Rhône region.

[ IRSN ACTIVITY REPORT 2002 ]CRISTAL: New French criticality-safety package developed
as part of a joint project between IRSN, CEA and COGEMA.
It aims at assessing the criticality risk in all nuclear facilities
and transport packages where fissile materials are used.
Criticality: Risk of uncontrolled fission phenomena infissile materials.
Criticality accident: Uncontrolled chain fission reaction
triggered in an environment containing fissile materials
such as uranium 235 or plutonium 239.
CSN: Consejo de Seguridad Nuclear (Spain).
CTC: IRSN emergency response centre.
CTHIR: Technical Centre for the Approval of RadiologicalProtection Instrumentation.

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Page 69[ GLOSSARY ]ANNEXESDA

DGA: General delegation for armaments.
DGAC: General Directorate of Civil Aviation.
DGEMP: General directorate for energy and raw materials.
DGS: Directorate General for Health.
DGSNR: General Directorate for Nuclear Safety andRadiation Protection.
DIAPLU: Study project on the PLUtonium behaviour in
the DIAgenesis of marine sediments.
DISPRO: Study project on near-field dispersion.
DIVA: Devices for the study of fires, ventilation and airborne
contamination.
Dosimetry: Detection, by assessment or measurement, ofthe dose of radiation absorbed by a substance or person.
DRIRE: Regional Agency for Industry, Research and theEnvironment.
DSND: Delegate for nuclear safety and radiation protection for activities and installations concerned by national
defence provisions.
DSV: Department of life sciences.

Framatome: Manufacturer of nuclear steam supply
systems.

E

Fuel assembly: Cluster of fuel rods, connected with ametallic structure, used in nuclear reactors.

G
Gamma (γ symbol): Highly penetrating but not very
ionising electromagnetic radiation, emitted during thedisintegration of radioactive elements. This type ofradiation is stopped by concrete or lead screens.
GEA: Atomic study group.
GRNC: Nord-Cotentin radioecology group.
GRS: Gesellschaft für Anlagen und Reaktorsicherheit(Germany).
GSIEN: Group of scientists for information on nuclear
energy (France).

H
HAT: Human Alimentary Tract Model.

EBRD: European Bank for Reconstruction and Development.
EDF: French national electricity utility company.
ENTHALPY: European corium thermodynamic database.
ENVIRHOM: IRSN health and environment research
programme to study the effects of chronic exposure to
low-dose radionuclides.
ÉPIC: Public establishment of an industrial and commercial
nature.
EURADOS: EUropean RAdiation DOSimetry group.
EURATOM: European Atomic Energy Community.
EURODIF: European uranium enrichment by gaseous
diffusion plant.
EVIDOS: Evaluation of Individual Dosimetry in Mixed
Neutron-Proton Fields: research programme funded by
the European Community.
EVITA: European Validation of the Integral Code ASTEC.

HFD: High Civil Servant for Defence.

F

IFA: French-German initiative for Chernobyl.

FASSET: Framework for ASSessment of Environmental
impacT.
FLAMMES: Software describing the evolution of carbonated product fires developed by IRSN.
FLIP: Liquid fuel fire interacting with a wall.

HSE: Health and Safety Executive (United Kingdom).

I
IAEA: International Atomic Energy Agency.
IARC: International Agency for Research on Cancer.
IBRAE: Nuclear safety institute of the Russian Academyof Sciences.
ICARE: Interpretation of damaged cores for water-cooled
reactors: software simulating the degradation of a PWR
core during a severe accident.
ICHEM: European Iodine Chemistry Project.
ICPE: Listed environmental protection facility.
ICRP: International Commission on Radiological Protection.
IFREMER: French research institute for exploitation of
the sea.
IGR: Gustave Roussy Institute (France).
IGS: Institute of Geological Sciences.
ILL: Laue-Langevin Institute (France).
INBS: Secret basic nuclear installation.
[ IRSN ACTIVITY REPORT 2002 ]69

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Page 70

ANNEXESINDOS: International Dosimetry.
INERIS: National institute for the industrial environmentand hazards (France).
INSERM: National health and medical research institute(France).
INSTN: National institute for nuclear science and technology.
INSU: National institute for sciences of the universe.
InVs: French health watch institute.
IPSN: Institute for protection and nuclear safety (France).
IRSN: Nuclear safety and radioprotection institute(France).
ISO: International Standards Organisation.
ISO 9001: European standard for quality management
systems.
Isotope: Elements whose atoms have the same numberof electrons and protons, but a different number ofneutrons. They have the same name and the samechemical properties. Around 325 natural isotopes and1,200 artificially created isotopes are currently listed.

A
J
JAERI: Japan Atomic Energy Research Institute.
JNC: Japan Nuclear Cycle Institute.

A
L
LOCA: Loss Of Coolant Accident.
LTCRA: Cellular therapy and accidental radiation protection
laboratory.

A
M
MCCI: Molten-core Concrete Interaction.
MEDEC: French trade fair for professionals in the healthsector.
MINEFI: Ministry of the Economy, Finance and Industry(France).
MOX: Fuels of mixed uranium and plutonium oxides.
MWe: MegaWatt electric.

A
N
NEA: OECD Nuclear Energy Agency.

70[ IRSN ACTIVITY REPORT 2002 ]Nuclear fuel: Fissile material (able to undergo a fission
reaction) used in a reactor to develop a nuclear chain
reaction. After being used in a nuclear reactor, this isreferred to as irradiated fuel.
Nuclear materials: Materials which can be used to
manufacture an explosive nuclear device. They aredefined from their fissile (for a fission device), fusible (fora thermonuclear bomb), or fertile (capacity to produce
fissile or fusible materials) characteristics. French legislation retains six nuclear materials: plutonium, uranium,
thorium, tritium, deuterium and lithium 6 (deuterium andlithium 6 are not radioactive).
Nuclear safety: Set of measures taken at all levels ofdesign, manufacturing, operation and decommissioningof nuclear facilities to prevent accident and to limit theireffects.

O
OAR: Radiation protection assistance office.
OECD: Organisation for Economic Co-operation andDevelopment.
OPCW: Organisation for the Prohibition of Chemical
Weapons.
OPERA: Permanent environmental radioactivity observatory.
OPRI: Office for Protection against Ionising Radiation(France).

P
PCRD: Research and development framework programme(European Community).
PHARE: European co-operation programme with thecountries of Central Europe.
Phébus: Experimental reactor.
Phébus FP: Research programme devoted to the study offission product (FP) behaviour.
Phénix: 250 MWe fast neutron reactor.
PIC: Common interested programme.
Plutonium: (Pu, atomic number 94). Transuranic chemicalelement. The isotope 239 has a half life of 24,110 years.
POLLUTEC: International trade fair for environmentrelated equipment, technologies and services for industry.
PSA: Probabilistic Safety Analyses.
PWR: Pressurized Water Reactor.

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Page 71[ GLOSSARY ]R

T

Radiation protection: Set of measures intended toensure the sanitary protection of people and workers
against negative effects of ionising radiation.

TACIS: Technical Assistance for Commonwealth of
Independent States.

Radioactivity: Property of certain chemical elements whose
nuclei spontaneously disintegrate into other elements
emitting ionising radiation.
Radioelement: Natural or artificial radioactive element.
Radionuclide: Radioactive isotope of an element.
RAFT: Reactivity Accident Fuel Test, IRSN research programme developed in collaboration with EDF and JNC(Japan) concerning the safety of the fast neutron reactors.
REMORA: Study project on the Radionuclide REMObilisationin the Rhône prodelta.
REMOTRANS: REMObilisation, long distance TRANSport
and Bioavailability of Radionuclides in Marine sediments.

A
S

Technicatome: Engineering company specialising insafety and reliability systems in severe environments.
TRANSAT: Study project on water ATmosphere TRANSfert.

AU
UIAR: Ukrainian Institute of Agricultural Radiology.
Unit: Power production unit including a boiler and aturbo-generator set. A nuclear unit is mainly defined by
its type of reactor and the power of its turbo-generator.
UNSCEAR: United Nations Scientific Committee on the
Effect of Atomic Radiation.
U02: Uranium dioxide.

SARA: Automated monitoring of aerosol radioactivity.
SARNET: Severe Accident Research Network.
SCANAIR: Computer system for the analysis of IRSN
injection reactivity accidents.
SEQUOIA: Progressive quality system, IRSN’s goal for the
future.
SÉSAME: Accident situation progression plan and assessment methods. This is a computer system developed by
IRSN to assess the releases produced by a pressurizedwater reactor in case of accident.
SIEVERT: Information and assessment system of the
exposure to cosmic radiation during flights.
SILÈNE: An IRSN experimental reactor used for criticality
experiments.
SIMEVENT: Ventilation simulation software developed aspart of a joint project between IRSN, SGN and COGEMA.
SIP: Shelter Implementation Plan.
SISERI: Ionising radiation exposure monitoring information
system.
SKI: Statens Kärnkraftinspektion (Sweden).
SSTC: State Scientific and Technical Centre (Ukraine).
STARMANIA: Station for the study of airborne contamination transfer and mechanical strength under incident
and accident conditions.
SYMBIOSE: SYstemic Approach for Modelling the Fate ofChemicals in BIOSphere and Ecosystems.
[ IRSN ACTIVITY REPORT 2002 ]71

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Page 72IRSN Coordination
Communication Department
Publishing
La Clé des mots
Graphics design and coordination
Aristophane agency
Production assistance
LAO Conseil
Printing
NéotypoPhoto credits
Contents left page: © IRSN (top), © EDF (bottom).
Contents right page: © IRSN (top), © BERD (middle),© Thomas Gogny (bottom).
Pages 5 ,7 and 8 : © Vincent Leloup.
Pages 10, 12, 13, 15, 16, 17 : © IRSN.
Page 18 : © Thomas Gogny.
Page 19 : © Thomas Gogny (left), © Pascal Gennerat (right).
Pages 22, 23 : © IRSN.

72[ IRSN ACTIVITY REPORT 2002 ]Page 25 : © Thomas Gogny (top), © CEA Valduc (bottom).
Page 26 : © IRSN.
Page 27 : © Thomas Gogny.
Pages 28, 29 : © EDF.
Page 31 : © IRSN.
Page 32 : © Claude Cieutat.
Page 33 : © Claude Cieutat (top), © EDF (bottom).
Page 34, 36 : © IRSN.
Page 37 : © COGEMA/ © Jean-Marie Taillat (left), © IRSN (right).
Pages 38, 39 : © IRSN.
Page 41 : © CEA Valduc.
Page 43 : © COGEMA / © Jezequel.
Pages 44, 45, 46, 47 : © IRSN.
Page 48 : © IRSN (left), © COGEMA / © Jean-Marie Taillat (right).
Page 49 : © IRSN (left), © COGEMA / © Jean-Marie Taillat (right).
Page 50 : © BERD.
Page 52, 53 (left), 54 : © Thomas Gogny.
Page 57 : © IRSN.
Page 59 : © Thomas Gogny (top), © IRSN (bottom).
Page 67 : © IRSN (left), © Thomas Gogny (middle, right)© IRSN Communication
ISSN : 1637-6730
Registration: October 2003

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IRSN
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Web site: www.irsn.org

Institut de radioprotection
et de sûreté nucléaire