Annual Repor t

2005

IRSN missions
RESEARCH AND PUBLIC SERVICE MISSIONSDefining and implementing national andinternational research programmes
Contributing to training inradiological protection
Permanent monitoring in the fieldof radiological protection
Contributing to public informationand transparency

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTechnical support with regard to nuclear
and radiological risk
Operational support in the event of a crisis
or radiological emergency

CONTRACTUAL SERVICES IN EXPERTISE,RESEARCH AND MEASUREMENTS
Carrying out expert assessments, research
and work for public or private bodies

2005

IRSN Activities

Management and Support

Current events, strategy and organisation

Annual Repor t

2]

I R S N 2005 ANNUAL REPORT[1]CURRENT EVENTS,
STRATEGY AND
ORGANISATIONI R S N 2005 ANNUAL REPORT[3

IRSN Activities

Management and Support

Current events, strategy and organisation

As a nuclear risk expert reportingto public authorities and a key
player in promoting transparency,

the IRSN is preparing
for the future
On a financial scale, the IRSN managed to
pay off the mortgage burden carried since its
creation. Indeed, the change to the Institute’s tax
status with respect to VAT (all other things being
equal) resulted in a return to a break-even situation.
Efforts to control and increase revenue at all levelsin the Institute helped to consolidate this position.
Finally, a solution was drafted in conjunction
with supervisory ministries to finance the IRSN’s
decommissioning costs and specific strategic
facilities.
On an operational scale, most targetedJean-François LACRONIQUE,
Chairman of the Board of Directors

L

ike 2004, 2005 was an eventful year.This
report describes events by presenting
the main focal points of the Institute’s
missions, activities and results.

Firstly, on the human scale, 2005 saw the endof the transition period with the CEA and all the
Institute’s employees coming under the IRSN
umbrella. The success of this operation was key toensuring the long-term nature of our expert
assessment and research potential. However, theresulting stability of our situation does not meanthat the Institute is no longer looking outward, as
the mobility of 170 individuals underlines. This
inbound and outbound mobility mainly concerns
the nuclear sector (CEA, operators, engineering) andthe scientific community (universities, engineeringschools) and has also allowed the IRSN to consolidate the presence of its managers on assignments
in international institutions (IAEA, EU) and to bolster
the number of doctorate and post-doctorate students.

4]

I R S N 2005 ANNUAL REPORT

objectives were met.
The number of expert assessments delivered insupport of government authority operations reachedrecord levels in all areas (operator projects, regulatorychanges, international operations, emergency drills,“nuclear material” expert assessments, etc.). By
concluding agreements and protocols with theseauthorities, it was possible to regulate the activity
by setting priorities and lead-times, thus enabling
key requirements to be met despite a downturn inavailable resources. An example of this is theexpert assessment carried out on ANDRA’s “Dossier
2005 Argile”, which mobilised several teams andwas promptly delivered when required, thenpublished on the Internet in January 2006.
The public interest missions carried out by the IRSN
in compliance with its implementing order werecarried out with determination and key progress
was achieved in many of them: rollout of the
SISERI system for radiological monitoring of theworkforce, advancements in radiological protection

The number of expert
assessments delivered insupport of government
authority operations reachedrecord levels in all areas“”

Significant progress was also made in
research: the results obtained in the treatment
of severe radiation “burns” saved the life of patientfrom Chile, who was able to benefit from the world’s
first stem cell therapy carried out by the Armed
Forces Healthcare Department in conjunction
with IRSN specialists. A contrario, the door toinnovating research into low doses was opened
following a demonstration of the relevance of
research into the effects of chronic contamination(Envirhom project), backed by documentary proof.
In terms of security, new programmes weredeveloped in the field of fire propagation (PRISME),
and fuel behaviour in an accident scenario (SOURCE
TERM). These programmes are jointly financed bya host of partners both in France (EDF mainly) andabroad. The know-how of the Institute’s teams,
the originality and quality of the experimental
resources, whether at the IRSN or related CEA
resources, thus continue to bask in internationalrecognition.

Naturally, project commitments must be
pursued. The objectives agreement signed on
5 July 2006 is confirmation of the policies
adopted over the last three years. A mediumand long-term plan will be drawn up to coordinate
the implementation of this agreement and make
IRSN research more accessible.
These policies coincide with the law on transparency and nuclear safety recently adopted by

Jacques REPUSSARD,
Director Generalparliament: the Institute intends to offer its
specialist skills and reliability to the new Nuclear
Safety Authority and to public authorities in general.
It also plans to effectively handle the missions
requested of it by these bodies and particularly
the mission regarding research into risks fromionising radiation and nuclear technology. By
meeting the expectations of society players andsignificantly promoting transparency, it intends tocontribute to the practical application of the law.
Finally, it is planning to play a key role in the European
and international processes of growing strategic
importance.

Jean-François LACRONIQUE,
Chairman of the Boardof Directors

Jacques REPUSSARD,
Director General

I R S N 2005 ANNUAL REPORT[5IRSN Activities

Management and Support
training, a twofold increase in the number ofconnections on the Institute’s general public websites over 12 months (over a million connections ayear), contributions to public debates on nuclear
issues, support provided to the Local Information
Commissions (CLI) and their national umbrellaassociation (ANCLI). The Institute also started
groundwork with a view to modernising its radiological monitoring systems across France and to
upgrading its response procedures and resourcesin a nuclear or radiological emergency situation.

The IRSN is a lynchpin in the
global challenge for nuclear safety
This mobilised experts from the Institute’s Division
for nuclear defence expertise to check that civilian
operators were correctly enforcing the defence
code and to ensure France’s compliance with its
nuclear non-proliferation commitments. This is apriority safety mission which was carried out at
the request of national authorities.
Similarly, this division played a key role in thesignificant work carried out on overhauling regulations in progress since 2002 to enhance safety
and provide a more effective documentary resource
able to meet the needs of our society in terms ofrisks from malicious intent and terrorism.

Michel BRIÈRE,Deputy Director General, in chargeof defence-related missions.

N

6]

Some of our experts took part in drafting or revising
IAEA safety documents, others went on support
missions abroad as part of safety programmes under
the auspices of the IAEA or the G8. And others arecoordinating networks, primarily on a Europewide scale, to develop technical capacity with respect
to research, measurement and protection of nuclear
material.

uclear safety brings a host of bodies
and authorities into play. Nationwide
nuclear safety is enhanced by the multidisciplinary and consistent expertisefederated by the IRSN to serve the public sector.

This evolving capacity to provide expert assessmentsin the field of safety is underpinned at present bystudies on the metrology of nuclear material andthe modelling of severe hazards such as the use of
explosives or weapons in particular.

In terms of defence-related nuclear safety on
facilities, 2005 was an eventful year in which key
projects were performed such as the basin 8 projectat the port of Brest, the test reactor in Cadarache
and the boiler room of the future Barracuda-type
nuclear attack submarine.
2005 also saw the re-emergence of safety commissions with respect to laboratories and plants, former
test sites, waste and transport, and significant preparation work for emergency situations (four major
drills).
But 2005 was also marked by greater contributions to efforts to ensure that nuclear or radioactive materials and their related facilities andtransport benefit from extensive protection against
the risk of theft, hijack and sabotage.

The IRSN is a lynchpin in the global challenge fornuclear safety.

I R S N 2005 ANNUAL REPORT

Michel BRIÈRE,Deputy Director General,in charge of defence-related missions

CREATION
The IRSN was created by article 5 of law
no. 2001 – 398 of 9 May 2001, and by
the implementing order of 22 February 2002.

STATUS
The IRSN is a public establishment of an industrial
and commercial nature placed under the joint
authority of the Ministries of the Environment,
Health, Industry, Research and Defence.

EXECUTIVES
Jean-François LACRONIQUE, Chairmanof the Board of Directors
Jacques REPUSSARD, Director General
Michel BRIÈRE, Deputy Director General,in charge of IRSN defence-related missions

2005 BUDGET• Revenues: €287 million• Expenditure: €268 million, including €26 million
in investment

STAFF
The IRSN employs about 1,600 employees
including many specialists, engineers,
researchers, physicians, agronomists, veterinary
surgeons and technicians, skilled experts innuclear safety and radiological protection and in
the field of controlling sensitive nuclear materials.

SITES
Clamart (head office)Agen, Cadarache, Cherbourg-Octeville,
Fontenay-aux-Roses, La Seyne-sur-Mer,
Les Angles-Avignon, Le Vésinet, Mahina (Tahiti),
Orsay, Pierrelatte, Saclay, Tournemire.

Philippe JAMET, Deputy Director Generalin charge of general affairs

EXPERTISE AND RESEARCH
The IRSN is the expert in researchand specialised assessments into nuclear andradiological risk serving public authorities.

SCOPE OF ACTIVITY• Environment and response• Human radiological protection• Prevention of major accidents• Reactor safety• Safety of plants, laboratories,
transport and waste• Nuclear defence expertise

FOUR LINES OF DEVELOPMENT• Re-engineering of its research strategy
with its main partners• Optimising missions in support of public authorities• Making its expertise accessible to meetsociety’s expectations• Developing the European and worldwid dimension

I R S N 2005 ANNUAL REPORT[7IRSN Activities

Management and Support

About the IRSN

The IRSN in 2005
Report and prospectsThroughout 2005, the IRSN put the strategic policies set out in 2003 by the Director Generaland approved by the Board of Directors into practice.This allowed the Institute to finish laying
the foundations for its quality-based management system and to continue adapting its
research facilities as part of the debate on the heavyweight equipment to be maintained andused for research into nuclear safety at international level.The IRSN also finished drafting the objectives
agreement signed with the government for the period 2006-2009. This instrument defines the key
scientific and technical objectives of the Institute, the most important of which are planned over the
medium- and long-term.

IRSN’S MAIN LINES OF DEVELOPMENT IN 2005
1. RE-ENGINEERING ITS RESEARCH STRATEGY WITH ITS MAIN PARTNERS
Promoting scientific and technicalproduction
In 2004, the IRSN organised its first in-houseseminar on the theme of scientific excellence. In
2005, its recommendations led to several initiatives
being implemented including the drafting of ascientific and technical excellence programme,
the organisation of a dedicated committee, a crossdivisional scientific event, training through researchand the implementation of a system for assessing
the Institute’s scientific and technical excellence.

Assessing the scientific and technicalexcellence of the Institute
The IRSN carried out targeted assessments of itsscientific and technical activities: results from a
research programme, scientific collaboration, expert
assessments, etc.These test initiatives contributed
to approving the assessment procedure and togarnering practical feedback for continuing thepolicy in 2006, particularly regarding the distinction
to be made between scientific assessments andassessments regarding the strategic options offered
by a programme.

8]

I R S N 2005 ANNUAL REPORT

Tailoring research tools
As part of a debate into the heavyweight equipment required for research into nuclear safety to
be maintained at international level, the IRSN
renovated CABRI, a reactor for testing the safetyof nuclear fuel, in 2005. The Institute also set up aninternational focus group with the objective of
fuelling the IRSN/CEA debate on the future of the
PHEBUS reactor, which is a test facility for studying
damage to a nuclear reactor core and the releaseof related fission products.

Formalising the Institute’s relationships
with the public authorities
In 2005, the IRSN finalised the system to formalise
its relationships with public authorities by setting
up framework agreements with several government health and safety bodies in particular. Every
year, the relevant application protocols specify thecontent of the activities carried out as part ofthese agreements.This allows the Institute to better
meet the expectations and priorities of publicauthorities and to better tailor its resources to theirrequirements and thus improve the efficiency ofthe overall system of expert assessments.

Modernising the radiological monitoring
resources for response operations
In 2005, the IRSN started several initiatives aiming
to provide the Institute with more effective resources,
including the renewal of the Institute’s response
vehicles, and preliminary studies into renewing its
network for measuring radioactive aerosols.
The Institute has continued enhancing its
information system for monitoring exposure toionising radiation (SISERI).

AGREEMENTS SIGNED BY
THE IRSN IN 2005
7 June. Signature of the frameworkagreement between the Department forLabour Relations (DRT) and the IRSN defining
the conditions according to which the IRSN
provides its technical support to the DRT
with respect to the radiological protection of
employees and the procedure for initiating
and performing technical support initiatives.
29 June. At the Seyne-sur-Mer, signatureof the 2005 framework agreement defining
the terms of the collaboration between
the IRSN and Ifremer in national andinternational study and research programmes
in the Mediterranean.

Optimising the use of available resources
In 2005, the IRSN launched a debate into the relativevalue of its technical support activities to the publicauthorities.An analysis of its responses to the DGSNR
was thus undertaken in conjunction with the latterto focus the available resources on activities
producing the highest added value.

THE GOVERNMENT-IRSN OBJECTIVESAGREEMENT 2006-2009
The four-year objectives agreement for theperiod 2006-2009 drawn up in 2005 aims to
structure the strategic approach chosen to
enable the IRSN to perform its missions in an
optimised manner and define its key scientificand technical objectives. This contract
structures the IRSN’s activities around theseven challenges listed below and describes
the objectives to be achieved in terms ofpolicy effectiveness and the Institute’s
management instruments.
Helping to ensure a high level of safety andradiological protection in existing nuclear
facilities until the end of their life.
Obtaining the specialist knowledge andresources required for future nuclear facilities
in a timely manner.
Monitoring the exposure of workers and the
public to ionising radiation and monitoring
radioactivity in France.
Contributing to the fight against the
proliferation of nuclear, biological andchemical weapons and to controlling nuclear
and radiological safety in the face of terrorism.
Developing the IRSN’s technical response
and mobilisation resources to respond to therisk of a major radiological emergency.
Understanding the effects of chronic lowlevel irradiation.
Developing protection against ionisingradiation in the medical sector.

I R S N 2005 ANNUAL REPORT[9IRSN Activities

Management and Support

2. OPTIMISING ITS TECHNICAL SUPPORT MISSIONS TO ADMINISTRATIVEAUTHORITIES AND ITS CONTRIBUTION TO PUBLIC POLICY

3. MAKING ITS EXPERTISE ACCESSIBLE TO MEET SOCIETY’S EXPECTATIONS
Promoting transparency
In 2005, the IRSN continued its policy of making
its expertise accessible to the civil society througha host of initiatives involving associations, unions
or other specialised institutes. The IRSN becamemuch more involved with the Local Information
Commissions (CLI) by responding to requests fromthe National Association of Local Commissions(ANCLI) regarding nuclear waste management
governance, by performing field work with the CLI
in the Loire basin and taking part in the public debate
on the head-of-series EPR in Flamanville, for which
the IRSN drafted “stakeholder’s specifications”. As
part of this contribution, the IRSN recalls that it isinvolved in work in this area with the ANCLI and

the GSIEN (Group of scientists for information on
nuclear safety) and that it is planning on continuing
its efforts in this area.

Contributing to training in radiologicalprotection
Another IRSN vocation is to provide radiologicalprotection training to healthcare professionals
and individuals subject to exposure in their working
environment. To provide the most comprehensive
training possible, the Institute doubled the numberof sessions organised in 2005 so as to reconcile
customer satisfaction with optimal quality, bothin terms of the teaching strategy and the resources
developed to perform it.

4. DEVELOPING THE EUROPEAN AND WORLDWIDE DIMENSION
Contributing to research and European
expertise
In 2005, the IRSN decided to respond to the lastcall for tender issued by the European Union’s
6th FPRD by formulating 14 proposals.
As part of setting up a club of technical safety bodies,
these founding establishments drew up a joint work
programme for assessing the safety of reactors
and nuclear facilities, identifying research needs
and managing scientific and technical knowledge.

Promoting nuclear safety and security
worldwide
At the same time, the Institute launched several
key international programmes such as SOURCETERM, carried out in conjunction with a number ofinternational partners (European Commission,
United States, Canada, South Korea, Switzerland,etc.).
The purpose of this initiative is to enhance knowledge
about releases potentially occurring in the case ofa severe accident with power reactor core meltdown.
The IRSN also contributed to a greater extent to
the work of the IAEA, principally by assigning more
nuclear protection, radiological protection and nuclear
safety specialists to the Vienna branch, and to multilateral co-operation carried out within the OECD/NEA(see box). The Institute also participated in somekey international support programmes as part of
the G8 Global Partnership by contributing to the
preparation and performance of initiatives decided
upon by Russia and France, such as security at nuclear
bases and better monitoring of radioactive sources,
the main purpose being to prevent risks of proliferation. The IRSN also took part in international

10 ]I R S N 2005 ANNUAL REPORT

programmes to improve the safety of facilities in
Eastern Europe as part of European programmes
and the EBRD, mainly with respect to its partnershipwith GRS.

DETAILS
The OECD’s Nuclear Energy Agency (NEA) is
an international agency grouping together
28 member countries from Europe, North
America and the Asia-pacific region. The NEA’s
work is carried out by seven technical advisorycommittees including the Nuclear Facility
Safety Committee (CSIN) of which the IRSN
is an active member.
The chairman of the CSIN is L. HAHN, Directorof GRS, and the Vice-Chairman is P. JAMET,
Deputy Director General of the IRSN.
This committee comprises focus groups
specialising in the various disciplines (riskassessment, the human factor, severe accidents,etc.) and is coordinating about 15 research
projects financed and performed as part ofco-operation between the member countries
and at the European Commission level. These
projects include the CABRI-Water loop (fuel)and PRISME (fire propagation) projects carriedout by the IRSN, ROSA and PKL(thermohydraulics) carried out in Japan andGermany, and the MCCI (corium-waterinteraction) project carried out in the
United States.
These three programmes benefit from a French
contribution financed by the IRSN.

The Institute’s activities
TECHNICAL SUPPORTFOR PUBLIC AUTHORITIES

688 technical notifications

RESEARCH

50%

of the IRSN’s
budget is devoted toresearch activities

to the public authorities(excluding activities relating
to defence)

144 publications

254 notifications to thein scientific journals, witha proofreading committee

safety authorities for activities
relating to defenceHUMAN
RESOURCES

100 bilateral agreements

1,675 people

15 countries involved in

16 French patents
in force (including one
co-owned with the CEA)

20

patents
in force abroad

158 software applications

INTERNATIONAL
ACTIVITY
signed with research andexpert assessment bodies

THE IRSN’SINTELLECTUAL ASSETS

and databases listed, 24 of which
are co-owned with the CEA

employed by the IRSN,
with 67 assigned to the
DGSNR or otherinstitutions

these agreements

80 international projects
in progress

The budget and its breakdown2005 Budget

Operation/Investment expenditure:
Operation 91%
Investment 9%

Other French
resources

Public 15%
EDF, research and development 19%
Cogema, research and development 6%
CEA 2%
Others 58%

Financing resources:
LOLF-189 programme subsidy 82%
Other French resources 15%
Foreign resources 3%

Foreignresources

CCE 30%Riskaudit 39%
GRS 4%
Epri 6%
Others 21%

I R S N 2005 ANNUAL REPORT[ 11

IRSN Activities

Management and Support

The IRSN in 2005, a few figures

Key events 2005

January

March

May

27_ Speech by Jacques
REPUSSARD, Director Generalof the IRSN, on reversible orirreversible storage in deep
geological formations during
a public hearing before theParliamentary Office for
Evaluating Scientific andTechnical Options (OPECST).

16/17_ Meeting in London of
10 members of the IRSN’s internal
stakeholders’ network with the Risk
Policy Unit team from the Health& Safety Executive (HSE) as part ofsharing innovating experiences
involving the stakeholders.

17_ Patent application to
the INPI regarding the use of
a new protocol to analyse
actinides (uranium, plutonium
and americium) in urine aimed
at optimising the medical
monitoring of workers exposed
to a risk of internal
contamination.

February
15 _ Launch of SISERI,
the national dosimetric
information system, whichcentralises information on theindividual dosimetry of the
250,000 workers exposed toionising radiation in France ina database accessible toauthorised persons.
21_ Signature of theoperating protocol for atechnical focus group between
the IRSN and Framatome ANP(Areva NP) regarding the
ANTARES project for a very
high temperature reactor
cooled with helium.

12 ]I R S N 2005 ANNUAL REPORT

16_ Presentation of the
Pierre Isoard award to Davide
GUERRA, for his thesis work on
the modelling of airborne
contaminant transfer into
ventilated premises close to an
accidental emission source.

April
5 _ Introduction of the IRSN
into the French National Civilian
Security Council, which provides
advice about risk prevention,
monitoring, warnings, crisis
management and initiatives toprotect the population.
21_ Presentation to the pressof the results from the IRSN’s
Baromètre 2004 initiative on how
the French population perceives
risks. This study shows that Frenchpeople acknowledge the efforts
put into reducing certain risks
and the quality of the work
carried out by scientific experts,
but want the scientific community
to be more aware of their
expectations and to benefit from
more comprehensive information
which does not conceal
differences in interpretation.

20 _ Inauguration of
two new facilities at the
Cadarache site (Bouches-duRhône): AMANDE (accelerator
for metrology and neutronic
applications for external
dosimetry) and EPICUR(Experimental Programmeon Iodine Chemistry Under
Radiation as part of the
SOURCE TERM programme).

June
1 _ Start of experimental
campaigns: MOZART (study ofthe oxidation of zircaloy
cladding in the presence of air)and BECARRE (study of damage
to boron carbide control rods).
Both are part of the SOURCETERM international research
programme.
6 _ Approval by theFederation of Post-Graduate
Teaching in Radiology (Fepur)
for providing radiologicalprotection training to medical
and paramedical staff.

July
8_ Ratification of theinternational agreement on
the physical protection of nuclear
material (CPPMN) in Vienna.

21_ Publication by theInstitute of the final report on
the CAROL (Camargue-RhôneLanguedoc) project regarding theobservation and study ofradioactivity in the environment.

13 _ Presentation
to the press of the conclusions
from the FGI (Franco-German
initiative) international
scientific and technicalprogramme for Chernobyl,
jointly coordinated by the IRSN
and its German counterpart,GRS.

30_ Approval of the IRSN’s
Technical Crisis Centre (CTC)
following the triggering of theinternal emergency plan for theNogent-sur-Seine (Aube)
nuclear facility.

November
3_ Commissioning of a
new version of the ASTRAL
calculation code, developed by
the IRSN and cofinanced by
EDF.
This code is used to quantify
the transfer of radioactive
elements into agricultural andforest environments, should
a nuclear accident occur
causing releases into theatmosphere.

AugustDecember
12 _ Publication of a new
prefectorial order regulating allclassified facilities forenvironmental protection (ICPE)
of the IRSN at the Cadarachesite (Bouches-du-Rhône).

September
1 _ In conjunction with EDF
and the CEA, launch of theinternational SOURCE TERM
programme, in association with
the European Commission,
Switzerland, the United States,
Canada and South Korea.
This research programme aims tolimit uncertainty about theassessment of radioactive productreleases into the environment in
the event of a water reactor core
meltdown accident.

October
1 _ Participation by the
IRSN in the public debateorganised by the Cité desSciences et de l’Industrie in Parison the long-term storage ofradioactive waste.
24/27 _ Organisation by
the IRSN of a conference inVaux de Cernay with Ulm
University and the EBMT(European Cooperative Groupfor Blood and Marrow
Transplantation) on medical
response in the case of aradiological accident or
terrorist attack.
27 _ Approval by the
IRSN’s Technical Crisis Centre(CTC) following an incident
affecting reactor no. 3 at theBlayais (Gironde) nuclear
facility.

12/13_ Presentation to
the expert advisorycommittee of the IRSN’scomments on the “Dossier
2005 Argile” regarding thefeasibility of storing waste inclay geological formations.
The project was drawn up by
the ANDRA in application of
the law of 30 December 1991
relative to radioactive waste
management.
15_ First test carried out
at the DIVA facility on fire
propagation in a laboratory
and plant environment (PICSEL
programme).
The results of this programme
will contribute to validating
simulation software used toforecast the aftermath of an
accidental fire in an electricalcabinet on the containment ofradioactive material.

I R S N 2005 ANNUAL REPORT[ 13

IRSN Activities

Management and Support

9/10 _ National security
drill at the COGEMA facility in
La Hague.

IRSN missions
The IRSN’s creation order (no. 2002-254 of 22 February 2002) set seven missions for the Institutein terms of radiological protection and nuclear safety. They are grouped into three areas:

RESEARCH AND PUBLIC SERVICE MISSIONSDefining and implementing national and international research programmes
The IRSN defines and conducts research programmes aimed at maintaining and developing theskills required to carry out expert assessments in its fields of activity. It either carries them out itself
or entrusts them to other French or foreign research institutes. Some programmes are carried out
in a European or international context.

Contributing to training in radiological protection
As an establishment carrying out research and expert assessments, the IRSN has a duty tocontribute to teaching and learning in its field of expertise: nuclear safety and security andradiological protection. The radiological protection training courses it organises are directed at
professionals working in the health sector and people exposed to risk in their jobs.

Permanent monitoring in the field of radiological protection
The IRSN is involved in permanent monitoring of radiological protection, mainly by contributing toradiological monitoring of the environment and ensuring the management and use of dosimetricdata concerning employees exposed to ionising radiation. The Institute also manages the inventoryof ionising radiation sources.

Contributing to public information and transparency
The IRSN informs the public of nuclear and radiological risks via publications, the Internet, a travellingexhibition jointly organised with the DGSNR, conferences, and much more.
With a view to providing transparency in the field of nuclear and radiological risk management, theInstitute is continuing its initiatives with the Local Information Commissions (CLI).The goal of these
initiatives is to make the IRSN’s studies and expert assessments available and to involve the stakeholders
as part of pluralistic groups of experts working on the technical challenges generated by complex
or controversial subjects.

TECHNICAL SUPPORT AND ASSISTANCE FOR PUBLIC AUTHORITIESTechnical support with regard to nuclear and radiological risk
The IRSN provides technical support in the field of nuclear and radiological risk to the competentpublic authorities. Its scope covers civilian nuclear facilities, facilities classified as secret, the transportof radioactive substances, the application of treaties on the control of nuclear and sensitive materials
and the physical protection and safety of industrial and medical applications. The Institute carries
out expert assessment work, research and development, model testing and development, codes andcalculation tools in the field of safety and radiological protection.

Operational support in the event of a crisis or radiological emergency
In the event of an incident or accident involving ionising radiation sources, the IRSN carries out
technical, healthcare and medical measures for public authorities specific to ensuring the protectionof the population, workers and the environment and to resuming a situation of safety on the facilities.

CONTRACTUAL SERVICES IN EXPERTISE, RESEARCH AND MEASUREMENTS
Carrying out expert assessments, research and work for public or private bodies
The IRSN offers contractual services in the fields of expert assessments, research and projects (analyses,
measurement and dosing) for French, European and international bodies in the public and private
sector. The Institute also provides third-party expert assessments on classified installations for theprotection of the environment outside of the nuclear sector.

14 ]I R S N 2005 ANNUAL REPORT

Activities and staff

Paris region staff: 1,244 employees

CHERBOURG - OCTEVILLE

CLAMART■ Environment(Head office)Staff departments

FONTENAY-AUX-ROSESLE VÉSINET

Operational activities■ Nuclear defence expertise ■ Environment and response■ Human radiological protection ■ Reactor safety■ Safety of plants, laboratories, transport and waste■ Environment and response■ Human radiological protection

SACLAY■ Safety of plants, laboratories,

ORSAY

transport and waste■ Environment

PIERRELATTE■ Response■ Human radiological protection

CADARACHE■ Environment■ Prevention of major accidents■ Human radiological protection

TOURNEMIRE■ Nuclear defence expertise■ Environment

AGEN■ Environment and response

LES ANGLES - AVIGNON■ Response■ Safety of plants, laboratories,

transport and waste

LA SEYNE-SUR-MER■ Environment

MAHINA (Tahiti)■ Environment

South-East staff: 330 employees approximately

The details for all IRSN sites can be found on the flap at the back of the report.

I R S N 2005 ANNUAL REPORT[ 15

IRSN Activities

Management and Support

Sites

The Board of Directors
April 2006T

he Board of Directors meets at least four times a year. Through its deliberations, it deals withIRSN business in compliance with article 10 of its implementing order, and particularly thegeneral conditions governing the organisation and functioning of the establishment. It discusses
the Institute’s programmes and the annual report. In terms of finance, it approves thebudget, decisions involving changes, financial statements and income appropriation.
The Board of Directors is made up of 24 members: 10 government representatives appointed by order,
including the director general for nuclear safety and radiological protection, and the government representativein charge of nuclear safety and radiological protection, six qualified persons also appointed by order andchosen for their skills in the Institute’s area of activity, including a member of parliament or of the French
senate, who is a member of the Parliamentary Office for Evaluating Scientific and Technological Options,and eight elected staff representatives from the establishments.The term of office of the board of directors’
members is five years which can be renewed once for the six qualified persons.
Five new directors have been appointed since 2005.

GOVERNMENT REPRESENTATIVES

Jean-François LACRONIQUE

Head of the National Mission to support nuclear risk
management, representing the Civilian Security Minister

Professor of Medicine, on the proposal of the Health
Minister, chairman of the Board of Directors

Jean-Denis COMBREXELLEClaude BIRRAUX

Director of Labour Relations, representing the Labour Minister

Vice-Chairman of the Parliamentary Offce for Evaluating
Scientific and Technical Options

Guillaume SAINTENY
Director of Economic Studies and Environmental
Assessment, representing the Ecology and Sustainable
Development Minister

Florence FOUQUET

Jean-Marc CAVEDON
Director of the Division for Research into Nuclear Energy
and Safety at the Paul Scherrer Institute in Switzerland,on the proposal of the Research Minister

In charge of the nuclear industry sub-division at the Energy
and Raw Materials Directorate, representing the Industry
Minister

Maurice LAURENT

Dominique GOUTTEJean RANNOU

Director of the Energy, Transport, Environment and Natural
Resources Division, representing the Research Minister

Air Force General, on the proposal of the Defence Minister

Marcel JURIEN de la GRAVIÈRE
Nuclear safety and radiological protection representative
for activities and facilities relating to defence

André-Claude LACOSTE
Director General of Nuclear Safety and Radiological Protection

Jocelyne BOUDOT
Assistant Director for the management of environmental
risk, representing the Health and Social Affairs Minister

Former French National Assembly Head of Department,on the proposal of the Industry Minister

The qualified person proposed by the Ecology andSustainable Development Minister will be appointed
shortly.

LEGAl REPRESENTATIVES
Thierry TROUVÉ
Director of Pollution and Risk Prevention,
Government Commissioner

Daniel RACINET

Frédéric EYRIES

Government Inspector

Inspector General for Armaments, representing
the Defence Minister

Jacques REPUSSARD

The representative for the budget division will be
appointed shortly.

Michel BRIÈRE

EMPLOYEE DIRECTORS
Mireille ARNAUD, Hervé BOLL, Betty CATANIA,
Jean-Marc DORMANT, Thierry FLEURY,
Dominique MARTINEAU, Xavier MOYA,
François ROLLINGER

16 ]QUALIFIED PERSONSPatrick AUDEBERTI R S N 2005 ANNUAL REPORT

Director General
Deputy Director General, in charge of
the IRSN’s defence-related missions

Jean-Claude DALE
Accountant

Philippe BOURACHOTWorks Committee Secretary

April 2006T

he IRSN has a scientific board whose purposes are defined by the Institute’s creation decree.
The council put forward an opinion concerning the Institute’s programmes, assesses their results
and can formulate recommendations on IRSN’s activity-related policies.Its opinions or recommendations are forwarded to the board of directors and supervisory ministries.
The scientific board issues a written opinion on the Institute’s annual report, and it can be consulted by theboard of directors’ chairman or by supervisory ministries regarding all research in the establishment’s areasof skills. Its opinion may be requested on all issues or actions involving by the IRSN.
In 2005, the scientific board held two plenary meetings (in May and November) during which it gave
in particular its opinion on the Annual Report 2004 and on the Scientific and Technical Report 2005.
These meetings also included visits to some facilities (such as CABRI and AMANDE in Cadarache or the
DEI/SARG facilities in Fontenay-aux-Roses) and were an opportunity for the board to gradually become
informed of the different aspects of the IRSN’s research programmes and organisation. As indicated in
the board’s rules of procedure, more specific assessments are carried out by commissions created on the
joint initiative of the board and the IRSN. The commission devoted to studies and research carried out by
the Institute into the deep storage of radioactive waste held its first meeting on 21 September 2005 andshould continue its work in the first quarter of 2006. A second commission, dedicated to the IRSN’s work
into reconstructing the fallout of the Chernobyl accident in France, will carry out its work at the beginningof 2006.
The scientific board is composed of 12 members chosen according to their scientific and technical skills
and appointed for five years by the joint order from the supervisory ministers of 6 July 2004.

Chairman: Michel QUINTARD

Jean-Marc COSSETCNRS Research Director at the Fluid Mechanics Institutein Toulouse, on the proposal of the Research Minister

Professor of Medicine, head of department at
the Curie Institute, on the proposal of the Health Minister

George YADIGAROGLU
Bernard SEVESTRE
Engineer General for Armaments, Deputy Director at the
French Atomic Energy Commission, on the proposal of
the Defence Minister

Martin SCHLUMBERGER
Professor of Medicine, head of department at the
Gustave Roussy Institute, on the proposal of the Defence
MinisterEthel-Esther MOUSTACCHI
Scientific Director reporting to the High Commissioner for
atomic energy, on the proposal of the Environment Minister

Victor TESCHENDORFF
Head of Department at Gesellschaft für Anlagen und
Reaktorsicherheit (GRS / Germany), on the proposal of
the Environment Minister

André AURENGO
Professor of Medicine, head of department at the
Pitié-Salpêtrière hospital, on the proposal of the Health
Minister

Professor of Nuclear Engineering at the Swiss Federal
Institute of Technology, on the proposal of the Industry
MinisterAndré PINEAU
Professor at the Paris Ecole des Mines, on the proposal of
the Industry Minister

Philippe LECONTE
Physicist, former director of the CEA’s radioactive waste
management research programme, on the proposal of
the Research Minister

René AMALBERTI
Professor of Medicine, head of department at the Aerospace
Medicine Institute, on the proposal of the Labour Minister

Lars-Erik HOLM
Professor of Medicine, director general of the Swiss
Authority for radiological protection, on the proposal of
the Labour Minister

I R S N 2005 ANNUAL REPORT[ 17

IRSN Activities

Management and Support

The Scientific Board

Organisation chart
April 2006
BOARD OF DIRECTORS
Jean-François LACRONIQUE, Chairman

FUNCTIONAL DIVISIONSDivision for Strategy,
Development and External
Relations

Division for Scientific andTechnical Evaluation,and Quality

Michel BOUVET*, Director

Joseph LEWI, Director

Deputy Director in charge of external relations:Jean-Bernard CHÉRIÉDeputy Director in charge of programmes:
Yves SOUCHET
Research programmes
Expert assessment programmes
Society awarenessInternational relations
Secretariat for advisory committees

Radiological protection training
Assessment and scientific activities
Quality management
Health, safety and environmental protection
Scientific and technical knowledge
engineering
Scientific information resources

General Secretariat

Communications Division

Jean-Baptiste PINTON, General Secretary

Marie-Pierre BIGOT, Director

Financial affairs
Human resources
Commercial relations and legal support
Property management and general services
Information systems administration

In-house communication
Information to the press and press relations
Public relations and programmes* From 1 January 2006.

GENERAL SERVICES
Accounting Office
Jean-Claude DALE, Accountant

18 ]I R S N 2005 ANNUAL REPORTJacques REPUSSARD, Director General

Michel BRIÈRE, Deputy Director Generalin charge of the IRSN’s defence-related missions

Philippe JAMET, Assistant Director Generalin charge of general affairs

OPERATIONAL DIVISIONSDivision for Nuclear Defence
Expertise

Division for Human RadiologicalProtection

Jérôme JOLY, Director

Patrick GOURMELON, Director

Application of international controls
Technical support to public authorities
and studies
Assessment of defence-related safety
Safety of nuclear facilities

Radiological protection studies and expert
assesments
Radiobiology and epidemiology
External dosimetry
Internal dosimetry

Division for Environment
and Response

Division for Reactor Safety

Didier CHAMPION, Director

Pressurised water reactors
Gas-cooled, fast neutron and test reactors
Materials and structures
Systems and risks
Thermohydraulics, cores and the runningof facilities
Severe accidents and radiological consequences
Human factors

Study into the behaviour of radionuclides
in ecosystems
Study and monitoring of radioactivity
in the environment
Analysis of risks related to the geosphere
Sample processing and metrology for the environment
Radiological protection response and support
Emergency situations and crisis organisation

Martial JOREL, Director

Division for the Prevention ofMajor Accidents

Division for the Safety of Plants,
Laboratories, Transport and Waste

Michel SCHWARZ, Director

Thierry CHARLES, Director

Studies and experimental research into accidents
Experimental instrumentation and engineering
The study and modelling of fuel in accident
scenarios
Fire, corium and containment studies and modelling

Fuel cycle transportation and facilities
Laboratories, irradiators, accelerators anddecommissioned reactors
Radioactive waste
Industrial, fire and containment risks
Criticality
Airborne dispersal of pollutants

I R S N 2005 ANNUAL REPORT[ 19

IRSN Activities

Management and Support

GENERAL MANAGEMENT20]

I R S N 2005 ANNUAL REPORTMANAGEMENT
AND SUPPORTI R S N 2005 ANNUAL REPORT[ 21

IRSN Activities

Management and Support[2]

MANAGEMENT
AND SUPPORTTo enhance the quality, pertinence and clarity of the initiatives
carried out daily by its teams as part of its scientific, technicaland operational programmes, the IRSN performs a series ofcross-divisional functions in the fields of scientific andtechnical excellence, health and safety at work, quality,communication and human resources.
The Institute assesses the professional risks to which its
employees are exposed by focusing on changes to the legal
and regulatory framework in this area. It is developing aquality-based management system with the objective ofobtaining ISO 9001 certification by 2007 and is continuing
its policy of communication with a view to raising awarenessabout its activities and skills. Finally, the Institute is pursuing
its efforts to improve employee efficiency through training
and career management.

22 ]

23

Scientific and technical excellence

28

Quality

30

Health and safety at work

33

IRSN communication

36

Human resources serving
development at the IRSNI R S N 2005 ANNUAL REPORTScientific and technical excellence]

Scientific and technicalexcellence
The IRSN’s policy of scientific and technical excellence is based on promoting thisexcellence, setting up a system of assessing the Institute’s activities from a scientificand technical standpoint and evaluating the activities contributing to the IRSN’s
reputation. In the field of scientific and technical knowledge engineering, the IRSN’s
activities focus on two key areas: information on scientific and technical questions
and archive management. In 2005, several initiatives were implemented to facilitate and widen access to the scientific and technical documentation requiredby the IRSN’s engineers and researchers to perform their missions.

The COXST committee
dedicated to scientificand technical excellenceThis committee was set up in 2005 and debates,
analyses and monitors the direction taken in termsof the policy of scientific and technical excellence,
recommendations resulting from the scientificand technical assessments carried out by theInstitute or by the Scientific Board, and initiatives
with respect to scientific communication. Within
the IRSN, it carries out initiatives to promote, assess
and acknowledge the excellence of the Institute’s
activities and teams.

23 agreements
signed with
universities,
engineeringschools or the
CNRS

11 km ofarchives“Targeted” test assessments
A “targeted” assessment consists of objectively
analysing a specific activity to obtain a pertinent
representation which allows an opinion andrecommendations to be formulated. The assessment may focus on any of the IRSN’s scientific ortechnical activities (services, expert assessments,
research, studies). They are conducted by experts
who have not been involved in the activity inquestion and from outside the Institute if possible.
Test initiatives were launched on different topicalareas in a bid to establish the type of questions tobe asked and practical procedures regarding the

Implementation of the scientificand technical excellence
programme
This programme was set up in 2004 and groups
together the cross-divisional or generic initiatives
contributing to achieving excellence in the IRSN’s
programmes and to the promotion and evaluationof its skills and work. Its content focuses on specificactivities which are not part of the Institute’s
other programmes:> training through research and teaching;> scientific activities;> scientific and technical assessments;> scientific and technical communication;> exploratory research.

The scientific and technical assessment director
with three co-workers.

I R S N 2005 ANNUAL REPORT[ 23

IRSN Activities

MANAGEMENT AND SUPPORT[MANAGEMENT AND SUPPORTScientific and technical excellence

assessments carried out with the teams concerned:
the findings from a research programme, therefocusing of this programme, scientific collaborations, expert assessments of safety, a team, etc.
These test assessments were used to check theapproach out and update knowledge for futureassessments.They have shown that the structuringphase carried out by the assessment with therelevant team is essential to correctly defining theelements to be taken into account to ensure its
effectiveness. They have also highlighted thedifference between a scientific assessment and anassessment of strategic options regarding a
programme, and the difficulty in evaluating anexpert assessment activity without having recourse
to a second assessment.
At the end of the year, the divisions isolated about
15 subjects which may undergo a scientific andtechnical assessment in 2006-2007.

Global scientific andtechnical assessment:setting up indicators
The indicators fulfil a three-fold function: they are
the in-house tools used to achieve improvement
objectives, they help to clarify the IRSN’s stancewith respect to outside society, and they contributeto the acknowledgement of the scientific andtechnical quality of its work.
A comprehensive set of criteria has been established to define indicators for monitoring developments in scientific and technical excellence, at thelevel of the units and general management.
The indicators used for scientific and technicalassessments must be consistent with those
implemented as part of the French Organic Law
relative to Finance Laws (LOLF) or the objectives
agreement. The Institute has also undertaken to
actively participate in a project to produce indicators for the purpose of comparisons with national
research.

Implementation of a crossdivisional scientific andtechnical activity
In-house scientific and technical activities aim topromote knowledge-sharing and to better identify,
coordinate and take advantage of the cross-divisional
initiatives in the operational units.The first activity
group was set up in 2005 to focus on radiation-

24 ]I R S N 2005 ANNUAL REPORTThe central level of the division for scientific andtechnical knowledge engineering.

material interaction codes as part of using the Monte
Carlo codes.
The objectives of this group were drawn up into five
points at the launch seminar held in September:> identifying, learning and implementing the best
methods and practices;> sharing and upgrading technical skills;> enhancing knowledge on the use of calculation
codes;> raising awareness about procedures and validation methods for the calculation results;> preparing for the future.

Exploratory research:definition andapplication procedures
Helping researchers to express their creativity tobenefit future IRSN programmes is the objectiveof exploratory research. The Institute thus set up a
focus group in October 2005 composed of representatives from the various divisions.This group drafted
a definition of exploratory research and the proposal,
selection and implementation procedures to be
used.

IRSN Activities
These are essential for a research body like the
IRSN. Indeed, although Institute research is focusedon acquiring knowledge through expert assessments, independent experts should be allowed togive their opinion on this research, and to criticallyanalyse, evaluate and enhance it by putting forward new ideas. The relationships with universities
are a primary way of developing and improving IRSN
skills. By allowing professionals from the Institute
to contribute to the training given at the universities and engineering schools, these links are a
way of enhancing the Institute’s reputation,
attracting young blood and fulfilling its duty topass on its knowledge through teaching andtraining.
The studies carried out in conjunction with universities, engineering schools and CNRS laboratories
are drawn up into co-operation agreements covering joint research projects and the acceptance of
trainees. In 2005, co-operation agreements weresigned with different universities and schools (see
Focus opposite). As part of a national co-operationagreement signed in 2003, 11 specific agreements
were signed with different CNRS laboratories.
They cover varied topics such as mass spectrometry
at high temperatures, tension creep of concrete,
analysis of the thermomechanical behaviour offuel cladding , and the modelling of radiationtransfer in a porous environment.

The publication policy debate
A debate was conducted on the IRSN’s policy interms of scientific and technical publications. The
Institute has an obligation to publish articles inapproved scientific journals in its fields of activity(research and expertise) to show the value of its
findings. Time should be allowed for this in its
programmes.

[FOCUS]

Relationships with universities
and scientific organisations

Agreements signed in 2005 between
the IRSN and universities, engineeringschools or the CNRSCollaboration framework agreements with:> the Méditerranée Aix-Marseille 2 University – 11 August 2005
> the Joseph Fourier University in Grenoble – 17 October 2005
> the Paris XII University – 17 November 2005
Specific collaboration agreements with:> Havard University – 17 January 2005
> The Ecole des Mines in Saint-Etienne – 20 October 2005
> The Ecole Nationale Supérieure de Chimie in Paris –18 November 2005
Six specific agreements with the Armines laboratories
Specific agreements with CNRS laboratories:> IMF (Fluid Mechanics Institute) in Toulouse –9 February 2005
> Civil Engineering and Building Department at the ENTPE(National Engineering School for Government Civil Engineering) in
Vaulx-en-Velin – 10 March 2005
> Géosciences Azur – 21 March 2005
> LaMCoS (Contact and Solids Mechanics Laboratory) at the INSA
(National Institute of Applied Science) in Lyons – 22 April 2005
> EM2C (Molecular and Macroscopic Energy and Combustion
Laboratory) at the Ecole Centrale in Paris – 23 May 2005
> CEREGE (Management Sciences Research Centre) in Poitiers –27 July 2005
> LPM2C (Laboratory for the Physics and Modelling of Condensed
Media) in Grenoble – 9 August 2005
> LSGC (Science of Chemical Engineering Laboratory) in Nancy –23 August 2005
> LMGC (Mechanics and Civil Engineering Laboratory)in Montpellier – 29 August 2005
> LTCPM (Laboratory for Metallurgical Thermodynamics andPhysics-Chemistry) at the Ecole Nationale Supérieure
d’Electrochimie et d’Electrométallurgie in Grenoble –18 November 2005
> LMT (Mechanics and Technology Laboratory) at the Ecole
Normale Supérieure in Cachan – 29 November 2005

I R S N 2005 ANNUAL REPORT[ 25

[FOCUS][MANAGEMENT AND SUPPORTScientific and technical excellenceTraining through research:encouraging results

Training through research,teaching and publications:publication of annual reports
The IRSN set up an organisation allowing it topublish annual reports on training through research,teaching and publications. Many of the figures
published in this annual report come from thesereports. (see Focus opposite)

Scientific communication:
restructuring of the IRSN’s
scientific website
The goal of the IRSN’s scientific website (www.irsn.
org/net-science) is to inform the scientificcommunity about the teams and the work carriedout by the Institute. In 2005, it was restructured
and its graphics improved to provide greater
clarity and simplified access to information. This
new look site was online in July and generated its
first positive results with a 40% rise in the numberof connections between 2004 and 2005.
Effective collaboration between academics and researchers.

Thesis supervision is an opportunity for the IRSN to maintainclose links with the academic community as most theses
prepared within the Institute are under the supervision of
external researchers.
The IRSN thus undertook a policy of training through research in2004. The benefits of this policy became apparent with 27 new
doctorate students taken on in 2005, as against 18 in 2004.
At the same time, about 20 recent thesis graduates are roundingout their training by following a post-doctorate training course
at the IRSN. A reasonable number of them will then be recruitedby the Institute(1).
Moreover, the Institute is encouraging its researchers to support
its eligibility to supervise research (HDR) policy, thus showing its
willingness to open up to the world of university research.
In 2005, three new HDRs were delivered to IRSN researchers.

Scientific publications: twobooks published in 2005
The IRSN publishes a collection of scientific books.
The translation of an ICRP document published at
the end of 2004, a guide for medical practitioners
entitled Vos patients et les rayons (Your patients andradiation) was a tremendous success with 4,000
copies issued on request to the medical community.
Two other books were published in 2005. The firstwas a French translation of publication 91 by theInternational Commission on Radiological Protection(ICRP) entitled Cadre méthodologique pour évaluer
l’impact des rayonnements ionisants sur les espèces(1) 4 out of the 8 students who vivaed their theses in 2004 were employedby the IRSN.

Publications to share the IRSN’s scientificknowledge.

26 ]I R S N 2005 ANNUAL REPORTIRSN Activities
non humaines (Methodological framework forassessing the impact of ionising radiation on nonhuman species) ( collection Lignes directrices). The
second, entitled Scientific trends in radiologicalprotection of the environment, is a collection ofcontributions by speakers from the Ecorad 2004
congress.

IRSN archives: inventory
finalisation
The archive inventory ended in 2005 with the formation of a database enabling searches to be carriedout across the 11 km of the Institute’s archives
and the acquisition of a new archive management
software. Historians can thus now use the IRSN’s
historical archives.A debate is also under way regarding electronic archiving.

Wider electronic accessto scientific and technicaldocumentation
The scientific information resource centre (Cris) canbe used by all staff and now proposes the full textof scientific and technical documents from several
hundred electronic reviews to the entire Institute.
Two new bibliographic databases, one offering fulltexts, have been put online.
Moreover, the Cris’ new bibliometric database
now indicates the impact factor of international
scientific reviews thus helping researchers to
optimise their publications. Dialog, the database
query portal, has been enhanced, four patent

Scientific and technical documents
available to all staff.

Archive research facilitatedby a database.

bases have been added and six Afnor reference
standards can be consulted online.This information
is available to all staff on the intranet. In addition
to this, a new documentary management software
can be used to consult references from the Cris’
document base on the intranet.
The Cris has provided information about the tools
and services on offer to the different divisions
through presentations and a mini-guide of which
500 copies were issued.

Capitalising on scientific andtechnical knowledge: launch of
the preparation phase
The objective of this project is to set up a tool
allowing all IRSN employees to quickly locate arequired document from those produced by theInstitute, while complying with the rules governing
information availability and circulation. In 2005,
the Institute carried out the preparatory phase of
the project by producing three reports entitledrespectively: Inventaire des outils et projets existants
en gestion des connaissances (Inventory of existing
tools and projects for knowledge management),
Proposition d’une stratégie pour un système de gestion
des connaissances et analyse du besoin (Proposalof a strategy for a knowledge management andneeds analysis system) and Faisabilité du projet decapitalisation: périmètre, architecture fonctionnelle
et organisation (Feasibility of the capitalisation
project: scope, functional architecture and organisation).

I R S N 2005 ANNUAL REPORT

[ 27

[

MANAGEMENT AND SUPPORT
Quality

Quality
The IRSN’s Certification project launched in the summer of 2003 is continuing withthe goal of obtaining ISO 9001 certification by 2007.The groundwork for the Institute’s
quality-based management system was finalised in 2005, allowing the developmentof macro-processes (which represent the Institute’s main lines of activity) and theprocesses comprising them.

Pilot external
and internal
communication

Define and pilot
the Institute’s
company project

Customer needs and expectations

M1

M2

Manageby quality

M3

M4

Provide technical support or assistance for public authorities

R2

Participate in managing crises and emergency situations

R3

Conduct missions of radiological monitoringof populations and the environment

R4

Carry out research to acquire knowledge, develop and maintainthe skills required to accomplish te Institute’s missions

R5

Meet the needs for expert assessments and studies expressed bycompanies and other society actors

R6

Formalize, promote and teach the know-how and positionsof the Institute

R7

Contribute to public information on radiological andnuclear risks

Manage humanresources andensure internal
communication

Ensure financial
and economic
management

S1

S2

I R S N 2005 ANNUAL REPORT

Assess and promotescientificexcellence

R1

IRSN process mapping.

28 ]> definition of both pertinent and realistic objectives,and indicators for appraising the achievement ofthese objectives;> identification of the critical points for the functioning of processes and definition of the related
control provisions.
The following actions were also carried out in 2005:> continued training and communication efforts,
mainly through conducting three half-day information seminars on quality-based management
at the Institute’s main sites, the start of a series of“how to be audited” training courses for preparing

Manageinformation
systems

Managecontracts

S3

Customer satisfaction

The development of the IRSN’s macro-processes
involves work on describing processes.This is highly
important inasmuch as the missions that they will
be used for will cover several divisions of theInstitute. It comprises the following three stages:> examination of all IRSN unit activities and thebreakdown of these into the Institute’s 17 macroprocesses (see diagram below);> identification of the interfaces between macroprocesses;> definition of the processes making up each macroprocess;Manage hygiene,
safety, working
conditions andenvironmental
protection
S4

S5

Manage property
assets andgeneral services

S6

IRSN Activities
standard NF EN ISO/CEI 17025, for the programmes 135
and 99-4.
The policy was pursued with a view to obtaining Cofrac
approval for the Steme as an “organiser of interlaboratorycomparisons” in 2006. To ensure that the criteria in thestandard were met in full, the laboratories dedicated tothis activity were reorganised, and special software formanaging interlaboratory tests was developed.
Following a blank audit in June 2005, the initial approval
application was filed with the Cofrac in July. This approval
will be the acknowledgement of IRSN’s organisation andtechnical skills in this field.

IRSN standards and intercomparison laboratory.

In 2005, the IRSN’s division for sample processing andenvironmental metrology (Steme) saw its “Cofrac Essais”
approvals renewed and acceptance of the requested
extension concerning the determination of uranium
isotopes in water, according to the benchmark fromagents for the certification audits, the circulationof a brochure to staff presenting the main aspectsof the “certification” project and a first edition of
the IRSN’s quality manual, and finally the circulation of a quarterly information bulletin for staff on
project progress;> on 30 November 2005 the drafting of an IRSN
management review, preceded by IRSN unit (divisions and departments) management reviews.
These reviews allowed the action plans for 2006
to be drafted at the different line management levels.
These plans cover the project phase, from the second
half of 2005 until the “blank” audit (autumn 2006),
which should be the opportunity to perform an overall
assessment of the new quality-based management
system prior to certification application.

[FOCUS]

Policy to achieve approval to
become an “organiser ofinterlaboratory comparisons”

Cofrac approval offers customers a guarantee of thequality of the services provided. As a signatory of theEuropean multilateral agreement relative to mutual
recognition of tests, calibration and certification andrelative to equivalent international agreements, the Cofrac
also opens the door to exportation.
These approval policies coincide with the IRSN’scertification policy. Indeed, the requirements regarding thecontent management system in standard NF EN ISO/CEI
17025 comply with the principles laid down in the
ISO 9001 version 2000 standard.

“QUALITY” AUDITS IN 2005

About 30 internal audits were carried out
at the IRSN in 2005, including seven crossdivisional audits. From now on, the audit
programmes will be developed so as to beable to audit each of the Institute’s 100
constitutive processes at least once overa three-year period.
Moreover, the training of new auditors
recruited in 2004 was virtually carried out
in full. Some have already taken part in
audits.

I R S N 2005 ANNUAL REPORT

[ 29

[

MANAGEMENT AND SUPPORTHealth and safety at work

Health and safety at work
Safety, working conditions and healthcare in the workplace are priority issues for the
IRSN. The Institute’s policy in this field, which was circulated to staff in May 2005(2),has been drafted into an annual prevention programme drawn up on the basis of anassessment of professional risks and analysis of changes to the legal and regulatory
framework.

Professional risks

Updating personal
exposure records

The identification and results from the assessmentof risks to which employees are exposed at theirworkstations were drawn up into a single document
for each IRSN site.
The assessment includes all risks and particularly
exposure to ionising radiation and carcinogenic,
mutagenic and toxic chemical products with respect
to reproduction. The unit managers are using thisdocument to set up prevention initiatives also
focusing on staff training, projects or the purchaseof personal protective equipment.

The risk assessment led the IRSN to update thecontent of employee personal exposure records toinclude information regarding accidental exposure.
This record allows the occupational physician tocarry out preventive medical monitoring tailoredto the specific nature of each workstation. As thisis kept in the employee’s medical file after departure,
it is also a way of creating a record of his/her professional exposure.

Fatal accidents

0 0
10 10 + 0

Occupational accidents reported to the Social Security
organisation resulting in work stoppage
Occupational accidents reported to the Social Security
organisation resulting or not in work stoppage

17 10 +7

Occupational accidents reported to the Social
Security organisation resulting or not in work
stoppage and minor accidents

39 10 + 7 + 22
Number of days lost: 115

Tf: 3.93

Number of hours worked: 2 545 220

Tg: 0.05

The national health insurance fund has defined two national indicators:• frequency rate (Tf): number of occupational accidents with work stoppage per one million of hours worked• severity rate (Tg): number of days lost per one thousand of hours worked

Pyramid of accidents occurring in the workplace at the IRSN in 2005.
(2) Brochure circulated in-house and published on the HSE intranet.

30 ]I R S N 2005 ANNUAL REPORTIRSN Activities
Upgrade of facilities:
investment of €4.9 million
in 2005
Work to upgrade facilities from a technical andregulatory standpoint was carried out in the facilities
most exposed to electrical risks and fire risks. In Le
Vésinet in particular, the conformity of electricalfacilities and ventilation systems in laboratories
measuring radionuclides in the environment was
upgraded.
Specialised entities carried out searches for asbestos
presence and analysed material condition. These
diagnostics led to the creation of technical “asbestos”
files and confirms the presence of asbestos inmost older facilities, which thus require monitoring,
withdrawal or containment operations to be carriedout.

Risk prevention
and first aid:
staff training
Over 2,000 IRSN employees received safety training
in 2005, reporting a rise of 64% on 2004, with agreater focus on first aid response in an emergency.
This general training was complemented by specifictraining on raising management awareness on theissues of health, safety and protection of the environment.

Comparison of frequency rates
Frequency rate

8
8

6,9

7,71

7

Branch of activity“Public-sector technicaland scientific researchestablishment”

6
5

Technical committee“Service activity I”(national level)

4,35

3,89

4

3,83

3,94

3,93

3

2,94

2
1

0

IRSN

2003

2004

0

2002

Comparison of severity rates
Severity rate

Technical committee“Service activity I”(national level)

0,4

0,36

-

0,35

0,29
0,3

Branch of activity“Public-sector technicaland scientific researchestablishment”

0,2

0,15

0,14

-

0,15
0,1

Radiation protection:
adapting to regulatory changes
The Institute undertook several initiatives toimplement the order of 31 March 2003 relating toworkforce protection. In particular, it appointed
radiation protection specialists to cover all of its
sites and set up a regulatory inspection programme
for its facilities and radiation sources carried out
by an approved body.The Institute set up protocols
to allow the radiation protection specialists andoccupational physicians to access results from staff
dosimetry tests recorded on the national SISERI
system.

year

2005

-

IRSN

0,03

0,03
0

0,05

0

2002

2003

2004

2005

year

Change in Tf and Tg at the IRSN
Frequency rate (Tf)Severity rate (Tg)

4,35
3,93

4

2,94
3
0,5

Preparing for incidental andaccidental scenarios

2

The IRSN has a system whereby management canbe informed on a 24-hour basis of any event occurringin the facilities and which may endanger personnel,
property or the environment of the Institute, andwhereby the relevant authorities can be duly
informed thereof.

1

0,03

0

0,03

2002

2003

2004

0,05

0

0

2005

year

I R S N 2005 ANNUAL REPORT[ 31

Setting up of a central health andsafety committee
The corporate agreement signed in May 2003 by
IRSN management and unions provides for the
existence of a central body composed of management and staff representatives. With its global
remit covering all sites in terms of health, safety
and staff working conditions, this body met for the
first time on 3 May 2005, thus fuelling the Institute’s
system for improving its results in environmental
safety and protection.

IRSN internal practice andprocedures: definition of
applicable rules[FOCUS]

On 25 May 2005, the management rolled out theInstitute’s internal practice and procedures, which
is a document defining the rules which employees
and staff must implement in terms of security.

The IRSN’s regulated facilities
and activities
Activities subject to the environment code
Facilities classified for environmental prevention (ICPE)> subject to authorisation: 10, nine of which are covered by sections
1700 (use or storage of radioactive substances).
> subject to declaration: 15, four of which are covered by sections 1,700
Nuclear activities subject to the public health code
Number of authorisations delivered by the DGSNR: 15
Employees exposed to ionising radiation> Category A: 110 (24 women, 86 men)
> Category B: 860 (336 women, 524 men)

32 ]I R S N 2005 ANNUAL REPORTInternal practice and procedures to define
the rules governing safety in particular.

Controlling the effects
on the environment
In this specific area, the Institute ensured that the
number of radioactive sources in its possession was
reduced to an absolute minimum in 2005, andthus eliminated 950 of the 1,000 sources not in use,
inherited on its creation.

Stricter security rules
for the ICPE and a reduction indangers at source
On 12 August 2005, the prefect of the Bouchesdu-Rhône department signed an order regulating
all the IRSN’s facilities classified for environmental
protection (ICPE) in Cadarache, previously operated
by the CEA. In addition to reinforcing the technicalrequirements in terms of risk prevention, thisorder requires a reduction in authorised releases
into the environment. Regarding the Fontenay-auxRoses site, the prefect of the Hauts-de-Seine
department requested a commitment to carryingout impact and danger studies in September 2005.

IRSN communication]

IRSN
communication
The IRSN’s action in this area can be broken down into two areas: external communication,
aimed at the public, with respect to which the Institute is focusing on a policy of
explaining what it does and describing its skills, and in-house communication aimed
at staff with the intention of nurturing common values.

External communication
The IRSN’s external communication policy
contributes to the Institute’s reputation. It also
involves raising awareness about its policy ofopenness with society and its viewpoint as anindependent expert.
The circulation of scientific information nurturesand strengthens the image of the InstituteAs the main vector for circulating information fromthe IRSN, the Internet is a key contributor to widening
the Institute’s reputation. Different theme-based
websites created by the Institute can be consulted
on its portal, www.irsn.org. The restructuring ofthese websites continued in 2005, mainly with aview to making them more ergonomic.
Moreover, the IRSN continued to publish for its
diverse readership in 2005, and this included theannual report offering a global overview of its
activities. Published in French (5,000 copies), English(1,500 copies) and in a bilingual multimedia version (7,500 mini-CDs), this report can be consulted
online via the Institute’s portal.
The Institute has also updated its presentation
document, 10,750 copies of which were circulated
in French and 11,400 copies in English.
The IRSN published several leaflets circulated at
professional trade fairs:> Face à un accident (When an accident happens,
1500 copies), Prestations dans le domaine nonnucléaire (Non-nuclear services, 1700 copies) and La
radioprotection (Radiological protection, 2400
copies) were circulated at the Pollutec trade fair.
> The following leaflets were circulated at the Medec
trade fair: Exposition médicale aux rayonnements
ionisants (Medical exposure to ionising radiation,
8,400 copies), Rayonnements ionisants et santé

Theme-based websites accessible fromthe main IRSN website.

(Ionising radiation and health, 6,000 copies) andAssister les équipes médicales (Supporting medical
teams, 4,500 copies).
Reinforcing visual identity
In 2005, the IRSN changed its visual identity by
developing a collection aimed at making its books
immediately recognisable to the public.

I R S N 2005 ANNUAL REPORT[ 33

IRSN Activities

MANAGEMENT AND SUPPORT[MANAGEMENT AND SUPPORTIRSN communication

In-house communication
This revolves around three areas:> in-house information;> awareness and dialogue;> building a common identity.
In-house information
The in-house information system for IRSN staff was
finalised in 2005. This is based on four tools:> the in-house magazine Repères;> in-house news flashes;> information points at the units;> the intranet.
A Repères readership survey carried out in 2005
confirmed the Institute employees’ interest in thispublication. The intranet was updated in 2005 toboost the number of connections by putting a seriesof practical new services online. This website is
helping to improve the efficiency of the Institutethrough better comprehension of its different
activities.
Awareness and dialogue
The IRSN management seminar and breakfast
meetings organised in 2005 were an opportunity
for IRSN employees to dialogue with their Director
General and to fully understand the policies adopted
by the Institute. Following these events, meetings
were organised between the communications
division and staff to present the Institute’s initiatives
in this area.

The Fête de la Science scientific festival.

34 ]I R S N 2005 ANNUAL REPORTExamples of theme-based collectionsedited by the IRSN.

Building a common identity
Several initiatives were carried out in 2005 topromote the building of an identity shared by
IRSN employees from their arrival. The humanresources and communications divisions offer new
arrivals a welcome package, show a film presenting
the Institute and propose seminars.
The personnel of the Institute is also invited to inhouse or external corporate bonding events suchas the Fête de la Science (Science Festival).

IRSN Activities[INTERVIEW]> How does the IRSN see its role in terms of external communication?
Through its communication and information initiatives, the Institute is aiming to boost the Frenchnation’s level of confidence (general public, professional community and the press) in theinstitutional expert assessment system for personal and environmental protection from risks related
to the use of ionising radiation. It can thus raise public awareness and enhance recognition by these
sections of society of its status as a public authority expert in nuclear and radiological risk.
> Which challenges are met by the Institute’s in-house communication policy?

Marie-Pierre BIGOT,IRSN Communications
Director

The IRSN is still a very young organisation that needs to consolidate its identity and culture. The
diverse nature of its personnel, their profiles, cultures and responsibilities is one of the Institute’s key
assets. The idea behind the in-house communication policy is to make this diversity a power
element. In this respect, compliance with the charter for using the IRSN logo and thecommunication charter are contributing to the gradual consolidation of the Institute’s identity andto its growing institutional and media presence.

I R S N 2005 ANNUAL REPORT

[ 35

[

MANAGEMENT AND SUPPORTHuman resources serving development at the IRSN

Human resources serving
development at the IRSN
The IRSN’s human resources policy offers a central role to the development of skills.
The key events in this policy in 2005 were the performance of major initiatives indifferent areas such as training, employee protection or the corporate savings
scheme, thus demonstrating the dynamic policy adopted by the Institute in terms ofhuman resources and social relationships.

Fully-fledged IRSN staff
Now that the period of CEA staff secondment to
the Institute is over (28 February 2005), the workforce is now composed exclusively of staff having
signed an IRSN work contract. The IRSN therefore
had 1,574 employees on permanent work contracts
at 31 December 2005, including staff seconded to
the DGSNR. The staff employed at the Institute’s
units represented 1,488.5 full-time equivalent
positions for a target workforce of 1,524 full-time
positions. Managerial staff makes up 68% of thisworkforce, with the remaining 32% in nonmanagerial staff. 56% of the workforce is composedof men and 44% of women.

Breakdown by gender56

44

Men 56% (55% in 2004)
Women44 % (45% in 2004)

2005: the finalisation of a host ofdebates and initiatives
Breakdown bysocio-professional categories

68

32

Ingeneers, researchers andmanagerial staff 68% (68% in 2004)
Non-managerial staff 32% (32% in 2004)

The management of human resources at the IRSN
is part of the Institute’s global policy. Accordingly,
a host of initiatives started the previous year wereconsolidated in 2005:> Expert Channel. The IRSN wanted to offer its
employees new motivating career prospects notably through the creation of Expert functions. The
missions of the employees involved should
significantly contribute to accomplishing theobjectives set out in the Institute’s scientific andtechnical policy and its recognition within theinternational scientific community. Some 20
employees were thus appointed to expert or senior
expert functions during the first series of
appointments carried out in 2005.
> Management. In 2005, the IRSN launchedManagement Workshops as part of restating thecentral role played by unit managers in implementing
the Institute’s strategy and motivating teams. In

36 ]I R S N 2005 ANNUAL REPORTIRSN Activities
2006, one of the key aims of this work is to set up
a training programme focusing on line management
responsibilities and a management charter officially
stating what is expected of managers.

Age pyramidOver
60 years

3%
4%

51 to
60 years

16%
15%

Annual interviews.A new development interview
system was implemented to give added drive tothese interviews.
>

41 to
50 years

20%
13%

36 to
40 years

23%
23%

Mission costs. A new reimbursement regime formission costs was implemented based on the principleof actual costs with an upper limit in 2005 to replace
the former fixed cost system, a legacy from the CEA.
>

31 to
35 years

18%
18%

26 to
30 years

14%
18%

Clearer human resourcesmanagement tools andprocedures

Under
25 years

7%
8%
0

25

50

100

> Recruitment. The human resources division
now systematically interviews the candidates
preselected by the divisions to offer directors advice
and a more comprehensive overview to help themin their decision-making process. This recruitment
process was used for the 122 employees recruitedby the Institute in 2005.

Social protection, payroll,elections, savings scheme:
a dynamic social policy

Mobility. Extending its scope in the scientificcommunity by developing its relationships with
French and international research bodies is a key
objective for the IRSN. In 2005, some employees
from the Institute thus joined outside bodies tocontinue on their career path.

The IRSN’s social structure and corporate agreements
offer a high level of protection for employees.
> Social protection for employees. The healthinsurance option adopted in 2004 in agreementwith the unions allows IRSN employees to benefit
from comprehensive coverage of healthcare fees
while paying lower health insurance contributions.

>

Men

Women

> Payroll. In 2005, payroll negotiations did notreach an agreement and took place against a backdrop
of considerable opposition by employees to themeasures proposed by the management with respect
to the 3% payroll scale set at the Institute. Similarly,
negotiations also focused on setting up a managerial
staff remuneration system adapted to the IRSN, anda new agreement to replace the previous CEA legacy
agreement was signed by two union organisations.
However, this new system could not be applied
given the oppositions from the three unions which
did not sign the agreement. A convention was also
to drafted into an agreement allowing the Instituteto dispense training in the fields of safety andradiological protection through its employees.

Recruitment interview between the humanresources division and a candidate.

> Elections. The bodies of the IRSN’s works council
and employee representatives were renewed for two
years in June 2005 and about 40 meetings were held

I R S N 2005 ANNUAL REPORT

[ 37

[

MANAGEMENT AND SUPPORTHuman resources serving development at the IRSN

over the year. With a budget of €1.15 million forsocial and cultural activities, the works council was
directly responsible for all of its missions.
> Employee savings scheme. By continuing toopen employee savings schemes in 2005, the numberof IRSN participating employees had reached nearly
30% at the end of the year. The Institute also
developed its 1% logement (accommodation aid)
policy and chose two partner collecting bodies toallocate rented accommodation or property loans
to employees. Finally, a direct loans system forpersonnel enabled about 15 employees to receive
financial aid to purchase property or a vehicle in
2005.

An increasing focus on training students
through research.

Encouraging young people: a risein the number of thesis students

Works council elections.

38 ]I R S N 2005 ANNUAL REPORTThe rise in the number of doctorate students
preparing their thesis at IRSN laboratories (66 at
31 December 2005 as against 58 the previous year)
is part of the Institute’s policy to develop training
through research. At 15, the number of young
post-doctorate researchers at the IRSN remained
stable in 2005. Moreover, out of 118 university
student trainees at the IRSN, 77 were at the end of
long-term scientific studies (French engineeringschool diplomas or the second year of a Frenchmasters’ degree). Finally, the IRSN welcomed 16
apprentices in 2005, mostly as part of technicaltraining at university level.

IRSN Activities
Professional training:
increased efforts
In 2005, IRSN training expenditure stood at about
4.5% of payroll corresponding to an estimated
42,000 hours with 2,100 employees participating.
The cost of teaching by training bodies thus rose
to about €1.33 million. Two key initiatives from2005:
> induction courses for new recruits allowing
them to take stock of the IRSN’s missions andobjectives and to dialogue with employees fromother units – 83 new employees took part in thisin 2005;> a training operation launched mid-year focusingon public speaking and aimed at the Institute‘smanagers.

Breakdown by domain of training
hours carried out in 2005

Economy, management 2.11% (2% in 2004)
Quality 3.59% (9% in 2004)
Information Technology 9.25% (13% in 2004)
Relations, communication,
management 12.21% (5% in 2004)
Safety, prevention 14.59% (10% in 2004)
Foreign languages 17.94 % (18% in 2004)
Technical sciences 40.31% (43% in 2004)

I R S N 2005 ANNUAL REPORT

[ 39

40 ]

I R S N 2005 ANNUAL REPORTIRSN Activities

[3]
IRSN
ACTIVITIESIRSN 2005 ANNUAL REPORT[ 41

Programmes to achieve
its missions
To optimise its performance in accomplishing its missions, the IRSN has organised its
activities into 31 thematic programmes, some of which cover a number of missions.
The activities connected with these programmes may therefore feature in several
missions. An overall view of each programme can be obtained by referring to the tableof contents at the end of this document.

RESEARCH AND
EXPERTISE IN THE FIELD
OF NUCLEAR RISKS
Human and organisationalreliability
PAGES
51
108

This programme encompasses all IRSN’s actions
concerning human reliability and the analysis oforganisations in the context of nuclear installations
or other situations involving exposure to ionisingradiation.
It thus responds to increasing demands by safety
and radiological protection authorities and provides
for changes connected with large-scale renewal of
operating teams and the evolution of skills, especially as regards technologies.

Safety analysis of PWRs andother reactors in operation
The IRSN ensures the follow-up of power reactors
and experimental reactors in operation, in supportof the safety authorities.The IRSN examines safety
data and files submitted by reactor operators inaccordance with regulations. It identifies andprioritises safety problems and analyses feedback.
On the basis of this follow-up, notices or reports
are drawn up in answer to questions from the safety
authority.

PAGES
100
to 105

Support for the safety analysis ofreactors in operation
The IRSN conducts R&D studies and actions regarding the safety of existing and future installations.
Its activities can be divided into three fields: thedevelopment of probabilistic safety analyses, thecarrying out of studies in support of analyses, andthe acquisition and development of software andrelated R&D.

PAGES
50
51
106
107

Ageing of pressurised
water reactors (PWR)
The ageing of nuclear power plants results in the
degradation in components, and this has to beprevented, monitored and counteracted so that the
installation can continue to operate in satisfactory
safety conditions.The research and safety analyses
conducted by the IRSN cover the various aspectsof the problem (ageing of components, study of the
behaviour of containments as they get older, andnon-destructive tests).
In this field, the Institute ensures that its appraisals
remain independent by carrying out its own work
which is complementary to that performed by theoperator.

42 ]I R S N 2005 ANNUAL REPORT

PAGES
51
52
108

IRSN Activities
operators to deal with them. The goal is to improve
prevention of these accidents, to study the resources
required to limit their consequences and to prepare
the IRSN for crisis management in case of an accident.

Safety of plants, transport anddismantling
Nuclear installations upstream and downstreamof the fuel cycle, and the transport of nuclear andradioactive materials, pose specific risks requiring
a great deal of work in providing technical support
for the relevant authorities and conducting studies and research, especially as regards the risk ofcriticality.This programme also concerns the safety
of installations during dismantling and mustspecify any possible means of improving thesafety of these operations, especially as EDF has
decided to step up its dismantling programme.

PAGES
60
to 62
111
to114
138
139

Fire, explosion and dispersion
Fuel and its management
in normal and accident
operating conditions
PAGES
52
to 54
109

For economic reasons, EDF wishes to extend theuseful life of fuels and is turning to new materials.
For these new operating conditions, the IRSN’s work
involves studies and research regarding the relevance of current safety criteria or the definition of
new criteria, assessing the corresponding safetymargins and improving knowledge.

This programme covers the IRSN’s activities in thefield of the control of risks associated with fire,
explosion and air dispersion of radioactive or toxic
contaminants within nuclear failities and in theenvironment. The aim of the studies, research andexpert assessments under this programme is tocontribute to improving the level of safety of
installations and thereby provide better protection
for the public, workers and the environment.

Future reactors andinnovative projects
PAGE
110

Severe reactor accidents
PAGES
56
to 59
109
to 111

Ventilation
network

The purpose of this programme is to enable theInstitute to identify and assess the safety problems
of projects that are being considered to replace
the current generation of nuclear power reactors.
The programme concerns generation IV reactors,
which are intended to achieve improvements insafety, reductions in waste and resistance toproliferation and malicious acts. In its early stages,
this programme relies on close contacts with thedesigners and R&D organisations involved.

The IRSN studies and research on pressurised water
reactor core meltdown accidents (severe accidents)
aim to achieve an adequate understanding of thephenomena in order to assess the risks associatedwith such accidents and the procedures adopted by

PAGES
65
to 68
117
137
141

High
efficiency
filters

Air outlet
Air inlet
Smoke

Electricalcabinets
Electricalcable trays

Smoke(soot and gas)

IRSN 2005 ANNUAL REPORT[ 43

NUCLEAR DEFENCE
EXPERTISE
Safety of defence-related
installations, systems andtransport
PAGE
150

The IRSN provides safety authorities with technical support for the safety assessment of military
nuclear systems, secret basic nuclear installations
and defence-related transport systems. Its activities
are focused on the expert assessment of safety
documents, the analysis of operating experience,
the assessment of internal emergency plans andon crisis preparation.

Protection against malicious acts
This programme is intended to take malicious acts
into consideration in the design and operation of
nuclear installations. It also addresses the assessment of potential consequences of any malicious
acts against transport containers for nuclear orradioactive materials.

PAGES
159
to 161PROTECTION OF MAN
AND THE ENVIRONMENTAGAINST IONISINGRADIATION
Environmental monitoring
The purpose of this programme is to be aware, at
all times, of the levels of radioactivity to which the
population is exposed, to determine their origin andto ensure the early detection of any abnormal
increase in ambient radiation fields in the various
environments.

PAGES
72
91
92
119
120
134
138

Radioactive waste management
safetyProtection and control of nuclear
and sensitive materials
PAGES
154
to 15844 ]The IRSN’s activities concern the assessment of thelevel of protection of nuclear materials against therisk of theft or hijacking for malicious purposesand compliance with France’s international undertakings regarding the utilisation of materials
which could be used to manufacture nuclear or
chemical weapons.
In this context, the Institute provides public authorities with direct technical co-operation (national
inspections, assistance with international inspections, operational missions) and gives technicalsupport to the administrative authorities (expert
assessment of dossiers, contribution to the drawing
up of doctrines and regulations).

I R S N 2005 ANNUAL REPORTThe aim of activities in this field is to assess the risks
associated with radioactive waste and, if necessary,
to identify possible means of improving their management with regard to safety and radiologicalprotection. The actions carried out under this programme concern:> the understanding of unused materials andsubstances, waste and packages;> the storage and disposal of radioactive waste
regardless of its origin, activity level and the radionuclides concerned;> the management of spent sources;> the contaminated sites.
These activities include the assessment of operators’
dossiers, the drawing up of technical doctrines, aswell as studies and research conducted in order tounderstand events that might affect the safety ofdisposal facilities.

PAGES
62
to 65
114
to 116139

Chronic risksThis programme contributes to assessment of theeffects of chronic exposure to low-level radioactive
contaminants.Although the risks are low for a given
individual, they apply to very large human populations and ecosystems, and this could lead tosignificant consequences on the global level.

PAGES
72
to 75

IRSN Activities
Enhancing their assessment may therefore offer
advantages for the purposes of health or environmental management.

Radioecology
PAGES
69
to 71
118
140
141

The research and studies conducted at the IRSN
contribute to the development of knowledge andunderstanding of the origin and the future ofradionuclides released or already existing in theenvironment.The aim is to assess their radiologicalimpact in normal operating, incident and accident
conditions. In operational terms, this entails making
crisis management plans in case of a radioactive
release, with the use of decision tools for theprediction of releases and their evolution, and therehabilitation of the environment near, and far
from, the accident site.

Radon
PAGES
75
76
120
121
134
141

For more than 20 years, the IRSN has been studying
radon in all its aspects: formation and migration in
the soil, exhalation and then dispersion in theatmosphere, metrology mapping, accumulation inbuildings, health risks, reduction of concentrations, etc. Having acquired knowledge and experience that are unmatched in France, the Instituteis able to provide support for public authorities
and parties responsible for implementing a radonrisk management.

Radiological protection ofworkers
This programme includes the IRSN’s actions regarding internal and external exposure of workers
inside, or outside, nuclear installations and at work
stations involving exposure to ionising radiation.
Its goal is to identify the most critical situations
and to analyse ways of reducing exposure.

PAGES
76
77
122
123
135

Radiological protection in
the medical field
Medical exposure is the main source of exposure
to ionising radiation of artificial origin for the general
population. This exposure can constitute risks forpatients and practitioners. This programme entails
three main topics:> study on delayed complications in patients treatedby radiotherapy;> monitoring of medical exposures;> medical expert assessment.

PAGES
79
80
123
124
143
144

Exposure assessment andprotection equipment
This programme aims to improve understandingof the exposure of individuals in normal situations
and to carry out dosimetric expert assessments incomplex situations in several areas:> expert assessment of radiological protectionand epidemiology of populations concerned;> dosimetry, routine measuring equipment;> dosimetry, measuring equipment underdevelopment.

PAGES
77
à 79
92
93
136
142
143

IRSN 2005 ANNUAL REPORT[ 45

Radiological protection
policyPAGES
86
87

The radiological protection policy is drawn upinternationally by various scientific, technical andregulatory organisations (ICRP, NEA, IAEA, Euratom,etc.).
The IRSN’s action as regards these organisations
concerns policy changes, the adoption of new topics
for study and the development of dialogue with all
French parties concerned by radiological protection.

HAZARDS AND CRISISSITUATIONSNaturally-occurring hazards
PAGES
68
69
117
118

The actions carried out by the IRSN are aimed atassessing the safety of installations with respect
to natural hazards such as earthquakes and floods
and at identifying any possible improvements.
This programme covers:> the risks of flooding and severe drops in waterlevels that could affect nuclear installations;> the development, optimisation and validation of
methods and tools to assess seismic hazards.

Management of emergency
situations
PAGES
126
to 130The IRSN’s facilities (technical crisis centre, mobile
facilities, etc.) are maintained in an operational
state and are constantly improved so that theInstitute can provide assistance to public authorities in the event of an accident or post-accident
situation in France. The Institute draws up contingency plans and takes part in crisis exercises. In
this way, its teams are trained in interaction withother players in the crisis, exercises are organised
on a national level and national or international

contingency plans are drawn up. Feedback in thisfield is a key factor in achieving progress.
This programme is made up of two parts:> studies and developments, crisis exercises;> maintaining the technical crisis centre and its
mobile facilities in an operational state.

Management of post-accident
situations
The post-accident management of a nuclear orradiological crisis may involve a large number ofplayers called upon, over the course of time, tomanage many interdependent tasks: radiologicalprotection and the follow-up of the health of
populations, rehabilitation of areas affected, redeployment of industrial and agricultural activities
and compensation for victims, etc.
The aim of this programme is to set up an organisation, methods and a range of technical tools,
along with a network of external contacts, to enable
all the stakeholders to carry out their missions
effectively.

Irradiation and contamination
accidents
Following an accidental exposure to ionising radiation, medical teams must be able to assess theinjuries suffered by the irradiated individual in the
shortest possible time in order to establish a reliable diagnosis and implement a suitable treatment
protocol. As a provider of technical support to hospitals, the IRSN’s objective is to improve diagnosis
by making optimal use of the interface between
dosimetry, biological research and medical
applications.

I R S N 2005 ANNUAL REPORT

PAGES
80
to 82

Radiological protection response
and assistanceThis programme covers:> activities involving inspections, tests and expert
assessments of the effectiveness of ventilationand filtration systems in nuclear installations;> assistance and response in the field of operational
radiological protection in order to characterise theradiological state of premises and sites and to assist
with the management of abnormal situations;> monitoring activities in accordance with thedecree regarding worker protection against thehazards of ionising radiation.
These activities are performed in accordance withagreements with the relevant public authorities.

46 ]

PAGES
82
83
130
131

PAGES
121
122
136
137
144
145

IRSN Activities
TRAINING AND
DISSEMINATION
Contribution to public
information and transparency
PAGES
94
to 97

As part of its missions, the Institute helps to provide
information to the public and public authorities
about nuclear safety and the protection of persons
and the environment. It publishes the scientificresults of its study and research programmes.
The IRSN is also seeking to make its expertise
responsive to the expectations of society.The Institute has undertaken a number of pilot projects toachieve greater transparency in the field of
nuclear and radiological risk management. These
projects, pursued in conjunction with social players,provide the basis for access to the IRSN’s analyses
and studies for Local Information Commissions.
Furthermore, the IRSN is working on steps to
involve stakeholders in pluralistic expert groups
with the aim of considering the technical issues ofcomplex and controversial topics.

Training and education throughresearch
PAGES
88
to 90

The IRSN’s knowledge base is formalised, enhanced and taught through its education activities.
The Institute sets up external and internal training
courses, participates in external teaching andprovides support for theses and work experience
periods. Furthermore, the IRSN’s policy of scientificand technical excellence aims to achieve the highest
possible level of scientific and technical merit in
all its research and study activities, and recognitionof that excellence.

International assistance, support
for programmes and agreements
The Institute’s international activities include:> bilateral relations with its foreign counterparts;> relations with international organisations;> special involvement in relations with European
institutions;> support for foreign safety authorities;> contributions to the international activities of
the French safety authorities.

PAGES
84
to 86
125
146
147

INVESTMENTS
Upgrading of
the CABRI installation
The upgrading of the CABRI installation involves
improving the earthquake resistance of the buildings and equipment, renovating the ventilation
system and installing a pressurised water loop to
replace the sodium loop. This installation will be
used, for the international CIP programme, to study
the behaviour of the fuel during a reactivity accident
in conditions representative of the core of a pressurised water reactor.

PAGES
55
56

AMANDE
This new installation produces monoenergetic
neutron beams of metrological standard needed
for the study and characterisation of neutron
detectors used for radiological protection. The
AMANDE project adds to the reference installations already operated by the IRSN and provides
it with references comparable with those available
at major international metrology laboratories.

PAGE
79

IRSN 2005 ANNUAL REPORT[ 47

Key figures 2005
Key figures 2004

14%: share of outside revenues for co-financing of research programmes
14%
Nearly 10,000 movements of sources recorded
6,200

38,000 samples taken in the environment
38,000603 persons received training in radiological protection provided by the IRSN
283

864,996 hits on the IRSN ‘s website
689,038

48 ]I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONSRESEARCH
AND PUBLICSERVICEMISSIONS
The research programmes conducted by the IRSN have several
objectives: to provide the skills required for suitable expertise in
the Institute’s fields of activity and to prepare the necessarychanges regarding the control of risks related to nuclear activities.
The IRSN is also responsible for public service missions suchas radiological protection monitoring and contributing to public
information and transparency.

50

Defining and implementing national andinternational research programmes

88

Contributing to training inradiological protection

91

Permanent monitoring in the fieldof radiological protection

94

Contributing to public informationand transparency

IRSN 2005 ANNUAL REPORT

[ 49

[

R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmes

Defining and implementing
national and international
research programmes
72 theses in progress(63 in 2004)

The research programmes developed by the IRSN are essentially applied research
programmes, including work related to basic research. They aim to develop knowledge
useful for expertise in the short, medium or long term. These research activities are
conducted through national and international co-operation, by welcoming thesis
students, developing programmes in partnership and setting up joint research units.

24 post-doctorates(16 in 2004)

42 holders of seniordoctorates or authorised
to supervise research(37 in 2004)

350 communications
at congresses(349 in 2004)31

current study andresearch topics(31 in 2004)

RESEARCH WORKSUPPORTING
THE SAFETY ANALYSIS
OF REACTORS IN
OPERATION
The IRSN carries out research and development action regarding the safety ofreactors in operation in order to developmeans of assessing programmed systems
and appraising the possibilities offeredby the development of non-destructive
test methods.

25

ICPE under theenvironment code
(26 in 2004)

10 current European

projects in radiologicalprotection and safety(8 in 2004)

50 ]In 2005, this work was focused on assessing thecover provided by tests with the GATEL tool, theverification of the design rules for multi-task
systems with the CHRONOSCOPE tool which wasdeveloped for a thesis, and the static analysis ofsource codes with the VALVIEWER tool.

Working in co-operation with the CEA, the IRSN isdeveloping non-destructive test simulation software packages. These are designed to ascertain
the condition of materials and so make surethere are no defects liable to adversely affect thesafety of the components concerned. The CIVA
software for modelling ultrasonic and eddy current
examinations enable the Institute to assess theperformances of inspections conducted, independently of the operators concerned.

authorised in accordancewith the public health code
(14 in 2004)

hosted(38 in 2004)

It is becoming increasingly difficult to assess thesoftware used in systems and command-control
equipment owing to their increasing complexity.
The IRSN is pursuing a sustained R&D effort todevelop analysis tools and to encourage operators
to improve, where applicable, the facilities andmethods they use to perform their own verifications.

Software for non-destructive
tests

15 nuclear activities

21 foreign scientists

Assessment of programmed
systems

The IRSN’s experts responsible for assessing
programmed systems.

I R S N 2005 ANNUAL REPORT

It can also be used to substantiate requests tooperators to make improvements to inspections.

RESEARCH AND PUBLICSERVICE MISSIONSIn 2005, the SIPA simulator (see Focus opposite)
was used for:> thermal-hydraulic studies, especially for the level
2 probabilistic safety analysis (PSA) of 900 MWe
reactors;> training in physics and reactor control;> the preparation of three national crisis exercise
scenarios.

Renovation of the SIPA 2 simulator[FOCUS]

SIPA simulator

RESEARCH ON
PWR AGEINGThe IRSN is working together with the
CEA to carry out R&D regarding themechanisms of degradation of equipment materials that are important forthe safety of nuclear installations.
Simulation of an accident scenario using SIPA.

FOCUS

In 2005, the main research topics were: wear on
mating parts, fatigue on pipes vibrating due to theeffects of flow, thermal fatigue in zones where two
fluids of different temperatures mix, and stresscorrosion. The general purpose of this research isto obtain better knowledge of degradation conditions or kinetics which are still little known or
unknown (see also Focus*).

p.52

RESEARCH WORK ON
HUMAN ANDORGANISATIONALRELIABILITY
The IRSN carries out studies on the operation and assessment of organisations.

Assessment of organisations
In 2005, the IRSN carried out research on the
integration of human factors in the design ofinstallations.After preparatory work in conjunction
with industrial partners, a study was conducted on
maintenance subcontracting and safety management. This work was the subject of theses.

After a year of thorough study, the SIPA simulator renovation
project was drawn up in 2005. This simulator is used to simulate
the behaviour of 900 MWe and 1,300 MWe reactors in accident
situations.
The IRSN and Framatome signed a contract, in December 2005,
to renovate their respective simulators together.
This contract defines the allocation of costs and the pulling of
the competencies required to carry out the project.
The SIPA 2 simulator has been operating at the IRSN since 1992
and its renovation became necessary owing to the obsolescenceof its computer hardware and increasing maintenance costs.
The project, which is to begin in 2006, includes the creation of
new simulation configurations for the 900 MWe, 1,300 MWe and1,450 MWe reactors by 2009. These configurations will becreated jointly by the IRSN and Areva NP with the support of
the Canadian manufacturing company, L3-COM-MAPPS,
for the supply of computer hardware and software.
In addition to providing greater flexibility in use, the new
simulator configurations will make it possible to simulate
the behaviour of all EDF reactors including, eventually, EPR.

I R S N 2005 ANNUAL REPORT[ 51

[FOCUS][R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmesInternational seminar on the impact ofageing on reliability

Fifty experts took part in the seminar on the impact ofageing on reliability.

The IRSN, along with the Dutch Institute for Energy, organised aseminar on the practical applications of age-dependent reliability
models and the analysis of data obtained through operating
experience. The aim of this international meeting was to describeand exchange experiences regarding the practical application oftime-related reliability models for components and systems.
Probabilistic safety analyses (PSA) are indeed being used more
and more to assess the safety of installations. However, the PSAs
usually used do not include time-dependent reliability models
for components and systems, and cannot assess the effects ofmaintenance on the reliability and availability of systems thatare important for safety.
The topics considered during this seminar included:> management of ageing and treatment of ageing effects in PWRs;> modelling of the ageing of components;> operating experience;> accelerated ageing tests.
Fifty experts from various countries and sectors (researchorganisations, safety organisations, industrial groups andconsultants) took part in this seminar during which 18 papers
were presented, including two by the IRSN.
For further information:www.energyrisks.jrc.nl/APSA/Workshops.htm
http://seminaire_apsa2005.irsn.org/index.php

Analysis of expert assessment
practices
In 2005, the IRSN began research, in co-operation
with the Ecole Nationale Supérieure des Minesde Paris (engineering school), to consolidate theavailable knowledge on expert assessment practices implemented in the field of human and organisational factors.

FUEL AND ITSMANAGEMENT INNORMAL AND
ACCIDENT OPERATING
CONDITIONSThe study of fuel behaviour, one of theresearch projects conducted by the IRSN,
mainly concerns the accidents of control
rod ejection, loss of coolant and dewatering of spent fuel pits.
In 2005, the IRSN carried out a new examinationof the safety criteria to be applied to fuel in normal
operation, incident-related situations and accident
situations. This re-examination became necessary
owing to recent changes in:> cladding and structural materials;> operating conditions, especially the increase infuel burnup fraction and fissile material enrichment;> knowledge acquired, especially through R&D
programmes, conducted by the IRSN or with its
participation, on fuel in normal and accident
operation.
This new examination will contribute to the input
for the preparation of a safety standard for future
fuel management systems. The conclusion ofthese studies will be presented to the Standing
advisory group for nuclear reactors in 2007 or
2008.

Control rod ejection
accidents
As regards control rod ejection accidents in particular,
the safety demonstration is currently based mainlyon the results of the CABRI REP-Na tests, a summaryof which is to be published in 2006.

52 ]I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONS

tests and for transposition to power reactor scale,has continued. This software models the behaviourof a fuel rod subjected to a sudden power change.
The main development introduced in 2005 was amodel to assess heat exchanges between a rod
cladding and the coolant in the test conditions
provided in the NSRR reactor.This development wasused to enrich the validation base for the SCANAIR
software.

In 2005, international co-operation for the new
CABRI International Project (CABRI-CIP) which
followed on from the CABRI REP-Na tests, led to atechnical seminar and the meeting of the Technicaladvisory group of experts.This group undertook the
preparation of the test matrix for tests to be carriedout in the pressurised water loop and which will be
the subject of detailed quantitative analyses. In thescope of this programme, the IRSN is examining thepossibilities of using the Japanese NSRR reactor,
operated by JAEA, to study the behaviour of thefission gases present in the irradiated fuel in caseof rapid heating. A researcher from the IRSN has
been seconded to the NSRR team.
Development of the SCANAIR software, used forthe preparation and interpretation of the CABRI

Loss of coolant accident (LOCA)

Phébus FPT1, [height] 0.50 mm
vrmax = 0.0193
vzmax = 0.6959

4968

Failure mode
Deformation
StressElongation
Temperature
Upper or lower

0.06

1600.01400.00.045

1200.01000.0

0.03

800.0
0.015

600.0

400.0

0
0

0.015

0.03

0.045

0.06

DRACCAR calculation of cladding deformation in the
Phebus FPT1 test.

The IRSN is playing an active part in the definition andinterpretation of tests in experimental programmes
concerning the behaviour of irradiated fuel during a LOCA,
which are being conducted in the USA (ANL), Japan (JAEA)
and Norway (Halden).

The first two of these programmes entail out-of-pile tests
on an irradiated fuel rod section extracted from a powerreactor. The principle of these tests consists in submitting
the rod section, initially featuring internal pressure, to asudden temperature change representative of thecalculated change for a fuel rod in a reactor. The aim is to
study its behaviour during the main accident development
phases: swelling and failure of the cladding, possible
displacement of the fragmented fuel into the swollen
regions of the cladding, high-temperature oxidation andhydridation of the cladding, and behaviour when wetted on
reflooding. These integral type tests are completed by a setof mechanical tests conducted at low temperature on new
pre-hydrated or irradiated cladding sections that have been
submitted to high-temperature oxidation. These tests canbe used to measure the residual mechanical characteristicsof the cladding in the post-accident phase during which therods may be subjected to various stresses (hydraulic,seismic, handling).
The tests in the 3rd programme concern a single rod.
They are carried out in the Halden test reactor and theirmain objective is to characterise the displacements ofirradiated fuel fragments inside the swollen regions which
form during swelling of the cladding.
The IRSN has drawn up a summary of all the successful LOCA
programmes conducted since 1973. In this way, theInstitute has been able to identify gaps in available
knowledge concerning the utilisation of fresh fuels with ahigh burnup rate. This work has also allowed theInstitute to offer its French and international partners an
R&D programme on LOCA focusing on those aspects.

I R S N 2005 ANNUAL REPORT[FOCUS]

Detailed modelling actions using recent methods
to predict clad cracking have been jointly financed
by EDF and Areva since 2005. They were used, in
2005, to defend a thesis on the modelling of crack
propagation in a rod cladding during a rod ejection
accident or a power ramp.

[ 53

[

R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmes

Loss of coolant accident (LOCA)
The IRSN has started studying the definition of
LOCA study guidelines which are to specify thefollowing:> the reference transient (large and/or small break)studied for the safety demonstration to justify theefficiency of the safety water injection system;> the physical phenomena to be considered;> the validity of the related safety criteria.

FOCUS

This action is being pursued in an international
context in which all the participants, including
US-NRC agreed to prepare a new approach basedon the results of R&D programmes in which the
IRSN has played a major part (see Focus*).

Development of the DRACCAR software has begun,
with the aim of modelling the deformations that
occur in dual rod assemblies in the event of a
LOCA, taking into account the thermal andmechanical interactions between rods. As existing
tools can only model a single “average” rod, this willoffer improvements for the interpretation of theexisting experimental base.
Transposition of the results to the reactor scale
will allow better evaluation of the deformations
occurring on the hottest rods during a LOCA. The
goal is to be able to assess the efficiency of corecooling during the accident in the short and longterms.

[FOCUS]

p.53

Spent fuel pit drainage accident

Fuel pit at the La Hague plant.

A R&D programme was started up at the IRSN in 2005 to
study the consequences of a spent fuel pit drainage
accident (a PWR spent fuel pit or a pit at the La Hague
reprocessing plant). Accidental drainage of the water inwhich the stored assemblies are located would lead to atemperature increase, occurring all the more quickly as thefuel’s residual power after irradiation in the reactor is high.
This temperature increase, intensified by direct exposureof the fuel rods to air (as the cladding oxidation reaction ismore exothermic by oxygen than by steam) could, in somecases, lead to cladding failures due to the internal pressurein the rods. These failures would then result in the releaseof fission products.

There remains a major uncertainty regarding theconsequences of the oxidation of zircaloy claddings by air.
The R&D programme comprises a first part for the study
and development of models which could be used to
calculate this type of accident. Another part concerns theperformance and interpretation of tests with different
effects with the aim of achieving better understanding of
the mechanisms of zircaloy cladding oxidation andnitridation in the presence of air. A third part, thefeasibility of which will be examined in 2007, concerns theperformance of semi-integral tests on assembly mockups inorder to obtain global information for the validation of themodels used. (see also Focus Risk of spent fuel pit drainage*)

FOCUS

p.102

54 ]

I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONS

Spent fuel pit dewatering
accident
The Institute is conducting an R&D programme
concerning accidents involving the dewatering of
irradiated fuel assemblies during handling or inspent fuel pits (see Focus left-hand page). In 2005,
this work concerned the study of a fuel assembly
dewatering accident during handling.

MODIFICATION WORKON THE CABRIINSTALLATION
The modification work on the CABRI
installation will make it possible toconduct tests in conditions that are
representative of those in a pressurised
water reactor. This work entails, inparticular, the setting up of a pressurised
water loop to replace the sodium loop
previously used to study the fuel of fastneutron reactors and, then, water reactors(previous REP-Na programme).
The research programmes conducted in the CEA’s
CABRI research reactor (Cadarache, Bouches-duRhône, France) on the behaviour of fuels highly irradiated during a sudden power change will make itpossible to collect experimental data on the effects
of an increase in burnup fraction on these fuels.
In addition to the work to install the water loop,
the installation’s safety will be upgraded. It is alsoplanned to renew some items of equipment. In
parallel, the IRSN is developing an instrumented
test device to receive the irradiated fuel rod sections
which will be tested. The international CABRI CIP
programme will comprise some 10 tests as from2009, at an average rate of three a year.

Work progress
In 2005, the vessel containing the essential components of the pressurised water loop (pressuriser,
pump, relief tank, etc.) was installed and the firstphase of the seismic upgrading work for the CABRI
pool-type reactor vessel was conducted.

Progress in studies
The studies on the representativeness of the
CABRI test device compared with the case of a

WHAT IS A SEVERE ACCIDENT?
A severe accident may be caused by a core water cooling fault,
preventing the power produced by the reactor from being
removed, even after shutdown of the chain reaction (residual
power). Over a period of between one and several hours, following
multiple human or equipment failures, degradation of the fuel andthen core meltdown may occur. Complex phenomena would thentake place and their impact would depend on the accident’s initialconditions and operators’ actions.
In the case of existing PWRs, the accident would comprise fourmain phases:> Due to the residual power, the fuels in the reactor core would
lose their integrity, hydrogen would be released due to oxidationof the claddings by steam, and fission products would be released
into the containment.

> If water was not injected into the reactor vessel, the core would
melt and the mass of molten material formed in this way(known as corium) would first attack and, then, perforate thevessel bottom head. In the specific case where the vessel is stillpressuring and in case of failure, the ejection of corium into thecontainment could lead to direct heating of the atmosphere in thecontainment. Furthermore, in case of advanced degradation, asteam explosion could occur. The containment could also be
subjected to the stress of an explosion of the hydrogen present(deflagration or detonation).

> Due to the effect of the heat released by the corium, the concretebase mat under the vessel could be damaged to the point of
perforation. This damage would also have the consequence of
releasing various gases which, along with the steam already created,would cause a gradual pressure increase in the containment.

> Some of the fission products (noble gases, iodine, caesium, etc.)
could escape from the containment if it was damaged as a resultof the stresses generated by the above-mentioned events orif the U5 emergency procedure was implemented (deliberate
decompression with filtration with the aim of limiting the pressurein the containment to a magnitude in the vicinity of its designpressure).

An accident of this type on the current PWRs could thus leadto considerable radioactive releases into the environment.

I R S N 2005 ANNUAL REPORT[ 55

[FOCUS][R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmes

ASTEC, backbone of
the SARNET network

The ASTEC software team.

Jointly developed by the IRSN and its German counterpart, GRS,
to simulate the whole of a severe accident in a PWR, the ASTEC
software has a central role in the development of the SARNET
network.
An initial summary of the assessment of the software’s
possibilities was drawn up in 2005. This work was carried out by
27 organisations by comparing calculations and results fromexperimental programmes with calculation results from accident
scenarios for PWR and VVER reactors obtained with othersoftware packages.
Some improvements in the modelling of the behaviour of fission
products were based on a consensus of opinions from network
specialists. These will be included in the software in 2006.
In addition, general specifications were drawn up in order toadapt the ASTEC physical models to other water reactors of the
BWR, CANDU and VVER types. In this way, ASTEC should become
the standard European software for the purpose of severe
accidents.

56 ]I R S N 2005 ANNUAL REPORTPWR were completed in 2005 in co-operation withSERCO, a British engineering services firm in London.
They demonstrate that the tests to be performedin the CABRI installation will be transposable to thecase of a reactor.
The national and international partners in the CABRICIP experimental programme met in 2005. The
conditions for half the tests in the programme havenow been defined.

RESEARCH WORK ON
SEVERE ACCIDENTS*
WITH CORE MELTDOWNIN A PWR
The approach adopted for this programmeis based on the definition of accident
scenarios, the identification of physicochemical phenomena, the conducting ofexperiments with separate effects forthe development of elementary mathematical models, and the developmentof computing software including thosemodels, and their qualification in morecomprehensive experiments.

Deployment of the European
SARNET network
The main purpose of this network is to optimise theco-ordination of the development of knowledge inthe field of severe accidents by pooling experimental
and modelling work. It was started up on 2 April
2004 in the context of the European Commission’s
6th FPRD. Co-ordinated by the IRSN, it involves 49
organisations from 18 European countries engaged
in research on the safety of nuclear reactors(safety organisations, universities, industrialists,etc.). In 2005, the deployment of the SARNET
network was continued and its first internationalseminar on severe accidents in water reactors,
entitled ERMSAR, was held from November 14 to
16 in Aix-en-Provence (France). This seminar wasattended by more than 120 participants. It finishedwith a review and discussion session on the future
directions and priorities to be assigned to SARNET.
These conclusions will be used to define the next
action plan for the network.

p.55

RESEARCH AND PUBLICSERVICE MISSIONSWith the aim of optimising the integration ofknowledge acquired through national and international programmes, the SARNET network established relationships with:> the Russian ISTC organisation, in order to takepart in the definition of research programmes regarding severe accidents in Russia;> the SOURCE TERM programme (see Focus opposite), whose test parameters are defined jointly andthe first results of which are being interpreted by
the network’s circles of experts;> the OECD’s GAMA group, in the context of which
an exercise to compare the results of computercodes on accident scenarios featuring reactor coredegradation is being led by the IRSN.
Public information regarding the network is available
on the www.sar-net.org website that has been inservice since early 2005.

ERMSAR 2005 IN FIGURES
Participation:> 120 specialists;> 50 organisations, including 12 byinvitation (4 electricity utilities, 4 safety
authorities, 3 research organisations and1 university);> 19 countries including 3 outside Europe(Canada, South Korea, Russia).

Start-up of the SOURCE TERM programme[FOCUS]

The feedback from the 27 organisations in the
ASTEC software user network (see Focus left-handpage) was integrated in version V1.2, delivered inJuly 2005. In particular, it led to an improvementin the software’s robustness. Some 20 circles ofexperts from the network have continued theiranalysis in fields of interest in terms of R&D, theinterpretation of tests and the construction ofmodels. A prioritisation method was drawn up andimplemented in order to update the priorities definedin 2003 in the context of the EURSAFE project(3) on
which the network was based when it was started
up.

The BECARRE installation.

The IRSN started up a new research programme called SOURCETERM in 2005. The objective of this five-year programme is to
reduce the uncertainties inherent in the assessment of releasesof radioactive products into the environment in the case of acore meltdown accident in a water reactor. Conducted in Francein partnership with the CEA and EDF, this co-operative research
programme has received international backing and is to be
jointly financed by the European Commission, the Paul Scherrer
Institute in Villigen (Switzerland), the AECL research organisationin Canada, and US-NRC (USA).
This experimental programme covers four fields of investigation:> the chemistry of iodine in the reactor primary coolingsystem (CHIP tests) and in the containment (EPICUR tests);> the effect of air on the degradation of fuel elements, especiallyon the oxidisation of claddings (MOZART tests)> the release of ruthenium, and its chemical behaviour in thecontainment;> the effect of the degradation of boron carbide control rods onthe development of the accident and on the corresponding effecton radioactive releases (BECARRE tests);> releases of fission products from irradiated fuels (UO and MOX).
2
The year 2005 was marked by the inauguration of the EPICUR
installation in May, followed by the performance of the first tests
in that installation and, finally, the conducting of MOZART and
BECARRE tests.

(3) European project of the 5th FPRD which aims to prioritise the needs toacquire new knowledge in the field of severe accidents.

I R S N 2005 ANNUAL REPORT[ 57

[FOCUS][R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmes

PHEBUS programme:
first results of the FPT3 test

Storage of PHEBUS samples.

In 2005, non-destructive measurements (radiography,
tomography, γ spectrometry) were performed on the test device
and aerosols and vapours sampled during the PHEBUS FPT3 test
(conducted in 2004) were analysed.
Measurements of γ emission from 320 aerosol samples collected(sampled by filtering or sedimentary deposits) will be used in
the various test phases to quantify the releases and deposits offission product aerosols and vapours (including organic iodine
and molecular iodine) in the systems and the tank simulating
the primary cooling system of a PWR containment.
The profiles for γ emission, x-ray densitometry and γ and x-ray
tomography for the test device confirm that the objective ofmoderate degradation of the fuel (limited melting of the fuel)was achieved. The first interpretation calculations, performed
using the ICARE 2 software, successfully reproduced the thermal
state of the fuel assembly during the test but underestimatedits final state of degradation.
This could be due to inadequate modelling of the effect of
the control rod boron carbide.

Studies and research conducted
on severe accidents by the IRSN
in 2005
Core degradation and behaviour ofthe corium in tankThis accident phase is being studied at the IRSN
using the ICARE/CATHARE software developed by
the Institute. In the context of the level 2 PSA that
it is developing for 900 MWe reactors, calculationsof new accident sequences were performed using
version 1 of the software to study the breaks causedin the primary cooling system, especially on thesteam generator tubes in the case of core meltdown
under pressure.
Major advances in development were achieved toprepare version 2 of the software. This version will
be delivered in 2006 to perform calculations for the
reflooding of a degraded core in the context of thelevel 2 PSA conducted by the IRSN for 1,300 MWe
reactors. The new version will make it possible toprocess thermal-hydraulics and movements ofmaterials in the core in two dimensions. Other
improvements were achieved in 2005 on themodelling of radiation phenomena in the core andon the oxidation of rod claddings in air.
On 17 and 18 November 2005, the IRSN organised the second international seminar of the
ICARE/CATHARE software users’ club in Aix-enProvence (France). This seminar attracted some 30
participants, including 15 from foreign organisations. On the basis of all the accounts given, acomplete overview of the advantages and limitations of the current version V1 was drawn up andthe enhancements expected of V2 were identified.
Behaviour of fission products
In recent years, the study of the behaviour of fission
products at the IRSN has been closely linked to thedevelopment of the international PHEBUS-FP
programme. In 2005, processing of the first resultsof the last FPT-3 test carried out in 2004 was started(see Focus opposite).
Research on the behaviour of fission products duringa core meltdown accident will be continued in thecontext of the SOURCE TERM programme (see
Focus*).

FOCUS

p.57

Containment strength
The main aim of studies in this field is to fully
understand the risk of early and direct releases ofradioactive products into the environment.

58 ]I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONS

Review and prospects of the
SERENA programme of OECD-NEA
Furnace
5 kg
Moltenfuel

Furnace
20 kg
Moltenfuel

Testsection
VesselVessel

Water
level

Window
Water
level

Detonator

Detonator
KROTOSTROIKROTOS and TROI: two complementary installations
for the study of steam explosions.

FOCUS

p.56

The RECI (RECombiner and Iodine) programme was completed in
2005. The aim of this IRSN programme was to improve theknowledge available on the behaviour of fission products ina nuclear reactor containment in case of a severe accident.

[FOCUS]

Summary of the RECI programme

The RECI experiments revealed physicochemical reactions
generating volatile iodine by dissociation of solid metal iodides.
These reactions may take place when these iodides are heatedinside hydrogen recombiners when in operation.
Owing to the very small scale of the analytical experiments in
the RECI programme, the results obtained for caesium andcadmium iodides cannot be directly extrapolated to the case ofa reactor.
However, they can be used to scale an experimental facility
that is more representative of actual situations and alreadymake it possible to obtain a first estimate (using the IODE
module of the ASTEC software) of the impact of hydrogencatalytic recombiners on iodine releases.

The leading international experts in the field of steam
explosions joined the SERENA programme, conductedfrom 2001 to 2005, to assess current understanding of thephenomena and the computing possibilities provided bydigital tools. The IRSN participated in this programme with
its MC3D software, in partnership with the CEA.
There are real differences of appreciation as regards thevery nature of the phenomenon. Furthermore, thescattering of calculation results obtained using various
software packages show that substantial efforts are stillrequired in order to achieve a better understanding of the
explosion phase.
The CEA and the IRSN, in co-operation with the Korean
KAERI and KINS institutes, proposed a second study phase
based on the KROTOS (CEA) and TROI (KAERI)
experimental programmes in order to better define theconsequences of a steam explosion for fuels and situations
representative of reactor cases.

I R S N 2005 ANNUAL REPORT[FOCUS]As regards hydrogen explosions, the developmentof the TONUS software database was completed
in 2005. Experimental actions conducted incollaboration with the CNRS in Orléans (France),
were carried out in order to refine the flame acceleration criteria and improve the prediction of thetriggering of detonations.
The last spraying tests in the experimental TOSQAN
programme were performed in 2005 and theinterpretation of their results was started. These
tests will be used to qualify predictions by the
TONUS-CFD and ASTEC/CPA software regarding
the distribution of hydrogen and changes in pressurein the containment. Two of them are being used
for reference for an international exercise to compare
software packages.An experimental programme on
direct heating of the containment atmosphere,
conducted in collaboration with the German FzK
research centre in its DISCO installation, wassuccessfully completed. The results will be used to
improve the ASTEC/RUPUICUV software models
and to enhance the assessment of the consequencesof corium ejection under pressure into thecontainment.
As regards the risks of steam explosion (see Focus
below), version V3.5 of the MC3D software wasdelivered. It reflects feedback from the software’s
users and the most recent assessment works.

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Defining and implementing national and international research programmes

SAFETY OF
LABORATORIES,PLANTS, TRANSPORT
AND DISMANTLING
Study and research work in this field
concerns, in particular, the risks of criticality and dispersion of radioactive
materials outside containments.

Criticality studies, research anddevelopments
The studies conducted to assess the criticality risk
rely on computing software packages which use
nuclear data libraries (cross sections).These software
packages must be able to solve neutronics problems which differ greatly from one to the otherowing to the diversity of fissile media encounteredand the geometry of their containing equipment.
The Institute is developing a 3D multigroupneutron transport simulation software, known as
MORET 4. Based on the Monte Carlo method, thissoftware is a major component of the CRISTAL
criticality computation package. In 2005, the IRSN
studied the possibility of using other specific or
multigroup nuclear data libraries and carried out
work with the aim of reducing computing uncertainties through the improvement of statisticalmethods used and improving the detailed analysis
of calculation results. Some work is being carriedout in the context of OECD/NEA supervised cooperation.
Criticality software packages are qualified bycomparing calculation results with experimental
data. It is for this reason that experimental criticality studies are being carried out in the context
of national or international partnerships. These
consist in setting up full-scale configurations withperfectly well-known radiochemical and geometriccharacteristics that are very close to the criticalstate. These experiments are then simulated by
calculation. Calculations and experiments are thencompared in order to assess the accuracy of thecriticality software and to determine the margins
of error to be adopted for criticality studies.
In 2005, the qualification of the MORET 4 software
covered more than 1,300 experimental cases.
Further experimental programmes conducted by

60 ]I R S N 2005 ANNUAL REPORT

the IRSN were started in 2005 (see Focus righthand page).
In the context of the optimisation of operations
downstream of the fuel cycle in the USA, the aimof the US Department of Energy (DOE) is to validate
a computing method which would allow spent
fuel assemblies to be transported and stored more
densely. Complex criticality calculations are required in order to demonstrate the safety of thisdensification.
In this context, the IRSN provided DOE withexperimental results to validate criticality computer codes, taking into account the decrease inreactivity of the fuel assemblies after passing througha reactor (burnup credit). This experimental
programme was conducted in the CEA’s installations
at Valduc with co-financing by Cogema and the
IRSN (see Focus right-hand page). In addition, theInstitute continued its participation in theinternational ICSBEP project in 2005. This project,under the auspices of the OECD/NEA, pools theresults of criticality experiments conducted
throughout the world for the qualification of

CRITICALITY RISKThe criticality risk, i.e. the risk of accidental
triggering of a neutron chain reaction, exists
at every stage of the fuel cycle (enrichmentof uranium to form uranium 235, storage,transport, recycling of substances obtained
after spent fuel reprocessing, disposal ofwaste products).
A criticality accident involves a releaseof energy, essentially in the form of heat,accompanied by intense neutron andgamma radiation emissions.
Criticality risk prevention entails
determining the conditions in whichsubcriticality can be ensured during
operations involving fissile materials. In
addition, in order to ascertain the possible
consequences of a criticality accident, the
IRSN is carrying out studies and research inorder to provide efficient computing tools
with the highest possible degree of
qualification.

RESEARCH AND PUBLICSERVICE MISSIONSThe Institute’s research and development activities
also include the acquisition of knowledge and thedevelopment of skills in order to allow for the burnup
fraction in criticality studies. This is a feature of
the new 1.0 version of the CRISTAL package which
the Institute delivered to users in 2005.
In co-operation with EDF and the CEA, the Institutebegan, in 2005, processing the results of the experiments in the international REBUS(4) programme
conducted by SCK.CEN (Mol) and BELGONUCLEAIRE
in the VENUS installation at the Mol centre in
Belgium.This work will show whether the reactivity
effects due to irradiated PWR type UO 2 rods inexperiments for the REBUS programme are sufficient to contribute to the qualification of criticality software.
In the field of critical accidents, the Institute carriedout studies in 2005 concerning the consequences
and possibilities of response in case of a criticality
accident affecting transport containers. In addition,
the co-operation that began in 2004 with Imperial
College, which provides technical support on suchmatters to the British safety authority, continued
in 2005 with counter calculations of reactivity
transients representative of future experiments on
plutonium solutions (planned in 2006) for comparison with the computing models (see Focus
opposite).

Dispersion of radioactive or toxic
materials outside containments
The IRSN is carrying out studies and experiments
in relation to various foreseeable accident situations to support the assessment of the risks ofdispersion of radioactive or toxic materials outsidecontainments. Work aimed at experimentally
characterising the dynamic containment of a
glove box in an accident situation has increased therange of results previously acquired as regards gas
and aerosol transfer coefficients. It was thus shownthat the containment’s effectiveness features aminimum value depending on the flow rate, corresponding to the opening of a glove or bag port (failureof static containment). On the basis of the results

Experimental criticality
programmes 2005-2008[FOCUS]

criticality software. The IRSN presented its workon the reassessment of experimental data, fromformer criticality experiments, regarding annularcylinders containing plutonium solutions with orwithout the presence of solid “neutron poisons”.

Experimental device at Valduc for the performance of
criticality experiments.

In 2005, an experimental device using low-concentration
plutonium solutions was prepared and erected in the CEA’s“Appareillage B” installation at Valduc, Côte-d’Or (France). The
purpose of this device is to obtain experimental measurementsof the effect of temperature (which may be positive) in the caseof plutonium solutions of 15 g/l to 20 g/l. The experiments areplanned for 2006.
In addition, a programme was started in 2005 in collaboration
with two American laboratories in order to conduct criticality
experiments in the IPPE BFS reactor in Obninsk (Russia) for ISTC.
The objective is to carry out critical experiments representing
industrial configurations using MOX type fissile materials.
Studies on the impact of uncertainties affecting the nuclear data
for these environments will be conducted in the context of theexperiments.
The IRSN gave CEA confirmation, in 2005, of its intention to use
the “Appareillage B” installation at Valduc to conduct anexperimental programme to qualify the neutron characteristicsof the components of structural materials (steel, concrete,
zirconium, aluminium, etc.). Owing to their ability to absorb
neutrons, these materials are increasingly taken into account incriticality studies concerning transport, storage and disposal
situations. The detailed design of the experimental device will becompleted in 2006.

(4) REActivity tests for a direct evaluation of the burnup credit on Selected Irradiated LWR fuel bundles.

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Defining and implementing national and international research programmes

acquired, the concentrations of pollutants liable to
be inhaled by an operator in such degraded situations can be assessed.
The work aimed at assessing transfers of radionuclides through cracked concrete were continued
and tests on the retention of aerosols in dry air ina concrete wall were completed. Furthermore, afeasibility study on tests with an air and steam flow
was conducted in 2005.The tests will be carried out
in 2006.
The IRSN completed its experimental facilities forthe characterisation of filters with the commissioning of a CATFISH test bench in 2005. This bench
will study the effects of humidity on the clogging
and efficiency of filtration with flat filter media andindustrial folded filters. Preliminary tests werecarried out to qualify the installation’s performances
and a multiannual research programme was started.
Furthermore, the multiannual programme on theeffects of wind on accidental releases was continued with the performance of wind tunnel tests
on mockups representing nuclear installations.The
design of an installation mockup with an internal
ventilation system was also studied, to be used forwind tunnel tests for various accident scenarios.

RESEARCH WORK IN
THE FIELD OF WASTE
In the field of waste, the IRSN mainly
focused, in 2005, on drawing up a summary of research achievements in geological repositories for high-level longlived (HLLL) waste and completing specificstudies in order to prepare its report on
Andra’s Dossier 2005 Argile. This report
was put forward to the Standing advisorygroup for radioactive waste long-term
disposal facilities in December 2005.
The work carried out included the development ofdigital models and their validation by means oflaboratory or field tests. Field tests were carried out
in the Tournemire experimental centre (Aveyron)
installed by the IRSN in a former railway tunnel
excavated in a thick clay layer. The similarities
between the Tournemire clay (argillite) and the rockstudied by Andra in its Bure laboratory (Meuse)mean that the IRSN can use this tunnel to carryout studies that are not only methodological but
also phenomenological. Tests were also carried out

Research on surface
contamination of radioactive
material transport packages
Since 2001, the IAEA has been supervising a “coordinated research project” regarding non-fixedsurface contamination on radioactive materialtransport packages and vehicles. The aim of thisproject is to assess the validity of the current surface
contamination limits (0.4 Bq/cm2 for alpha emitterradionuclides and 4 Bq/cm2 for gamma, beta or alphaemitter radionuclides with low radiotoxicity) andto update them if necessary. In the context of thisproject, the IRSN played a part in establishing
scenarios for exposure to radiation resulting fromthe presence of surface contamination on packages
and transport facilities. It also calculated the doses
incurred for workers and members of the public foreach of the 350 radionuclides included in the IAEA
transport regulations, on the basis of a model
prepared by one of the project’s focus groups.
Notably, the Institute considered that the resultsof these calculations did not call into question thecurrent surface contamination limits.This work was
published by the IAEA in a summary document,
IAEA-TECDOC-1449, in June 2005.

62 ]I R S N 2005 ANNUAL REPORT

Inserting instrumentation intoa borehole.

RESEARCH AND PUBLICSERVICE MISSIONS[FOCUS]in the experimental tunnel used by Nagra (theSwiss counterpart of Andra) in the argillaceous
medium of Mount Terri (Switzerland) in collaboration with Andra.

Characterisation of disturbances
caused by rock excavation

Experiments on diffusion andretention of radioactive species

Characterisation of excavationdisturbed zones

FOCUS

p.63

The IRSN started an exercise to model the zones
disturbed by excavations (EDZ) around theTournemire structures in 2004 in the context of theinternational DECOVALEX project. In 2005, an EDZ
characterisation campaign by means of radial
boreholes around the structures was set up (see
Focus*). The Tournemire site, which has structuresof very different ages (one year, nine years and 110
years old), offers the possibility of studying changes
in the disturbed zone over long periods. In 2006,
the characteristics determined on site will becompared with results obtained by modelling.
Furthermore, programmes for the digital simulation of the reaction of the rock to excavation wereprepared in 2005 in the context of the European
NF-PRO project (6th FPRD). They are to be used tointerpret the results of the measurement of displacements, deformation and interstitial pressuresobtained in 2004 in the context of the same projects
for a mine-by-test operation (excavation in instrumented rock to monitor the rock’s hydromechanical reaction).

0.66 mMD2

Gallery 2003

N

S
1.6 m

Petrophysical on samples
Gas permeability in boreholes

D4
M

Multiannual experiments on the diffusion ofradioactive or stable tracers are being set up at
Mount Terri with the purpose of obtaining a better
understanding of the behaviour of radionuclides
and quantifying the effects of the rock’s anisotropy
on diffusion. In 2005, the experimental “niche”
was excavated and its instrumentation was installed. The borehole will be equipped with adevice with three blanking plates isolating two
diffusion chambers. In the first chamber, highlyinteractive tracers will come into contact with therock to study their diffusion. Tracers not fixed by
the rock on the site will go into the second chamberwhere the effects of the anisotropy of the environment will be studied.
The introduction of the tracers is scheduled for 2006
and the decrease in the concentration of tracers in
the chambers will be continuously measured until
2009.

Extension of the desaturation zone around the gallery excavatedat Tournemire in 2003.

Investigations were conducted in 2005 to characterise the damage
to the rock around the underground structures of the Tournemire
centre. Indeed, excavations disturb the rock, creating a damaged
zone which is then liable to constitute a preferential migration pathfor radionuclides.
Geological observations and measurements on site and on sample
cores (for changes in water content in the rock, hydraulicconductivity and speed of ultrasonic waves) were conducted bymeans of radial boreholes around the structures.
This work showed that the extension of the damaged zone remains
limited to a ring situated between the wall and a distance ofbetween 0.2 and 0.25 times the structure’s radius.
The investigations carried out show, however, that the spatial distribution of the damage intensity and the orientation and density of
the cracking caused vary according to the age of the structure. This
could be the result of damage due to a combination of various basic
physical mechanisms, such as the desaturation of argillite ordeferred deformations. The detailed interpretation of these investigations and their comparison with the results of modelling operations will be continued in 2006 in the context of the international
DECOVALEX and NF-PRO projects.

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[FOCUS][R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmesContinuing the Common interest
programme (PIC) on fires

Device for PICSEL_C tests under the SATURNE hood.

The PIC-Feux project (2003-2008), conducted in co-operation
with Areva, includes in particular the PICSEL programme to study
fires in electrical cabinets that could affect an installation withseveral ventilated rooms (clogging of very high-efficiency filtersby smoke, disturbance of negative pressure levels in premises,etc.) as well as equipment containing radioactive material (glove
boxes, bins, etc.).
The PICSEL_C tests for the study of the degradation of glove box
equipment (gloves, glove ports, etc.) and waste drums subjectedto thermal radiation simulating the effects of flame wereconducted in 2005.
In parallel, the results of the PICSEL_A tests, carried out in 2004
to characterise an electric cabinet fire in an open environment wereanalysed. The programme was pursued in 2005 with theperformance of one of the tests in the PICSEL_F series to study
an electrical cabinet fire in a confined and ventilated location in the
DIVA installation.
Furthermore, the clogging of filters by aerosols produced by fires
fuelled by solids is being studied in the BANCO installation at
Saclay. In 2005, special instrumentation was used to correlatechanges in the air resistance of filters with respect to thecharacteristics of the primary particles comprising the
combustion aerosols and the air flow conditions.
The empirical air resistance model previously constructed forthe combustion of solvents can thus be modified forthe combustion of solid materials such as those present
in electrical cabinets.

64 ]I R S N 2005 ANNUAL REPORT

Modelling the behaviour ofa repository
In 2005, the IRSN continued working on modelling
techniques to assess the containment capacities
of geological repositories, taking into account thevarious barriers envisaged in the design options
adopted by Andra in the Dossier 2005 Argile.
Studies were conducted in order to describe, inparticular, the mechanical and chemical behaviourof a radioactive waste repository and the possibilities of transfer of radionuclides to the surface
through the host layer and the more permeable,
upper porous horizons.The hydrogeological modellings of the Paris basin and the Meuse/Haute-Marnesite were updated. Prospective modelling exercises
were carried out on flow modifications due toplausible climatic variations.
The MELODIE computer code was used to assess
the containment capacities of a possible repository in the Callovo-Oxfordian formation, such asenvisaged by Andra in its “clay” file (Dossier 2005
Argile), for operating situations classified as “normal” (probable) or “altered” (incident-affected).
In 2005, the IRSN played a part in preparing the two
European projects for the 6th FPRD: PAMINA andMICADO dedicated, respectively, to computing
methods and tools to assess the long-term performances of a deep repository and the influence of
uncertainties regarding the radiological content ofwaste fuels on the overall safety of a deep repository.
Finally, in 2005, an agreement on technical cooperation regarding the exchange of experience
concerning the utilisation of the MELODIE code
was signed between the IRSN and AVN (Belgium),
which provides technical support to the Belgium
nuclear safety authority. This was a first concrete
result of the approach for the outsourcing of the
MELODIE code, adopted by the Institute in 2004.

RESEARCH AND PUBLICSERVICE MISSIONSThe IRSN’s research in the field of fireconcern the study of the behaviour of afire in a confined and ventilated environment: fire propagation and consequences,
smoke propagation to other premises.
In the field of the air dispersion of pollutants, the Institute is continuing its workon controlling the containment of radioactive or toxic materials, reducing theuncertainties involved in assessing
releases and their dispersion and, above
all, assessing the human and environmental consequences.

Research programmes
The experimental approach offers the means ofextending knowledge of the specific physicochemical phenomena of fires and to supplement
the database needed in order to develop and thenvalidate models related to these phenomena.Thesemodels are then introduced into the computation

Setting up the PRISME
experimental programme

Flame in the PRISME SOURCE S2 test under
the SATURNE hood.

software used to carry out studies to support theassessment of fire protection measures. Some
programmes are carried out in collaboration withindustrial partners, such as EDF or Areva, and are
the subject of exchanges with other national andinternational organisations, such as INERIS, universities, US-NRC, etc.
The Common interest programme on fires (PICFeux), conducted by the IRSN in collaboration with
Cogema and Areva, continued in 2005 with theperformance of several tests in the IRSN installations
at Cadarache (Bouches-du-Rhône) and Saclay(Essonne) (see Focus left-hand page).The preparationof the PRISME programme continued with theperformance of studies and the drawing up of
knowledge status reports. The general purpose of
the PRISME programme is to study in the DIVA
installation the propagation of smoke and hot gases
between rooms via doors or a ventilation system.
This programme was successfully internationalised through the OECD (see Focus*).
Research on the modelling of the development of
the power evolution of a fire fuelled by solid materials according to their chemical composition, theorientation of the fuel plate and the air flow in thevicinity of that plate were continued in the context

FOCUS

p.65

The PRISME research programme, dedicated to the studyof the propagation of smoke and hot gases produced bya fire in a ventilated installation comprising several
premises, was presented, in the second quarter of 2005,
to fire risk experts from 10 OECD countries (Germany,
Belgium, Canada, South Korea, Spain, Finland, Japan,
Slovakia, Sweden and the United States) at a meetingorganised by OECD/CSNI.

[FOCUS]RESEARCH WORK IN THE
FIELD OF FIRE AND AIR
DISPERSION

The possibilities offered by the DIVA installation, in which
the tests are to be performed, aroused much interest as
witnessed by the fact that practically all these countries
joined the programme. In return for co-financing,
they will take part in the precise definition of theexperimental conditions and will have access to theresults. On the French side, EDF and DGA will be partners
in the programme. Scheduled to take place between 2006
and 2010, the programme will start up with a first test
campaign called “PRISME DOOR”. It will aim tocharacterise the transfers of heat and material via a door
separating two rooms, one of which contains a fire.

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Defining and implementing national and international research programmes[FOCUS]of a thesis. The first test results were obtained in2005 using a specific device located under the hoodof the SATURNE tower in Cadarache. Two basic
research topics regarding aerosols produced during
a fire were also pursued in the Saclay installations:
identification of the mechanisms placing volatileand non-volatile airborne contaminants in suspension, and characterisation of the soot emitted,

Development of the ISIS softwarein terms of morphology and optical properties.
Finally, the experimental platforms used at
Cadarache to study fires was completed with theconstruction of the CARINEA installation, a device
designed for the study of small fires and which
comprises a smoke collecting hood.

Simulation of a fire andits consequences
To simulate a fire in a nuclear installation and toassess its consequences in terms of containmentof radioactive substances, two complementary
approaches are used at the IRSN: a simplified
approach using the FLAMME_S/SIMEVENT softwareand a detailed approach using the ISIS software.
The FLAMME_S/SIMEVENT software was used in2005 to carry out studies prior to the tests in the
PICSEL and PRISME programmes and calculations
to analyse the test results from the DIVA0 campaign carried out in the DIVA installation in 2004.
Furthermore, development of the SYLVIA software
was continued with the aim of improving on the
FLAMME_S/SIMEVENT software, which it will
replace in 2006, for the calculation of the effect ofventilation on the development of fire and thecalculation of the transport of particulate andgaseous species.

ISIS software developers.

The purpose of the ISIS software is to simulate 3D,
incompressible or only slightly compressible flows governed by
the effects of gravity and which are the seat of chemical
reactions. It should be able to describe in detail the air behaviour
and thermal behaviour of a room in which a fire occurs, whether
it is ventilated mechanically or naturally. This software will help
to improve the understanding of physical phenomena andconfirm or reveal the limits of the simpler modelling techniquecurrently used in the SYLVIA software.
In 2005, a version allowing calculations on several processors inparallel was developed. After a thorough test campaign to verify
the satisfactory operation of the relevant numerical schemes andtheir computer programming, the first physical validation
calculations were successfully carried out on fire tests conductedat the IRSN in ventilated premises. As the calculation software
was judged to be sufficiently operational on the numerical andphysical levels, it was then used, with success, to perform pre-test
calculations for the “PRISME DOOR” tests to be performed in
the DIVA facility in a configuration involving several rooms.

66 ]I R S N 2005 ANNUAL REPORTThe ISIS software was used to simulate fires in arealistic configuration for several minutes (see Focus
opposite). This calculation tool is now operational
for calculations to define IRSN tests and for thedetailed interpretation of their results.
Owing to the complexity of ventilation systems innuclear installations, their modelling requires theacquisition of a large number of measurements of
their air flow characteristics. The IRSN is especiallyinterested in drawing up a simplified modelling
method for these systems requiring the acquisitionof only a limited amount of air flow data butnevertheless able to realistically predict ventilation
behaviour in specified situations (see Focus below).

Research on air dispersion
The IRSN’s work is aimed at assessing the physicochemical phenomena relating to the suspension ofcontaminants and their transfer in normal andaccident situations. They should contribute to theassessment of the containment of radioactive

RESEARCH AND PUBLICSERVICE MISSIONS

materials and help to reduce uncertainties regarding the assessment of releases into the environment.
In this context, the year 2005 marked the end of
the PIC Aérocontamination (Common interest programme on airborne contamination) conducted with Cogema. The work carried out in thiscontext led to the release of a database, BADIMIS
V3, summarising knowledge on particle emission
for various accident scenarios in installations(dropping of powder, air flow on a heap of MOX
powder, etc.). In addition, research was carried out
to study the suspension of contaminants fromliquid sources.

In addition, research aimed at improving knowledge of the atmospheric dispersion of an acciden-

Experimental installation at Saclay
to simulate the dispersion of a heavy gas.

tal release of UF 6 was conducted in 2005 in thecontext of a PIC programme with Cogema. Using
the CFX-5 multidimensional calculation software,
it was possible to obtain a satisfactory simulationof the results of about 20 tests on the dispersion
of a heavy gas in ventilated premises.
These tests were carried out in the IRSN’s installations at Saclay, using a non-radioactive tracer(SF6) instead of UF6.

Simplifying the modelling ofventilation systems in case of fire

Full-scale blowing device to test the air flow andmechanical strength and compartmentation equipment
behavior under pressure.

Interactions between an installation’s ventilation system
and a fire affect the fire’s development and the containmentof radioactivity within installations. A great deal of air
data (pressures and air flow rates) is required in order tomodel the ventilation networks and transfers ofphysicochemical species, using the SIMEVENT software.

[FOCUS]In 2005, the IRSN conducted research on very small
particles (on a nanometric scale) which pose special measuring and filtration problems. In order tostudy their possible effects on health, a thesis
concerning the characterisation of the surface
developed by a “nanoparticle” aerosol was started
in collaboration with the INRS. Laser stripping
techniques, which may be used to decontaminate
the surface of materials, also produce nanoparticles. A thesis studying their formation during theinteraction between laser and material was started
in 2005 in collaboration with the CEA and Cogema.

As all this data is generally not accessible, simplifications
must be made according to the available data and the aimof the study.
In 2005, the IRSN established the initial basis for an
approach to simplify the modelling of ventilation systems.
The quantity of data required must be reduced as muchas possible while ensuring that the reduced set of data
defined in this way is adequate to correctly determine
the consequences of the fire for a given scenario andobjective.

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[FOCUS][R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmes

Agreement on co-operation with the
University of Chile on seismic hazards

RESEARCH ON
NATURALLYOCCURRING HAZARDS:
EARTHQUAKES AND
FLOODS
The aim of the IRSN’s work in this field
is to improve knowledge of possible external hazards (earthquakes and floods)
for installations at risk.

Research on earthquakes

Map of points measured during the seismic background noise
campaign conducted in Santiago de Chile (urban networks visible
in the background of the figure) with the frequencies deduced
from the measurements at those points in grey shading.

On 27 October 2005, the IRSN signed a co-operation agreementwith the University of Santiago de Chile in the field of researchon seismic hazards. This five-year agreement covers theperformance of joint work on the modelling of strong groundmovements, the propagation of seismic waves and site effects,
and the vulnerability and behaviour of structures during
an earthquake, along with the conducting of geological andpaleoseismological studies. It also plans the organisation oftraining schemes and conferences for a mutual exchange ofknowledge on these subjects. Under the agreement,a measurement campaign was conducted in Santiago in early
April 2005 to determine the “urban background noise” at morethan a 100 sites in the city. The ground characteristics will bemapped by processing the recordings taken. It is then planned toextend the measurements to the whole of the Santiago basin inorder to create a 3D geometric model of this basin.
Once the geological model has been established, it will bepossible to simulate strong motions caused by an earthquake on
a fault recently recognised as active by geologists. As a result of
these simulations, it will be possible to pinpoint areas in thebasins that are the most at risk in terms of seismic hazards.

In 2005, the IRSN’s research on the workings ofactive faults and the characterisation of their“seismogenic potential” was continued, with thestudy of the Vuache fault (Jura) in particular. Thisfault has been the cause of several earthquakes overrecent centuries, especially the Annecy earthquake
in 1995 which led to significant material damage.
The purpose of the study is to test a multidisciplinary method suitable for the French context, withlow deformation rates. The study is based on field
geometry, subsurface geophysical techniques andthe analysis of aerial photographs.
In addition, the Institute continued to investigate
site effects by undertaking work in an area exposed
to high seismicity in Chile (see Focus opposite).
Modelling of ground motion leading to failure of a
fault was continued in the context of two theses.
The first, presented in 2005, concerns the predictionof seismic movements by empirical damping
relations established on the basis of actual seismological measurements.The second thesis deals withdigital modelling with the aim of reproducing thecomplexity of the failure in the fault plane and ofseismic wave propagation phenomena in thegeological medium.

Flood hazard for nuclear
installations in case of
a tsunami
Following the tsunami in the Indian Ocean on
26 December 2004, the IRSN searched for documents, in 2005, reporting on events of that typethat may have affected French shores.This research
clearly showed that a tsunami occurred on the British
coast following the Lisbon earthquake in 1755, butthere is no information on events of that type on

68 ]I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONS

the French Atlantic shoreline. The IRSN thencompared the criteria adopted for the dimensioning of protection systems for EDF PWR sites anda “reference” tsunami deduced from available
observations, i.e. a rise of two or three metres in thesea level on the coast.This comparison showed thatthe existing protection systems for such sites could
cope with a “reference” tsunami in mean tideconditions. Study is, however, being continued todetermine the adequacy of the protection systems
for a “reference” tsunami in maximum continuous
tide conditions.

RADIOECOLOGYRESEARCH
The research conducted by the IRSN in
the field of radioecology concerns the
behaviour of radionuclides and theireffects on ecosystems, whether they are
the result of controlled or accidental
releases. It is also aimed at achieving abetter understanding of the spatial andtemporal development of radioactivity
in the environment. For the purposes ofthis research, the Institute has a high levelof involvement in international projects.

were validated in 2005, notably by means of crosscomparison exercises.

Development of applied
knowledge
Before models and tools are developed, the IRSN
conducts experimental and field work in order tobetter understand the mechanisms governing the
behaviour of radionuclides in the environment. In
2005, the topics covered by this work included
atmospheric dispersion, with experimental campaigns in the urban environment in the context of
the CAPITOUL project carried out in collaboration
with the French meteorological department, Météo
France, and transfers of carbon 14 and polonium
210 in marine species.
In addition, environmental data acquired in the field
is also used in the context of research projects
encompassing a variety of scientific disciplines.This
is the case for two of the Institute’s research projects,
SENSIB and EXTREME, which reached the implementation phase in 2005.
The goal of the SENSIB project on “radioecologicalsensitivity” is to eventually obtain a tool to represent
and compare, on the same scale, the sensitivity ofvarious media to radioactive pollution. The consequences of pollution for man and the environment
depend not only on the severity and nature of that

Development of models, tools
and expert assessment
techniques
In order to be able to assess the impact of nuclear
activities on the environment, the IRSN has, formany years, been developing and maintaining
models and tools needed to predict the behaviourof radionuclides in the environment. In 2005, a
new version of the ASTRAL software, jointly fundedby EDF, was delivered. This software can assess theconcentrations of radionuclides in the food chain
following an accidental atmospheric release. In time,
the ASTRAL software will be replaced by the
SYMBIOSE modelling platform which will be able
to model transfers of radionuclides within andbetween environmental compartments (aquatic,
terrestrial and atmospheric). EDF’s interest in the
SYMBIOSE platform was confirmed in 2005 throughits financial commitment to the development of
the industrial version. Work began on drawing up
the relevant specifications. In addition, the specificmodels developed for tritium and carbon 14 in 2004

Micro weather station and SF6 gas sampling devices used by
the Octeville laboratory for the CAPITOUL project.

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[FOCUS][R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Defining and implementing national and international research programmesRadioactive deposits linked with
Saharan dust falling in France

During a Saharan dust episode, dust levels can be 15 times
higher than usual.

In 2005, the IRSN launched a study, in the context of the EXTREME
project, to define the relationship between the level ofradioactivity in the atmosphere and the ambient dust
concentration, with Saharan dust transport and deposit episodes
representing the extreme dust levels. This type of event, limited
in time and with a high intensity, currently results in the greatest
atmospheric deposits of artificial radionuclides. As an example, on
21 February 2004, an exceptional Saharan dust transport anddeposit event occurred in the southern half of France, sweeping
an area of 300,000 sq. km. Readings of dust levels showed
increases by as much as a factor of 15 compared with usuallevels. Two million tonnes of dust were deposited during theepisode, with deposits of up to 50 g/m2.
Caesium 137 deposits measured after a few hours wereequivalent to those estimated for the whole of 2003. However,
the radioactivity added to soils on that occasion remained very
low compared with that already present as a result of radioactive
fallout from atmospheric nuclear tests and the Chernobyl
accident (approximately 1/1,000).
Locally, resuspension phenomena on a much smaller scale areobserved on a daily basis.
They currently govern the radioactivity background noise in theatmosphere near the ground.

70 ]I R S N 2005 ANNUAL REPORT

pollution but also on the environment into which
it is released. In 2005, work was started on factorsof agricultural sensitivity in the context of a thesison the utilisation of activity measurement results
obtained since 1961 in the air-soil-plant-animaltransfer system. As regards rivers, a post-doctoral
study was undertaken on the part played bygeomorphology in determining sensitivity factors
on the banks of the Rhône. For the atmosphere, athesis will undertake to establish the relationshipbetween air mass wash-out coefficients and thecharacteristics of precipitation, i.e. the type (downpour, shower, drizzle, fog, snow) its intensity, its
duration, the size of droplets and particles, the originof the air masses, etc.
As for the EXTREME project, this is studying theenvironmental consequences of processes generating large flows or stores of radioactivity, such as
storms and floods. Indeed, these events are liable
to displace large masses of material and to resultin radioactivity levels much higher than thosedetermined by existing modelling techniques, as
pollutant flows within a few days may often be
equivalent to total flows in several months or
event years (see Focus opposite). The report launching the EXTREME project was circulated in 2005.
This report was the result of post-doctoral workand a thesis on floods of the Rhône, and the beginning of a thesis on the forced redistribution ofmaterials on the scale of the Gulf of Lions.
These two projects rely, in particular, on the development of environmental measuring equipment
suitable for all media, implemented in the context
of the Institute’s OPERA measuring network. In
2005, a technical innovation was achieved by theInstitute’s laboratory at La Seyne-sur-Mer in collaboration with Harvard University. This consists inusing a sensor, dubbed “Gellyfish”, which is spontaneously balanced according to the surrounding
environment and facilitates the measurement ofconcentrations of metal pollutants. This device
can provide a standardised indicator of the concentration of contaminants in sea water, so facilitating the extension of marine observation networks,
such as “Musselwatch”, the international network
for the observation of marine pollution in the
Mediterranean, led by the IRSN under the auspicesof the International commission for the scientificexploration of the Mediterranean sea.

RESEARCH AND PUBLICSERVICE MISSIONS
Faced with the reduction in the means allocated toradioecology in Europe, the European Commission issued
in 2005 a call for proposals, in the context of the 6th
FPRD, to study the feasibility of a radioecology excellence
network. This could be started up as part of the 7th FPRD.
The purpose of this network would be to maintain andreinforce expertise in this discipline on a European andinternational scale. In response to the call for proposals,
the IRSN took the initiative of forming and co-ordinating
a consortium of 10 organisations from eight European
countries and submitting a project named FUTURAE.
After being appraised, this project was adopted by theEuropean Commission. A consortium of six organisations
was also set up in the context of the same call for tenders
to compare the various methods of assessing theenvironmental risks associated with radionuclides.
This consortium, which includes the IRSN, is co-ordinatedby the UK’s Centre for Ecology and Hydrology (PROTECT
project). These two projects will start in mid 2006 and will
last two years.

[FOCUS]

Participation of the IRSN in
European radioecology projects

Partners in the European FUTURAE programme under
the leadership of the IRSN.

High level of international
involvement
In 2005, the IRSN was strongly committed tointernational programmes, notably the European
ERICA project aimed at providing a method toassess the environmental risks of radionuclides.
In parallel, the Institute continued co-ordinating
the activities of the IAEA group revising the
TRS-364 guide regarding the parameters to be usedin radioecological models (EMRAS programme).
The IRSN also played a part in the writing of a
Unscear report on environmental protection andprepared a mussel reference sample for a crosscomparison exercise in the context of the international Musselwatch network.

Sample core of sediment from the river Rhône(EXTREME project).

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RESEARCH ON
METROLOGY FOR
RADIONUCLIDES IN
THE ENVIRONMENT
The aim of research on the metrology ofradionuclides in the environment is toimprove and constantly adapt thetechniques used in this field.This researchsupports radioecological studies ininvolving research on radionuclides invarious contexts and, sometimes, in verysmall quantities. As a result of thesestudies, the spatial and temporal development of radionuclides released by
nuclear activities can be understood andquantified.
In September 2005, the IRSN defined a reference
point for the radiological situation around the
new CERN accelerator, Large Hadron Collider, in
Switzerland, by in situ gamma spectrometry. In thisway, the Institute confirmed its mastery of thistechnique which is used by only four laboratories
in France.
In situ gamma spectrometry provides a sensitivity
equivalent to that obtained in the laboratory.

What makes it original is that it can give the specificactivity in Bq/kg and the dose rate per radionuclidein less than one hour including installation on site,measurement and analysis. Another advantage isthat a measurement representative of the site’smean value is obtained. In fact, laboratory measurements are performed on a sample weighing a
few 100 grams which has to represent the site to
be analysed, whereas the “sample” for in situ measurement is a disc which is more than 10 metres inradius and several tens of centimetres deep, i.e.
several tonnes of material.
A thesis aimed at improving its utilisation in complex environmental configurations (with nonuniformly distributed radionuclides) is being
prepared at the Institute’s Orsay laboratory.

CHRONIC RISKSThe IRSN conducts research on the risks
associated with chronic contaminationin order to improve the radiologicalprotection system. In 2005, the Institutepursued the development of tools toassess these risks for the environment
and to gain further knowledge on the
migration of radioactive elements in
the ground. In parallel, the ENVIRHOM
programme obtained major results toobtain better knowledge of the effects
on man and the environment, and thoseresults were presented to the scientificcommittee for this programme.

Assessment of chronic risks
Development of an environmental risk
assessment method
The findings of the ENVIRHOM programme, alongwith study in the context of the European ERICA
project, made it possible to design and develop arisk assessment method for ecosystems as regards
the presence or release of radioactive substances.
This assessment method is consistent with existing
methods used for chemical substances.

In situ gamma instrumentation near CERN to define the radioecologicalreference point (Geneva).

72 ]I R S N 2005 ANNUAL REPORT

Development of special tools for the expert
assessment of chronic risks
Furthermore, a number of tools for risk expert
assessments were developed in 2005:> EDEN for dosimetric calculations required for the

RESEARCH AND PUBLICSERVICE MISSIONS

Research on migration in non-saturated
zones of soils
In parallel with its work on the biosphere, the Instituteconducted studies in 2005 with the aim of obtaining
better knowledge of the fate of chronic radioactive
pollution in surface soils.
In this field, the EPIC project conducted on the
Chernobyl site in collaboration with the Ukrainian
IGS and UIAR research institutes led to the setting
up of new instrumentation characterising transfersin the non-saturated zone of soils.As a result, throughthe chemical and radiological analysis of water atvarious piezometers installed around a trench ofradioactive waste, it was possible to follow up thestrontium 90 (“plume”) originating from the trench.
In addition, special attention was paid to the studyof the transfer of plutonium and of its speciation(soluble and colloidal species).
The first stage of the CaPhéIne project regarding
the migration of radionuclides in soils was conductedin collaboration with the National centre for researchon polluted sites and soils (Douai, Nord). For thisproject, a lysimeter comprising contaminatedsediments over a natural soil was instrumented
with hydrogeochemical sensors.
As a result of the work for these two projects, itwill be possible to develop the modelling of transfersof pollutants in a non-saturated zone constituting
a route for the contamination of groundwater inthe case of polluted sites or waste disposal areas.

ENVIRHOM programme
The ENVIRHOM programme, which started in 2001,
deals with the risks related to chronic exposure toradionuclides with regard to both the environmentand human health. An international, multidisciplinary scientific committee is assessing the quality
and pertinence of the results obtained and gives
its opinion on guidelines proposed by the IRSN.

the previous four years, confirm the pertinence of
the ENVIRHOM programme.
Knowledge of biogeochemical cycles ofuranium and selenium
Advances in knowledge concerning the biogeochemical cycles of uranium and selenium in soils
and sediments in ecosystems has made it possible
to identify the routes via which living organisms
can be exposed to those two radionuclides, andthe relevant chemical forms, kinetics and intensity.
When a radionuclide has been incorporated into aplant or animal organism, only a fraction is biologically active to trigger relatively early responses
on the level of cells, tissue or the individual. For
example, selenium and uranium inhibit the

Presentation of the ENVIRHOM
programme to the scientific committee[FOCUS]

study of the exposure of living organisms to radionuclides;> the SYMBIOSE platform for models to calculatetransfer in the biosphere and related databases;> the FRED database for the effects of ionisingradiation on non-human organisms, used by the
IRSN to produce dose-effect relations in order todetermine protection criteria for ecosystems.

Presentation of the work on the ENVIRHOM programme
to the programme’s scientific committee at Vaux de Cernay

The scientific committee for the ENVIRHOM programme met for
the third time on 22 and 23 November 2005. Researcherspresented the most recent results obtained on exposure of theenvironment and man. The scientific committee expressed its
satisfaction on hearing these reports and drew attention to thequality and scientific interest of the work presented. It noted thecomplementary nature of the studies conducted on man andthose conducted on the environment, and suggested that those
links should be strengthened. One of the committee’s
recommendations was to continue having results published andto target journals recognised by the scientific community.
The ENVIRHOM programme had 25 articles published in 2005.

Exposure of the environment
The results obtained in 2005, which are in line withI R S N 2005 ANNUAL REPORT

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growth of a unicellular green algae populationaccording to a dose-effect relationship, with a threshold corresponding to a precise quantity of theelement studied inside the cell.
Progress towards the modelling of effects on
a population
On the basis of the experimental results obtained
for a small freshwater crustacean, the effects observed for an individual exposed to an alpha emitter
throughout its life cycle were extrapolated to an
entire population. Initial results show that someeffects observed on the individual level, such as
decreased resistance to lack of food, could resultin very severe effects for an entire population, including possible extinction.
Consequences for man of chronic uranium
contamination
The first element studied in the ENVIRHOM programme was uranium, as it can be present at highconcentrations in ground water in some regions,such as Finland, New Mexico and Canada. Studies
are being conducted on rodents experimentallycontaminated with uranium added to their drinking
water (40 mg/l) for durations of variable length.
Effects on the central nervous system
Chronic exposure to enriched uranium affects thewake-sleep cycle, the working memory and theExperiment on growth inhibition in algae
subjected to chronic exposure to uranium.

74 ]I R S N 2005 ANNUAL REPORT

anxiety-like behaviour of the rat after 1.5 monthsof exposure. During the year 2005, these effects
were correlated to the accumulation of uranium in
two brain structures involved in controlling thesebehaviours: the hippocampus and the hypothalamus. This backs up the hypothesis of a direct
effect of uranium on the central nervous systems.
Furthermore, a modification of the metabolism ofacetylcholine, the main mediator involved inmemorisation processes is noted in the hippocampus, the cerebral zone involved in spatial working
memory.
On the other hand, no significant modification
was observed after chronic exposure to depleted
uranium. Furthermore, its accumulation in cerebral
structures is different from that of enriched uranium. These various results were published in 2005.
Effects on the metabolism of vitamin D
The P450 cytochromes (CYP) are a family of enzymes
that plays a major role in the metabolism of exogenous substances (drugs, pollutants, pesticides,etc.) and endogenous substances (steroids, vitaminD, hormones, etc.).
In 2005, the IRSN studied the effect of chronic
contamination with depleted uranium in the rat
on certain hepatic and renal CYPs. The ingestion of
depleted uranium for nine months increases themain CYPs, in the liver and kidneys, involved in themetabolism of drugs.
These results suggest that a course of treatment
by drugs, given after chronic contamination with
depleted uranium, could lead to hepatic and renal
toxicity owing to an accumulation of toxic agentsin those organs. If this hypothesis was to be
confirmed, drug doses would have to be adapted
for the treatment of persons subjected to chronic
exposure to depleted uranium.
This type of contamination also results in an increasein the expression of a P450 cytochrome involvedin vitamin D metabolism in the kidneys. Furthermore,some vitamin D target genes involved in the transportof calcium in the kidneys are stimulated by chronic
exposure to uranium, thus reflecting a physiologicalimpact.
In conclusion, the effects of depleted uranium onvitamin D metabolism could lead to calcium andphosphorous homeostatis changes or, even, thedevelopment or aggravation of some bone pathologies or some cancers, such as of the colon or prostate.

RESEARCH AND PUBLICSERVICE MISSIONSRESEARCH WORKON RADON
Radon is a natural radioactive gas occurring all over the surface of the Earth. It
accumulates in confined spaces, especially in buildings. It is due to the risk oflung cancer that work is carried out onradon and its decay products in thehome. The IRSN is conducting research
to develop tools to model the phenomena involved in the circulation andaccumulation of radon in buildings andin water.

Understanding the radon
concentration mechanisms inbuildings
An experimental programme aimed at understanding the mechanisms affecting radon concentrations in buildings was completed in 2005. Instrumentation was installed in a detached house in
Kersaint (Finistère) to determine the penetrationof radon through the basement slab and its halfburied walls, its accumulation in the building andits distribution between the floors as a result of air
circulation and exchanges with the outside.
The data collected in this way was used to test
the RADON 2 code, developed at the IRSN.This code
is to provide a generic description of the accumulation of radon in a building.
The goal is then to provide an efficient diagnosis
tool to assist in the management of the radonhazard
and able to “predict” the activity concentration ofthis gas in dwellings located in areas with a highpotential for radon exhalation or on polluted sites.
The ground under the building is not always themain source of the radon measured indoors. Other
sources, such as building materials, can sometimes
play an important part. A bibliographic analysis
showed that the disparateness of studies on theexhalation of radon from building materials madeit difficult to use them. In the absence of any clear
trends, tests are planned on the Kersaint experimental site. Their aim is to determine how muchbuilding materials contribute to the activity
concentration of radon measured in the house at
Kersaint.

Instrumentation in the house in Kersaint (Brittany).

Radon, tracing water circulationin fractured media
Variations in the activity concentration of radonin groundwater in fractured media have beenstudied on a site in Morbihan (France), since 2004.
This research is aimed at improving knowledge ofthe behaviour of radon in water according to thehydrology, fracture systems and rock properties. In
2005, work was conducted, in particular, on tests
to validate models to calculate radon concentrations
in water on the basis of the characteristics of themedium.
Ground water in fractured water-bearing formations can constitute non-negligible radon sources,
especially in granitic regions. The objective is tobetter understand the production and transfer ofradon in a heterogeneous medium so that it can betaken into account in the management of radonhazards.
This work is being conducted as part of a project
set up in Brittany.

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Defining and implementing national and international research programmes

Measurement of radon andits decay products[FOCUS]

It is known that the risk of lung cancer associatedwith exposure to radon is not due to the radon itself
but to its short-lived decay products. These occur
in the form of aerosols, i.e. particles in suspension
in the air, some of which are inhaled and are deposited in the lungs.These nanometric particles become
fixed on atmospheric dust and are transported bythat dust in confined spaces.
The IRSN is conducting research in order to improve
its basic knowledge on the physics and metrologyof radon and its decay products, so that radon measurements in the field may be considered to provide

Quantification of cancer risksa reliable indication of the risk. The Institutecollaborated with the University of West Brittany
to develop and qualify an instrument to measure the size distribution of the free fraction ofradon decay products, as this is an indispensable
parameter in order to determine their behaviour
in a closed volume and their deposit in the respiratory tracts. In the context of this collaboration,a thesis was started in October 2005 to study theelectrical charge of these decay products, as this is
another parameter affecting deposits. This work
benefits from the technical environment developed around the IRMA irradiator and the calibration bench for BACCARA radon dosimeters.
This equipment is also used for other appliedscientific research projects and to provide calibration
services for radon measuring instruments.

EPIDEMIOLOGY
OF NUCLEAR
WORKERSThe IRSN continued its epidemiologicalactivity in 2005 with a view to enhancing
the assessment of cancer risks associatedwith chronic exposure to low doses ofionising radiation.
Alpha-Risk: a European programme.

The Alpha-Risk research project, financed by the European
Commission and co-ordinated by the IRSN, was started in July
2005 for a period of three years. This project seeks to improve
the quantification of cancer risks associated with chronic internal
exposure and, in particular, exposure to emitters such as uranium,
plutonium and radon and its decay products. It includes theprincipal epidemiological teams in Europe which are monitoring
populations with a precise record of individual dosimetry.
The Alpha-Risk projects is backed by 18 partners from ninecountries and relies on the collaboration of experts in the fields
of epidemiology, dosimetry, statistics and modelling. The projectis intended to specify the effects of low or repeated doses andshould lead to a consensus on the best assessment of the risk oflung cancer attributable to radon decay products, in smokers andnon-smokers. It is expected that a summary of the risks
associated with low doses will be drawn up as a result of theAlpha-Risk project.

76 ]I R S N 2005 ANNUAL REPORTThe IRSN is monitoring a cohort of workers fromthe CEA-Cogema group in order to estimate therisks of cancer associated with occupational exposure to ionising radiation: exposures that are low
but chronic. This assessment entails determining
the individual doses received by the workers
throughout their careers, searching for their vitalstatistics and, where applicable, the cause of death.
A total of more than 50,000 workers are involved.

Common interest programme inepidemiology
A Common interest programme (PIC) funded byCogema and the IRSN is studying the health effects
in a number of workers exposed to low levels of
ionising radiation.This three-year programme, whichstarted in 2004, relies on close co-operation between
the IRSN’s epidemiological laboratory and the
Cogema occupational medical department. It
comprises three studies.
> In 2005, the IRSN continued the analysis of the

RESEARCH AND PUBLICSERVICE MISSIONS

deaths of a cohort of French uranium miners. The
work carried out entailed extending the follow-up
of that cohort and analysing causes of death until
the end of 1999. A study to determine the smoking
history of the miners was carried out in order toallow for the part played by tobacco in occurrencesof lung cancer.The new results confirm the existenceof supplementary deaths due to lung cancer associated with exposure to the decay products of radon
accumulated over their entire working life.
> The study into the deaths of the Cogema workers
concerns more than 10,000 individuals, followed
up from 1976 to 1994. An initial report was drawn
up in 2005 and this showed there was no increasein mortality within the group of workers comparedwith the general population of France. The study of
the risk of death caused by cancer in relation to
cumulated exposure is continuing.
> The IRSN also tested, in 2005, the feasibility ofa morbidity study of Cogema workers (Ile-de-France
plant). This study is especially interesting in orderto determine the rates of occurrence of pathologies
with a low mortality rate. The first step involves
the data collected by the occupational medical
department at Cogema’s Ile-de-France plant. It willthen be extended to other sites. The purpose of thefeasibility study is to test all the tools required tocollect all the relevant diagnoses (cancers, andother chronic and acute illnesses) and, in parallel,
to provide access to other tools outside Cogema(regional cancer registers, other sources of information, etc.). This morbidity study would provide
a management tool for the Cogema occupational

Team of epidemiologists.

medical departments while also making it possible
to obtain more accurate results in the study ofCogema workers, which is currently based on
mortality data.

IMPROVEMENTS IN
RADIOLOGICALPROTECTION
The IRSN regularly improves its methods
and tools to assess the exposure of personnel to ionising radiation to provide
better radiological protection for workers,
patients and the general public.
In nuclear installations, workers are exposed tovarious risks of external irradiation, internal contamination and via the skin.Their protection is ensured
by various devices studied by the IRSN to check, inparticular, their reliability in case of accident andto improve their effectiveness.

Study of the performances ofsyringe shields used in nuclear
medicine

Installation of dosimeters to measure
the exposure of fingers when usinga syringe shield in nuclear medicine.

In nuclear medicine, some acts require a radioactive
marker to be injected into patients. This marker
contains a radionuclide which acts as a tracer,
generally combined with a molecule that has theproperty of attaching itself to specific cells in theorganism. The current trend shows increasing useof yttrium 90 (β- emitter).When radiopharmaceuticalsolutions are handled, the technician’s hands, in

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particular, are exposed to the radioactive sources
whose activity levels are in the vicinity of 1 GBq.
Radiological protection devices such as syringe
shields are therefore used when injecting patients.
In the course of 2005, the IRSN developed a digital
tool to evaluate the performances of these devices
and to propose improvements in order to reduce
exposure of the hands. This tool was validated bycomparing the results with experimental dataobtained, notably, in collaboration with the Gustave
Roussy Institute’s nuclear medicine department.
In the case of yttrium 90, it was confirmed that atungsten syringe shield 5 mm thick provided thehands with protection three times greater thanthat provided by a 1 cm thickness of Plexiglas. In
addition, a simple modification of the tungsten
device, by adding a few millimetres of Plexiglas,
reduces exposure by a factor of 2. Similar studies
were conducted for the injection of fluorine 18(β+ emitter).

IRSN conducted research to develop new protocols
for the analysis of α-emitter actinides in urine andstools offering better performances in terms ofsensitivity and response time in order to improvethe monitoring of exposed workers.
The benefit of using calix[6]arene molecules toselectively isolate U, Pu and Am actinides in urine
was demonstrated.These molecules effectively allow
the selective extraction of these three actinides ina quantitative manner. The invention developed byresearchers from the IRSN concerns the embeddingof calix[6]arene molecules on media with a view tousing them to analyse U, Pu and Am actinides inurine. A patent application for this invention was
filed on 17 May 2005. After being optimised andvalidated, the protocol developed should make itpossible to chemically treat the urine in one day
instead of the three days required by the protocols
used at present. This topic was also the subject of athesis presented in 2005.

Preparation of calix[6]arene
molecules for use in
the analysis of actinides

Model for internal contamination
by injury

One of the methods of monitoring workers exposed
to a risk of internal contamination by α-emitterradioelements is to measure these radioelementsin their urine.The current analysis methods requirelong, complex chemical treatments. In 2005, theInauguration of the AMANDE installation.

78 ]I R S N 2005 ANNUAL REPORT

There is little available literature on the biokinetic
behaviour of uranium in the case of internal
contamination by injury. At present, the ICRP does
not propose any model for this type of contamination. It is for this reason that a study was started
by the IRSN. In the first stage of the study, conductedin collaboration with the Cogema occupational
medical department, a review of the various typesof contamination by injury occurring in the fuelcycle industry was drawn up. The next stage in the
study concerns the modelling of internal contamination by uranium after sustaining an injury. It isbased on in vitro uranium transfer experiments onpieces of skin, with in vivo validation on rodents.
The purpose of these experiments is to simulate themain types of injury listed.
In 2005, data regarding the transcutaneous passageof uranyl nitrate in an aqueous solution for healthyskin and for damaged skin were obtained in vivo inthe rat. They confirm and reinforce the results ofexperiments conducted in vitro on pieces of rat, pig
and human skin. In conclusion to this work, it appears
that, like inhalation and ingestion, the cutaneousroute allows the incorporation of uranium whether
the skin is damaged or not. This could be the originof some internal contaminations observed by occupational medical departments and that have
hitherto remained unexplained.

RESEARCH AND PUBLICSERVICE MISSIONSTHE AMANDEINSTALLATIONThe IRSN opened its new AMANDE
research installation on the Cadarachesite (Bouches-du-Rhône) on 20 May 2005.
The primary aim of this installation is todetermine the response of neutron
measuring equipment in relation to theenergy of the neutrons, as recommended
by international standard ISO 8529-1.

fibrosis in vitro and in vivo (see Focus below).
A new therapeutic approach for fibrosis using
statins was also tested in 2005. In rats, treatment
with pravastatin after irradiation showed a preventive action on the development of radiation-induced
intestinal fibrosis.
Thanks to these results, it was possible to offer
this treatment on a clinical basis in order to limit
delayed complications of therapeutic radiation andso improve the quality of life of patients treatedby abdominal-pelvic radiotherapy. A clinical study
is being prepared to assess the protective effect ofpravastatin.

Work will continue at UPRES EA 27-10

The AMANDE installation was designed to generatemonoenergetic neutron fields of metrologicalstandard, with energy adjustable between 2 keV
and 20 MeV by means of a specially designed particle
accelerator.The project was started in 2000 and theinstallation will be operational in 2007.
The phase for the setting up of the detection andqualification systems for the charged particle beamand neutron fields started and is scheduled to last
two years. The AMANDE installation will make the
IRSN neutron metrology and dosimetry laboratorya reference for neutron dosimetry on the national,
European and international level.

RADIOLOGICALPROTECTION IN THE
MEDICAL FIELDRadiotherapy treatment can have acuteand delayed secondary effects, such as
fibrosis.These side-effects are caused bydamage to healthy tissues exposed to
the radiation field. New therapeutic
approaches must therefore be developed
to provide better protection for healthy
tissue.

Therapeutic utilisation of statinssuch as anti-fibrosis agent
In 2005, the joint UPRES EA 27-10 unit (IRSN-Gustave
Roussy Institute) determined the general mechanisms for the development of radiation-induced[FOCUS]

The mathematical modelling of the distribution
kinetics of uranium in the organism after contamination via injury is currently in progress.

The research centre adjoining Gustave Roussy hospital in Villejuif

In 2005, the French Ministry for Research renewed its backing for
the UPRES EA 27-10 laboratory for the third time for a further
period of four years. The UPRES EA 27-10 unit (IRSN-Gustave
Roussy Institute) is one of the very few French laboratories
studying the biological bases of radiotherapy and its
consequences on healthy tissues. The unit’s studies are based on
a combination of intestinal physiology, molecular studies and thedevelopment of original experimental and cellular models with aview to determining the general mechanisms of radiationinduced fibrogenesis.
Two preclinical studies in animals were completed in 2005.
They showed the therapeutic benefits of using GLP-2 and statinson the development of radiation enteritis. This research was
conducted in association with the pharmaceutical industry(Novonordisk and Bristol-Myers Squibb). A first clinical protocol,
marking the completion of this research work, was proposed to
study the clinical efficacy of pravastatin after radiotherapy.

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Bio-indicator of damage to bone marrow

IRRADIATION AND
CONTAMINATIONACCIDENTS
The work carried out by the IRSN on theeffects of medium and high dose irradiation concerns effect bio-indicators fordiagnoses and, even, prognoses, researchon new therapeutic targets, and thedevelopment of operational measurement systems to complete diagnosis
tools.

Surfaceunder FLcurve
25 000

20 000

15 000

10 000
70
60
50
40
0
30
0.30
20
0.25
0.20
10
0.15
0.10
Fraction of irradiatedCumulated dose
0
0.05
0.00
bone marrowof ionising radiation (Gy)

5 000

Relationship between FL concentration and overall damage
to the bone marrow.

In case of accidental irradiation, damage to the bone marrow canconstitute a serious problem for the organism. Disturbances in
the formation of blood cells (haemopoiesis) may occur, so
leading to infectious and haemorrhagic risks which may affectthe vital prognosis of an irradiated individual. It is essential toassess the residual haemopoiesis in order to choose a therapeuticstrategy, as it is of paramount importance in order to decide
whether or not a bone marrow graft should be performed.
In 2005, the IRSN continued its studies on research in bioindicators of damage to bone marrow after irradiation.
The regulating mechanisms of the Flt3 ligand, a molecule playing
a part in the control of haemopoiesis, were studied after
irradiation for a thesis presented in 2005.
A heterogeneous irradiation model with variable percentages ofirradiated bone marrow was developed for the mouse.
The results show that variations in the concentration of Flt3
ligand in the blood can be used to directly assess radiationinduced damage to the bone marrow.

Improving diagnoses
Reference curves for irradiation at high doses
Improving diagnosis methods for accidentally
irradiated persons remains a major priority at the
IRSN. In Biological dosimetry, the conventional
technique used is based on the number of chromosomal aberrations and dicentrics in lymphocytes
isolated from a blood sample. This technique,however, has limitations for doses higher than 5 Gy.
In the course of 2005, the IRSN developed a new
methodology for the drawing up of reference “doseeffect” curves specifically adapted to irradiation athigh doses (higher than 5 Gy) in order to complete
the set of existing curves.
This methodology is especially suitable for criticality
accident conditions. It allows both high exposure
doses (more than 10 Gy) and the mixed gamma/
neutron flow to which victims are generally exposed
to be taken into account. For this purpose, gamma
irradiations and mixed gamma/neutron irradiations
at between 5 and 25 Gy were applied to blood
samples.
A method of achieving the early condensation ofchromosomes by means of chemical molecules fromlymphocytes obtained from the samples was adopted
and another type of chromosomal aberration, known
as centric rings, was used. These anomalies are 10
times less numerous than dicentrics and only reacha saturation plateau at much higher doses. Using
the reference curve thus obtained, the ratios ofcentric rings observed in victims of the criticality
accident at Tokai-Mura (Japan) gave exposure dosesthat were consistent with those determined byphysical dosimetry.
The IRSN now has a set of reference curves covering
accident situations and activities in various industries.

80 ]I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONSThis work is the fruit of collaboration between the
IRSN and the Centre for health and protection
against radiation (CPHR) in Cuba.
Dose assessment by electronic paramagnetic
resonance (EPR) in case of radiologicalaccident
The IRSN uses EPR spectrometry as a dosimetry
technique to assess the doses received by victimsof external exposure to ionising radiation. Dosimetry
is used to estimate the amount of irradiation andto establish the best possible diagnosis so as todefine the most suitable therapeutic strategy. Thismethod is being developed with the aim of increasing
the Institute’s operational efficacy.
The corresponding studies in 2005 consisted inselecting materials which may have been locatedin the victim’s environment, such as sugars, anddetermining their dosimetric properties in a photon
field and in a mixed neutron and photon field. The
results showed, in particular, that the materials
studied have interesting dosimetric characteristics,
i.e. a linear dose response and a response independentof radiation energy.
The IRSN also created a database of conversion
factors between the doses received at one or morepoints of the body, measured by EPR, and thedoses received by organs or the whole body. Factorsof this type were systematically calculated instandard and realistic irradiation configurations
for photon, neutron and mixed fields.This databaseprovides the Institute with a tool giving a firstassessment of the dose distribution within a very
short time. All the studies were carried out for the
purpose of a thesis to be presented in 2006.

Research into new therapeutic
options for accidental irradiationcases
Utilisation of mesenchymal stem cells
Cellular therapy entails providing the organism withcells capable of repairing its damaged tissues. The
work undertaken by the IRSN is being carried out
by a mixed team from the IRSN and Saint-Antoine
hospital (UPRES 16-38). It concerns the possibilityof adapting the principles of cellular therapy tothe case of victims of accidental irradiation in order
to correct cellular deficits which may have immediate
or delayed consequences for the organism.
The mesenchymal stem cells (MSC) in the bonemarrow are multipotent cells, i.e. they are able to

Dose assessment by EPR.

proliferate and differentiate into many types ofcells. These properties offer prospects in the fieldof regenerative medicine. The work carried out at
the IRSN in 2005 consisted in studying the possible
use of MSCs for the treatment of radiation-induced
tissue damage and, especially, for the cellular therapyof radiation-induced intestinal damage.
Immunodeficient mice were transplanted withhuman MSCs 24 hours after local high-dose
irradiation of the abdomen.The regenerative capacityof the MSCs was studied on the intestine.The results
showed that transplanted MSCs are engrafted in
the intestine and limit radiation-induced
morphological changes to it. The cellular effects of
MSCs during the structural regeneration werecharacterised. MSCs reduce the mortality ofintestinal cells and increase the proliferation capacityof the cells in the crypts of the intestinal epithelium,
a compartment where the intestinal stem cells arelocated.As a result of this study, it should be possible
to establish a relationship between the capacity ofMSCs to regenerate the intestinal structure and thepossible functional restoration of the intestine.

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Defining and implementing national and international research programmes

MANAGEMENT OF
POST-ACCIDENTSITUATIONS[FOCUS]In 2005, the IRSN’s main studies on the
management of post-accident situations were focused on the definition of
approaches and tools to respond to
accident situations and to deal suitably
with their consequences.

Completion of the contract
with DGA on molecular therapeutics

Histological cross-section of irradiated intestine.

The year 2005 saw the completion of two years’ work by the
IRSN under contract with the French General Delegation forArmaments (DGA). The aim of this work was to study the partplayed by intestinal damage in radiation-induced multiple organ
failure syndrome. For this purpose, the efficiency of therapeutic
approaches targeting the intestine was tested in mice, after
exposure of the abdomen area to high doses of irradiation(between 15 and 20 Gy). One of the therapeutic strategies
consisted in reducing the radiation-induced inflammatory
reaction by taking action quickly after the exposure. Thus, theresults obtained show that, in conditions where the intestine isseverely damaged both morphologically and functionally, steps
to quickly control the inflammatory response can increase thesurvival rate and reduce structural and functional intestinal
damage in the irradiated mouse.

82 ]I R S N 2005 ANNUAL REPORTWork on the European level
Environmental rehabilitation following
an accident
The assessment of possible rehabilitation actions
in agricultural and built-up areas after a nuclear
accident is being studied in the European EURANOS
programme. In 2005, the IRSN continued to lead agroup of interested parties in France (agricultural
technical institutes, local government departments,
elected representatives and experts) that have thetask of assessing a European decision guide regarding
the decontamination operations to be performed
in built-up areas.
Consensus on medical treatment in case ofa radiological accident
In October 2005, the European Group for Bloodand Marrow Transplantation (EBMT) and the
University of Ulm (Germany) organised a conference
at Vaux de Cernay (Yvelines) in order to establish
a European consensus on medical treatment in caseof a radiological accident, including as a result ofterrorism. After a review of the specific features ofan irradiation accident and of medical management, the participants defined the most suitable
medical treatment.
The results from focus groups were pooled toreach a consensus on many aspects of diagnosis
and therapeutic strategy. This consensus concerns,
in particular, treatment with cytokines and therapeutic indications for bone marrow transplantation, which had been fully debated over several
decades.
This consensus represents an important stage in
the approach to harmonise medical treatment for
many victims in case of a radiological incident.

Modelling tools for atmosphericdispersion
The IRSN collaborated with two university
establishments in 2005 to create tools to model
the atmospheric dispersion of an accidental
radioactive release.
The first collaboration, with the Ecole Centrale deLyon, concerned the development of the pX model
for local atmospheric dispersion, i.e. within distancesof 30 km from the point of release.
The second, with the Ecole Nationale des Ponts et
Chaussées, was for the development of the IdX
long-distance dispersion model, the modelling of
the behaviour of aerosols and the implemen-

RESEARCH AND PUBLICSERVICE MISSIONS[FOCUS]

Analysis and quantification of atmospheric fallout in France following
the Chernobyl accident
1 and 5 May 1986. It confirmed the considerable influenceof wet fallout in the occurrence of caesium 137
depositions in May 1986, already identified during
previous work presented in 2003. It showed deposits ofthe same level as previously. In particular, deposit
variability factors, which could result, locally, in higher
values in some departments of Easter France (Corsica,
Alpes-Maritimes, Drôme, Jura, etc.) were studied, alongwith the influence of the proportion of wet deposits on
the contamination of plants and, thereafter, of the foodchain in May 1986.

Map of France showing caesium 137 deposits on the groundas a result of the Chernobyl accident (May 1986).

The IRSN conducted and completed a study, in 2005,
with the aim of improving the analysis and quantificationof the phenomena causing the atmospheric fallout of
caesium 137 in France after the Chernobyl accident.
This study was based on the collection and interpretationof relevant data concerning the contamination of soil
and air, along with the amounts of rainfall between

tation of methods to apply the measurement resultsin the environment by means of models.
In this way, the first version of the pX model wasdeveloped and work on the scientific qualificationof both models was started.
In addition to this qualification process, a “research”
version of the IdX tool was tested by reconstructing
the dispersion of radioactivity resulting from the
Chernobyl accident (see Focus above).

Furthermore, as a result of this work, it was possible toconfirm and specify the benefits and contents of current
projects at the Institute with the aim of boosting its
capability of assessing radiological consequences in postaccident situations:> future developments of the atmospheric aerosol
monitoring network;> development of a code for the long-distanceatmospheric dispersion of radionuclides (ldX);> study of atmospheric wash-out of aerosols during rainy
periods, using observation results from the IRSN’s OPERA
network;> development of an assessment approach based on thesensitivity of environmental compartments subjected toradioactive contamination.

INTERNATIONALPROGRAMMES AND
AGREEMENTS
The IRSN’s research activities on theEuropean level expanded in 2005. Its workin connection with the Franco-German
initiative for Chernobyl was completed
and bilateral co-operation projects were
stepped.

Research in
the European context
The European Commission’s framework programmes
for research and development (FPRD) played a

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Defining and implementing national and international research programmes

Tripartite co-operation in case ofradiological accident

Dose assessment by biological dosimeter.

[FOCUS]

The IRSN signed an agreement in 2005 with Britain’s HealthProtection Agency (HPA) and the German organisation,
Bundesamt für Strahlenschutz (BfS), allowing any of the signatory
countries to call for assistance from all the biological dosimetrylaboratories in the other countries in case of a radiologicalaccident.
This agreement should make it possible to obtain a dose
assessment in a crisis situation three days after the taking ofa blood sample, and so help medical teams to implement
the optimal therapeutic strategy.

Franco-Russian co-operation
The IRSN has been co-operating with the Russian federal agency
for nuclear energy (Rosatom) for many years in a context definedby the CEA. During the CEA/Rosatom committee meeting held in
December 2005, it was decided that the IRSN would, from thenon, be a full member of this arrangement.
Co-operation between the IRSN and Rosatom mainly concerns thephysical protection of nuclear materials, radiological protection,
criticality and crisis management. The year 2005 was significant
owing to the renewal of co-operation in the field of radiologicalprotection, through the signing of a co-operation agreementwith the Moscow Institute of Biophysics regarding, at a first stage,
accident dosimetry, radiation pathology and biological dosimetry.

84 ]I R S N 2005 ANNUAL REPORT

part in the sharing of knowledge and the resources
required to carry out research, notably in the nuclear
fission field. They also allow European laboratories
to compare their results and foster the creation anddevelopment of research networks.
The IRSN is involved in 11 projects in the Euratom
part of the 6th FPRD (2002-2006), including coordinating the network of excellence on the physics
of severe accidents in pressurised water reactors(SARNET) and the project to assess chronic risks
due to alpha radiation (Alpha-Risk). The Institutealso took a very active role in proposing 11 newprojects for the last call for tenders in 2005.
In the context of the general FPRD, the IRSN isparticipating in the FIRST project on the protectionof healthy cells subjected to radiotherapy and in
the ETPIS technological platform which includes
some 170 European organisations working on thesafety of industrial installations subject to hazards
such as fire and explosion. The Institute is also
preparing to participate in safety research projects
which will be developed in the context of the 7th
FPRD.

Situation report in the FrancoGerman initiative for Chernobyl(FGI)
An initiative to deal with the consequences of theChernobyl accident was launched 10 years ago by
the French and German Environment Ministers in
co-operation with Ukraine, Belarus and Russia. The
implementation of this initiative, under the responsibility of the IRSN and its German counterpart,
GRS, mobilised more than 30 Ukrainian, Belarussianand Russian institutes with €6 million funding
provided, in equal shares, by the French and German
governments, EDF and the German electricity group,
VDEW.
The aim of FGI was to gather all existing data on
the safety of the sarcophagus, the impact of theaccident on the environment and its consequences
for the health of the populations concerned in thethree countries, in order to create a reliable databaseuseful for the planning of countermeasures, public
information and scientific and technical work inthose three fields.The databases completed in 2005
are now accessible on the Chernobyl Centre website(www.fgi.icc.gov.ua).
Thanks to these databases, progress has alreadybeen made in the three fields mentioned:

RESEARCH AND PUBLICSERVICE MISSIONS
contamination and the pathologies observed.
The purpose of this study is to provide answers to thequestions raised by the work of Dr Y. Bandazhevsky, whichsuggest that the children living areas contaminated byreleases from the Chernobyl nuclear power plant may beaffected by unusual pathologies such as cataracts,
gastroduodenal ulcers and cardiac dysrhythmia.

[FOCUS]

Studies of pathologies in children
in Bryansk oblast

The IRSN’s work is carried out with the collaboration ofphysicians from the Bryansk clinical diagnosis centre (BCDC)
and dosimetry specialists from the Obninsk medical centre
for research on radiation (MRRC). A group of 49 children living
in contaminated areas was formed on the basis of medical
follow-up data on inhabitants of Bryansk Oblast.

Measurement of caesium 137 in children
in Bryansk oblast.

The IRSN set up a study named EPICE in October 2005
with the aim of measuring the caesium distribution inchildren living in the Bryansk region, which was the mostcontaminated area in Russia, and of checking whether
there was a link between their levels of caesium

the data gathered regarding the safety of thesarcophagus were supplied to the Shelter Implementation Plan, managed by EBRD, in order to
optimise the agreed international effort to place
the remains of reactor no. 4 of the Chernobyl power
plant in a safe situation;> the use of data concerning the environmental
effects of the accident has made it possible toimprove some radionuclide transfer models which
would be used in the management of a nuclear crisis;> The data regarding the accident’s consequences
for the health of populations, especially as regards
cancers (solid tumours and leukaemia), congenital
malformations and infant mortality, represent avery major contribution to the study of theconditions in which these problems occur.
The IRSN and GRS organised discussions with theirforeign partners and international organisations in2005 with the aim of facilitating wide utilisationof the data assembled, perpetuating and enriching
the databases and furthering the work carried out
in the fields of health and the environment, especiallypost-accident management.
>

Teams from the IRSN, BCDC and MRRC conductedmeasurements of the distribution of caesium 137 in thebody, especially the heart, thyroid gland and liver, for eachchild. They also gave the children full medical check-up,
including cardiogram and scans of the thyroid gland, liverand heart.
Using the results of this study, which are expected in thecourse of 2006, it should be possible to specify the impact
of caesium 137 contamination on non-cancerous
pathologies in the individuals exposed.

French-Indian co-operation
The co-operation between the IRSN and India’s
Bahba Atomic Research Centre (BARC) was defined by an agreement signed by both parties in
July 2000.
After focusing on questions regarding reactor
containments and cores, it was extended to radiological protection in 2003.
Discussions were held on the broadening of theagreement in 2005. New topics including , inparticular, the assessment of the safety of radioactive waste disposal facilities, methods of assessing uncertainties in accident thermal-hydraulics
and epidemiology were added.
In this context, the IRSN hosted three BARC experts
in 2005 in order to start work on the validation
and adaptation of the ASTEC and ICARE/CATHARE
codes. This work is now being continued at BARC.
The Institute also actively participates in meetingsorganised in the context of French-Indian discussions
on nuclear safety. It was agreed, in October 2005,
that a seminar on methods of assessing uncertain-

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Defining and implementing national and international research programmes

ties in accident thermal-hydraulics would be jointly organised by the IRSN and BARC to be held in
Bombay in the first half of 2006. Furthermore, aseminar on the analysis of the safety of the EPR
reactor is also to be organised owing to the interest
shown by Indian organisations.

RADIOLOGICALPROTECTION:
STRENGTHENING
FRENCH PRESENCE
INTERNATIONALLY[FOCUS]

Visit of the French delegation for French-Indian
discussions on safety - Madras nuclear power
plant, 26 October 2005.

The IRSN defines its position on
environmental radiological protection
The protection and monitoring of the environment have always
been matters of great concern for the IRSN.
In response to the increasing emphasis on environmental
preoccupations over the last decade, the IRSN has set out its
general strategy for the development of an environmental
radiological protection system. The position statement, publishedby the IRSN in 2005, describes the development of practices inthis field, the current state of knowledge and knowledge thatshould be acquired in order to consolidate a method to assess
the environmental risks associated with radionuclides.
This document also considers the consequences of this approachon environmental monitoring strategy and the resulting
implications for the Institute’s relationships with its national,
European and international partners.
For further information, visit
www.irsn.fr/vf/09_int/09_int_3_lib/pdf/DOCREF-IRSN2005-48V1fr.pdf

86 ]I R S N 2005 ANNUAL REPORTIn 2005, French representation wasboosted at the International Commission
for Radiological Protection (ICRP). Fiveof the seven French members of ICRP
are IRSN employees. ICRP’s new chairman,
Lars-Erik Holm, director of the Swedish
institute for radiological protection (SSI),
is also a member of the IRSN’s scientificcouncil. Several experts from the IRSN
also participate in ICRP focus groups.
The IRSN has also stepped up its presence in otherinternational bodies that are competent in the fieldof radiological protection (Unscear, IAEA, NEA,
Euratom, IUR, ISO, IEC, etc.). This trend is linked, inparticular, to the greater attention paid to theincreased focus on the field of environmental
protection and is reflected by the arrival of a newgeneration of experts. The Institute thus remains
one of the main national organisations supplying
experts who participate in the work of those bodies.
This active participation is important as the mainorientations of the radiological risk management
system used to draw up French regulations onradiological protection are the result of consensuses
established with international bodies.
Owing to its international position, the IRSN has
formed a collaborative group with other French
players in the radiological protection field (authorities, industrialists, associations and experts). The
last meeting of this group on 2 November 2005
reported on ICRP’s process for the revision of its
general recommendations and on a project toRESEARCH AND PUBLICSERVICE MISSIONS

position statements drawn up by the Institute, or
under its supervision, regarding protection of theenvironment and the European Committee on
Radiation Risk (ECRR) (see Focus below).

Controversy over the effects ofinternal contamination
The possible effects on health of chronic internal
contamination are a subject of scientific controversy anddebate regarding the appropriateness of the current
radiological protection system for this type of exposure.
In order to shed light for this debate, the IRSN published acritical analysis report in 2005, regarding the proposals

made on this subject by experts participating in ECRR.
The conclusion of this analysis is that ECRR is asking theright questions but that its approach to providing answers
is lacking in scientific rigour, making its claims difficult toverify. The IRSN currently considers that there is no needto modify the existing radiological protection system but
is stepping up its research efforts in order to answer thequestions raised.
For further information, visit: www.irsn.org/rapport_ecrr

I R S N 2005 ANNUAL REPORT[FOCUS]

modify the Codex Alimentarius provisions regarding
the contamination of foodstuffs after a radiologicalaccident.
During this meeting, the IRSN also presented the

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Contributing to training in radiological protection

Contributing to training inradiological protection
Contributing to radiological protection training for health professionals and personnel
who are exposed in the course of their work is one of the public service missions assigned
to the IRSN. This activity is based on a recent regulation aimed at ensuring that greater
account is taken of the risks to which professionals are exposed.

41 sessionsorganised andcompleted (20 in 2004)

SUPPORT FOR
THE PREVENTION OF
RADIOLOGICAL RISKSAND TO LIMIT THEIRCONSEQUENCES[FOCUS]As a research and expert assessment
establishment, the IRSN has a duty toprovide training and to contribute toteaching in its fields of expertise, i.e.
nuclear safety and security as well asradiological protection.

In the course of 2005, the IRSN organised about 40
training sessions on radiological protection in
response to needs expressed by an increasingly
diversified clientele (industrialists, physicians ofradiology, metrologists, etc.), while taking into
account the availability of training instructors andthe technical means to be implemented. In fact, thesessions were mainly organised by IRSN managerial
staff.
These training courses endeavoured to find a compromise between clients’ requirements on cost andduration, which are often subject to regulations,and the quest for optimal quality both for theteaching project and for the methods used.

Setting up of a training course on the radioactivity of waterfor engineers and technicians from Ddass and Drass

Training provided by the IRSN.

Over recent years, there have been changes in regulations
regarding the radiological quality of water for humanconsumption, including the order of 12 May 2004
specifying inspection procedures. As a result, the engineers

88 ]I R S N 2005 ANNUAL REPORTand technicians responsible for the monitoring of “drinking
water”, within the “health and environment” departmentsof French departmental and regional administrations forhealth and social affairs (Ddass and Drass), expressed theneed for training in 2005.
In June, 25 Drass and Ddass agents from the Brittanyregion took part in the first training session on thissubject, in Rennes, jointly organised by the DGSNR and the
IRSN. This training, which is now available in other regions,aims to provide trainees with the theoretical and practicalassessment tools they need to verify that drinking water
specifications with regard to radiological criteria arecomplied with and to inform the local authorities of thesteps to be taken if those specifications are not met. The
expectations of the administrative departments concerned
was gauged during the “trial” training section in Rennes anda training module which can be used for all Ddass and Drass
departments was designed.

RESEARCH AND PUBLICSERVICE MISSIONS

Subject of sessions
or professional
training
activity

Durationof eachsessionNumberof sessions
in 2005

Target audience

Number of
students
trainedRadon metrology

3 days4

Approved organisations, housing experts

61

Medical radiological protection(patients and workers)

2 days8

Occupational physicians,
personnel skilled in radiological protection

85

Practical training
in the assessment ofradiological and nuclear risks,and study of exposed
work stations

2 days2

Occupational physicians
personnel skilled in radiological protection

16

Assessment of worker
exposure
to ionising radiation,
dosimetry management
and SISERI system

2 days2

Occupational physicians,
20
personnel skilled in radiological protection

Dosimetry management
at work

2 days3

Occupational physicians,
personnel skilled in radiological protection

20

Training in radiologicalof exposed workers

1 day

9

Exposed protection personnel

205

Training in radiological protection 3 days
(radiological protection inspectionin the workplace)1

Factory inspectors,
medical inspectors

Training in radiological protection 3 days(role, missions and facilities
of occupational physicians)

2

Occupational physiciansRaising awarenessin a medical environment

1 day

9

Hospital physicians and personnel,
95
occupational physicians, industrial medical officers

Radiological protection,
citizenship and governance

1 day

1

Elected representatives, members of CLI,
teachers

25

Training in radioactivityof water

1 day

1Engineers from Ddass and Drass

25*FOCUS[FOCUS]

Training sessions provided in 2005

25

p.139

*

TOTAL

42

38

615

With the exception of training in radon metrology, which requires a special environment, all other training sessions canbe conducted at the IRSN or on clients’ premises.

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Contributing to training in radiological protection[FOCUS]

The professional categories that were the mostfrequently represented in the 2005 sessions were
workers exposed to ionising radiation, organisations
responsible for measuring radon in establishments
opened to the public, physicians of radiology andparamedical personnel working in radiology,
occupational physicians and personnel responsible
for the dosimetric follow-up of workers, and theProfessional training
programmes offered

Training courses to meet every need.

90 ]I R S N 2005 ANNUAL REPORT

factory inspectorate. At the request of the Local
Information Commission in Saclay (Essonne), a
course on radiological protection, citizenship andgovernance was arranged for its members (local
elected representatives, representatives of associations and teachers).
Some of the courses mentioned above were also
attended by IRSN personnel.

Radiological protection of medical andparamedical personnel, for the protection of patients andworkers> Practical training in the assessment of radiological andnuclear risks, and study of exposed work
stations> Radiological protection of exposed personnel in industry> Assessment of worker exposure to ionising radiation,
dosimetry management and SISERI system> Raising awareness of radiological protection for exposed
personnel> Professional training on the procedures applicable toradioactivity detection portals - Measurement and steps tobe taken in case of detection> Radiological protection and inspection: training forfactory inspectors> Industrial radiology equipment users Preparation for CAMARI> Radon metrology in buildings> Radiological testing of drinking water>>

Metrology of drinking water, cross-comparison>

Radiological protection, governance and citizenship>

Course provided>

Course not provided in 2005

RESEARCH AND PUBLICSERVICE MISSIONS

Permanent monitoring in
the field of radiologicalprotection
In the context of its public service missions, the IRSN carries out permanent monitoringin the field of radiological protection. This includes the monitoring of radioactivity inthe environment in France, the assessment of the exposure of personnel and managementof the inventory of radiation sources.

RADIOLOGICALMONITORING OF
THE ENVIRONMENTIn France, the monitoring of radioactivity
in the environment is ensured by the IRSN
using sampling and telemetry stations
which may or may not be located close
to installations that could discharge
radionuclides.The environmental samples
taken are analysed in the Institute’s
approved laboratories.
The telemetry networks provide real-time
radiological monitoring of the environment bymeans of self-contained units that continuously
measure the radioactivity of the area where they
are located. When an increase in radioactivity isdetected, a warning is sent to the IRSN and an
investigation is conducted.This was the case in 2005
following a management incident in a nuclear
medicine department which led to the release ofcontents of urine tanks. The Institute’s assessmentof the corresponding contamination was used toassist in the management of the waste water
treatment sludge.
The sampling networks managed by the IRSN
are used to monitor changes in radioactivity byanalysis of samples of air, water, soil, flora and fauna.
30,000 samples were analysed in 2005. The Institute publishes the results of this monitoring activity on its website and now publishes an annual
summary of the radiological state of the environment in France.

Monitoring in French Polynesia
The IRSN conducted a sampling and analysis campaign on foodstuffs produced in French Polynesia,
as it does every year.The results are used to determine
the exposure of persons living in the various
archipelagos. In 2005, the total “added” dose wasless than 5 μSv. The annual report on Radioactivity
Monitoring in French Polynesia published by the IRSN
is available on its website.

points acrossthe country(500 in 2004)

1,000 gamma

radiationmeasuring
points using
thermoluminescentdetectors(1,000 in 2004)

213 beacons

making up the country’s
remote monitoring
network: Teleray,
Hydroteleray,
Telehydro and SARA
(213 in 2004)

Nearly100,000
radiologicalanalysesconducted(100,000 in 2004)

Metrology to support
monitoring
Warning network remote monitoring room in
Le Vésinet (Yvelines).

500 sampling

The mission of providing permanent monitoring requires an extremely rigorous approach in laboratories for the analysis of samples. The Institute’s

I R S N 2005 ANNUAL REPORT

10,000sourcemovements

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Permanent monitoring in the field of radiological protection

laboratories which perform these measurements
are subjected to an approval procedure which testifies to the quality of the results provided (see thechapter on Quality, part 2). In 2005, nearly 100,000
measurements were carried out as part of thismission.

basis, regarding the identification of the activity ofvarious samples. The results obtained are thenanalysed to confirm their performance levels and,
where applicable, pinpoint areas for improvement.
Owing to positive feedback on the operation of thisnetwork, it will be extended to all the Institute’s
measuring laboratories.

Preparing a full inventory of theInstitute’s measuring capabilities[FOCUS]

In order to be prepared for an accident which may
require the mobilisation of all its measuring capabilities, the IRSN started drawing up a detailed
list of its facilities and organising them into networks. The inventory of environment measuring
facilities was completed in 2005.
The laboratories in this “environment” network takepart in comparative tests, organised on an internal

Examining the objectives ofenvironmental monitoring
Changes in the industrial context, the partial withdrawal of
logistic support for Ddass, technical developments andimprovements in knowledge regarding radioecology have led the
IRSN to redefine the basis of its mission to monitor radioactivity
in the environment and the methods of performing that mission.
Four main objectives were identified in an appraisal conducted in2005:> monitoring to check for any abnormal situation concerning thewarning devices used for the early detection of such a situation;> observation of environmental compartments to precisely
characterise their radioactivity;> contribution to knowledge regarding radioactive releases, in
support of DGSNR in its work to check compliance withregulations in that field;> supply of information on the state of radioactivity in theenvironment to ensure an optimal response to statutory
requirements and the preoccupation of inhabitants.

PERMANENTMONITORINGIN MATTERS OF
RADIOLOGICALPROTECTION
The monitoring missions entrusted to
the IRSN in the field of radiologicalprotection concern the management ofionising radiation sources and theassessment of doses received by workers
and the public.

Source management
The IRSN manages the national inventory of ionising radiation sources. In this context, the Institutedealt with the following cases in 2005:> 28 requests to use sources;> 14 requests for dispensation from CAMARI
certification (for the handling of industrial
radiography and radioscopy equipment);

The various technical and geographic redeployment operations
began in 2005 in order to meet these objectives. A notable resultof this activity will be the development of automatic water
sampling systems.
SISERI system to centralise dosimetric dataon workers.

92 ]I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONS

8 enquiries on technical or statutory subjects;
10 source inventories for nuclear power plants(CNPE).
>>

Telluric radiation

Furthermore, 6,700 source user dossiers weremanaged: 1,900 were modified and more than
10,000 source movements were recorded (procurements, recoveries,imports, exports, etc.).

Dosimetric monitoringof workers
In accordance with decree no. 2003-296 of
31 March 2003, the IRSN collects, consolidates andbacks up data on the individual dosimetric monitoring of workers exposed to ionising radiation.
The dosimetric data, for more than 255,000 active
workers, are collected on a monthly or quarterly
basis for passive dosimetry and on a day basis for
operational dosimetry.
At the request of the Staff relations department,
the IRSN set up the SISERI information system tocentralise the dosimetric data on French workers.
After a six-month pilot phase, the system wasofficially commissioned in February 2005. The
acquisition of data supplied by the various operators and dosimetry laboratories is conducted inaccordance with protocols defined by the Institute.
Dosimetric data on individuals can be released tooccupational physicians and radiological protection personnel concerned via a secure access system.
The operational implementation of the SISERI
system will, in time, provide better statistics on
professional exposure.

Cosmicradiation

0.5
0.3
Radon

1.4

0.2

Water
and food

0.8
MedicalTotal
3.3 mSv/an

0.03
Other (discharges from installations,fallout from atmospheric testing, etc.)
Annual doses (mSv/an). Source : IRSN, 2005

Distribution of the exposure to ionising radiation forthe population of France.

Assessment of exposure levels
for members of the public
The mean effective dose received in France fromionising radiation sources was reviewed by the IRSN
in 2005. The new estimate takes into account the
average dose corresponding to medical exposures,
which is now estimated to be 0.8 mSv per person
per year.
All in all, the mean effective dose received in
France is 3.3 mSv per person per year.This value is very
close to the world average figure of 3.4 mSv/yearlited by Unscear.

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R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Contributing to public information and transparency

Contributing
to public informationand transparency
Teaching and transparency are two principles governing the IRSN’s actions withsociety. The Institute therefore makes a point of including nuclear and radiologicalrisks as part of the overall picture for all industrial risks. At the same time, through its
range of activities, it places its expertise at the service of professionals (in fields
including medicine, nuclear safety and the environment) and the public.

PUBLICINFORMATION“Nuclear under close
surveillance”

road show

3,360 visitors(6,500 in 2004)
including 340 school
pupils (1,120 in 2004)
2 cities visited(4 in 2004)

5 conferences

Public information, which is laid down as
one of the IRSN’s missions in its decreeof creation is aimed at making the stateof knowledge and expertise in the fieldof nuclear and radiological risks as widely
accessible as possible. In this spirit, theInstitute continued in 2005 with its policyof publishing for various categories ofthe public, the organisation of exhibitions and its participation in fairs andevents, as well as making a special effort
to develop its web portal.

organised (15 in 2004)

831 requests for
information
processed via the contact
box on the website(778 in 2004)

14,000copies of theannual report
distributed(12,000 in 2004)

Participation in 5

professional exhibitions
and public events(5 in 2004)

94 ]Well-earned success for the road show in Bourges (Cher).

I R S N 2005 ANNUAL REPORT

Direct information
As a nuclear and radiological risk expert for the
benefit of society, the IRSN organises and participates in events enabling it to come into contact
with the public. In 2005, the Institute updated theASN/IRSN road show, known as “Nuclear underclose surveillance “ with modified Chernobyl,
Environment and Health modules. This exhibition,
featuring round tables and conferences, attracted
2,000 visitors in Evry (Essonne) and 1,100 visitors
in Bourges (Cher).
In addition, the IRSN set up a teaching area which
welcomed 10,000 visitors at the 1st European
Research and Innovation exhibition. At the Festivalof Science organised by the French Ministry of

RESEARCH AND PUBLICSERVICE MISSIONS

Research, the Institute organised a stand in the
Luxemburg Gardens in Paris and supervised a sciencebar focusing on the topic of risk perception.

The Institute also participated, for the first time, inthe 11th Nureth congress attended by specialists
in nuclear reactor thermal-hydraulics in Avignon(Vaucluse).
With its Belgian and German counterparts,AVN and
GRS, the IRSN jointly organised the EUROSAFE
forum in Brussels (Belgium) on 7 and 8 November
2005. For the occasion, the forum focused on
improving safety: foundations, strategies anddeployment. This forum also has a twice-yearly
publication, the EUROSAFE Tribune, and a website:www.eurosafe-forum.org.

The IRSN’s web portal

Inauguration of the AMANDE and EPICUR
installations in March 2005, in Cadarache(Bouches-du-Rhône).

Information through the media
The IRSN took steps, in 2005, to optimise its responsiveness to requests from the media and to
invite journalists to events such as visiting two of
its new installations (AMANDE and EPICUR) andpress conferences including, in particular, thoseconcerning the publication of its 2005 barometerand reporting on the Franco-German initiative on
the consequences of the Chernobyl accident.
As a result of this effort, the number of articles
published mentioning the IRSN increased by morethan 45% (making a total of 220 articles publishedin 2005 compared with 150 the previous year).The
topics attracting the greatest media coverageduring this period included the safety of nuclear
installations, the environment and transparency.

The IRSN’s web portal (www.irsn.org) attracted
an increasing number of hits (+ 25.5%), rising from
689,038 sessions in 2004 to 864,896 in 2005. Last
year, the Institute restructured this portal (whichfeatures about 3,000 pages in French and 500 in
English) to improve its accessibility for the public,
the press and professionals concerned by theInstitute’s fields of activity.
In this context, the following websites came online: www.irsn.org/eau (concerning the monitoringof radioactivity in water, sludge and sediments)
and www.irsn.org/formations (covering the whole
IRSN range in the field of training).
The new portal has new features, such as a newsletter, a download centre and the synchronisationof data between all the Institute’s internet andintranet sites.

24,500information booklets
distributed(30,000 in 2004)
and 22,150
brochures on theInstitute’s training
activities andservices distributed(4,500 in 2004)

868,000hits

in 2005(690,000 in 2004),
including 250,000 single
visitors(195,000 in 2004)
on the Institute’s website:www.irsn.org

76,966
hits(55,548 in 2004),
including some 3,262
single visitors
per month(2,000 in 2004),
on the IRSN’s
scientific website

Information for professionals
The IRSN organised information areas at various
trade fairs and congresses last year: at Pollutec, aninternational exhibition of equipment, technologies
and services for the environment (Paris), the Institutereceived nearly 4,000 visitors on its stand built
around three topics: presentation of the Institute;
expert assessments and services; contracts.
At the Medec professional health exhibition (Paris),the IRSN welcomed about 1,000 visitors.

Mrs Nelly OLIN, Minister for Ecology and Sustainable Development
visiting the IRSN stand at Pollutec in December 2005.

I R S N 2005 ANNUAL REPORT[ 95

[FOCUS][R E S E A R C H A N D P U B L I C S E RV I C E M I S S I O N S
Contributing to public information and transparency

Pilot project with CLIs concerning
radioactivity in the environment in the
Loire basin

OPENING UP
EXPERTISE FOR
SOCIETY
In 2005, the opening-up of the IRSN’s
expertise for society resulted in various
types of actions involving associations,
unions representatives and other expert
institutes. Above and beyond the pilot
projects which may lead to the formingof pluralist expert groups in order to deal
with complex or controversial subjects,
the IRSN’s commitment is reflected byits participation in networks for information, optimisation and feedback, andthe creation of such networks.

The site at Saint-Laurent-des-Eaux. The first CLI was mobilised
to set up the pilot project conducted in the Loire basin.

Along with the CLIs of the Loire basin, the IRSN started a projecton the utilisation and intelligibility, for local actors, ofmeasurements of radioactivity in their environment. The purposeof this project is to create environment follow-up tools on thebasis of the measurements carried out by the IRSN and, moregenerally, those that will be available in the context of the national
network to measure radioactivity in the environment.
After explaining this approach to CLIs, the IRSN held discussions
with them and, on that basis, it was able to identify their exact
expectations. Future discussions will be held to ascertain the
expectations of CLIs for the whole Loire basin and, subsequently,
on the national level with Ancli.

In the context of the protocol signed with the
IRSN in 2003, the French National Association for
Local Information Commissions (Ancli) called upon
the IRSN, in 2005, for assistance with the governanceof nuclear waste management.
The project includes two parts: the preparation of
a seminar on “international feedback on participative governance for nuclear waste management”
and follow-up of the public debate on radioactive
waste management to consider the emergence ofinnovative processes allowing society to become
involved.
For the IRSN, this means contributing to the development of a culture of participative governance

Designers,
manufacturers/constructors
Operators

Researchon risks

Parliament

IRSN, public
expertise

Publicauthorities

Stakeholders(CLI)
Civil society

Nuclear safety depends on the vigilance of four
parties: the operator, the public authority, thepublic expert and the stakeholders in civil society.

96 ]I R S N 2005 ANNUAL REPORTRESEARCH AND PUBLICSERVICE MISSIONSIn addition, the IRSN is examining developmentsin the governance of hazardous activities andsituations along with five national expert institutes(Afsset, Ineris, Inrets, INRS, InVS).
For the Institute, the aim of this co-operation is toplace its approach in perspective with those ofother public institutes and to join them in strategic
discussions which could lead to joint action and to
exchanges on these new modes of governance.

The IRSN’s participation in the publicdebate on the first-off EPR projectin Flamanville[FOCUS]in its own organisation and making its work in thefield of radioactive waste and its governanceaccessible to civil society. Furthermore, the IRSN has
started a collaboration with unions representatives
on the monitoring of the exposure of workers toionising radiation.This entails a mission conductedby the Institute for the benefit of workers and publicauthorities as well as to the stakeholders, employers
and trade unions.

The safety of the EPR project is assessed by the IRSN.

The IRSN was mobilised to provide clearly understandable
information for the Special Commission for Public Debate (CPDP)
and to members of the public taking part in the debate whichstarted in mid-October 2005. In the participant’s guide drawn up
for this occasion, the IRSN summarises the general safety aims
adopted for EPR type nuclear power reactors.
The Institute emphasises certain important points of its
assessment of the safety of the EPR project and points out that it
worked in co-operation with the Group of Scientists for
Information on Nuclear Energy (GSIEN) and Ancli on this matterand that it is ready to continue work in that vein.

I R S N 2005 ANNUAL REPORT[ 97

Key figures 2005
Key figures 2004

9 national nuclear crisis exercises
9

2 real actions taken by the CTC
2

25 meetings held by the standing advisory groups
24

98 ]

I R S N 2005 ANNUAL REPORTTECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTECHNICALSUPPORT AND
ASSISTANCEFOR PUBLIC
AUTHORITIESWhether they act for the authority (technical assistance)or as technical support, the IRSN conducts its activities inpartnership with the public authorities.
In order to advance in the quality of its expertise, the IRSN
conducts a technical dialogue with industrialists and formalizes its technical doctrine by the publication of documents.

100

Technical support with regard to nuclear
and radiological risk

126

Operational support in the event of a crisis
or radiological emergency

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T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

Technical support withregard to nuclear andradiological risk
The technical support provided by the IRSN to the authorities consists of expert
assessment of technical files submitted by industrialists. These files concern thesafety of reactors, fuel cycle plants, transport and dismantling , as well asradioactive waste management. They also concern protection of man andthe environment. Following these expert assessments, the IRSN puts forward
recommendations on the arrangements proposed by the industrialists and the
medical sector to control these risks. These recommendations are sent to theauthorities or presented to the competent Standing advisory group of experts.

SAFETY ANALYSIS OF
NUCLEAR REACTORS

688 technical reports
to the public authorities
excluding defence-related
activities (608 in 2004)

630 participations in

inspections of basic nuclear
installations(almost 600 in 2004)

143 test reports

regarding cross-comparison
exercises of environmental
radioactivity measurements(107 in 2004)

110

recommendations forradiological protectionof man (134 in 2004)

The IRSN provides technical support to
the DGSNR(5) as regards the safety assessment and radiological protection in the
58 reactors in operation on the French
nuclear power plants. It also assesses thesafety of experimental reactors and thatof the EPR reactor. In 2005, the Instituteworked hard to review the safety of
1,300 MWe reactors with a view to theirsecond 10-yearly outage programmes,
and that of the 900 MWe reactors witha view to their third 10-yearly outage
programmes.

Reactor safety reviews andassociated safety reports
Each reactor in operation undergoes a safety review
every 10 years. This review includes checking thatthe power plants remain in conformity with theirdesign and operation standards, and studying any
possible changes to these standards and the associated modifications. These modifications aim at
improving the safety of the reactors.They are basedon feedback, advances in knowledge and new safety
provisions adopted for the most recent reactors
whenever that is technically feasible and there is a(5) DGSNR: General department for nuclear safety and radiological protection.

100 ]significant gain in terms of safety. During the year
2005, the IRSN continued its review of
900 MWe reactor safety with a view to their third
10-yearly outage programmes (VD3 900) (see Focus
opposite). Finally, as regards the second 10-yearly
outage programmes for the 1,300 MWe reactors,
the Institute completed the examination of safety
review studies, modifications and the standard
safety report.

I R S N 2005 ANNUAL REPORTThe safety report is used as a basis for the review.

End of study
analysis

EDF studies - IRSN examination
2002

2003

2004

2005

Definition of the “VD3 900”
Design and development studies
on response projects by EDF

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESEDF : proposed
approach andprogramme[FOCUS]

Safety review associated with the third 10-yearly outage
programmes of 900 MWe reactors

Implementationof series “VD3 900”
on TTS (lead unit)

40 years
Start of thefor the most
VD3 900 ECOT
recent 900 MWeunit complianceStandard 900 safety
reactoranalysis(TTS (lead unit)- report edition VD3Applicabilityofthe
2 cycles“VD3 900 MWe”
benchmark18 months
2006

2007

2008

2028

End of EDF studies

Guidelines
Severe accidents
PSA - levels 1 & 2Containment
Fire / Explosion
StudiesAG

AgeingMeetings held by the Standing
advisory group of experts fornuclear reactors

Guidelines & studies: 2.5 years

Development studies: 3.5 years

The schedule of the safety review associated with the third 10-yearly outage
programmes of 900 MWe reactors.

In early 2005, the IRSN completed the main investigation phase of the safety review studies
associated with the third 10-yearly outage programmes for 900 MWe reactors (VD3 900). This
ended with seven meetings of the Standing advisory group of experts for nuclear reactors.
These studies consisted in checking conformity of the 34 900 MWe reactors to the applicablesafety requirements and reassessing these requirements in the light of feedback and changing
technical knowledge. These studies mainly concerned:> probabilistic safety assessments (PSA) quantifying the risks of core meltdown and release ofradioactive products;> internal hazards in the installations such as fire (which gave rise to a specific PSA in the IRSN)
and explosion;> climatic hazards which may affect all safety functions on a site;> earthquake resistance of the installations;> design of many items of equipment, such as the security injection circuit, containment,
the spent fuel storage pits and their cooling systems;> severe accidents.
This work has led to around 20 modifications which will be implemented during the next
10-yearly outage programmes (from 2009) to guarantee and improve the safety of 900 MWe
reactors.

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T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

Examination of programmes ofwork and inspections carried out
during refuelling shutdowns andreactor maintenanceIn 2005, 52 planned shutdowns lasting from three
weeks to three months were examined by the IRSN.
In each case, the Institute studied the work andinspection programmes planned by the operator,
monitored the performance of these operations,
examined the handling of deviations identified
and the results of restarting tests.

Fan

Rotor

Drive
shaft

[FOCUS]

In particular, the IRSN examined the actions decided
by EDF to deal with the generic anomaly affecting
motor pump units in some backup circuits of the
34 900 MWe reactors. This incident was reported
as class-2 significant event on the INES scale in
December 2005.

FOCUS

p.54

Risk of spent fuel pit drainage
In 2005, as part of the safety review associated with the third
10-yearly outage programmes for 900 MWe reactors, the IRSN
showed that some accident sequences could lead to a rapid
drainage of the spent fuel pit. The examination of feedback also
revealed that many precursor events had occurred and that some
had already led to considerable draining.
As well as the total loss of cooling of the stored fuel, one of thepossible consequences of these events would be the partial or
total dewatering of one or several assemblies during handling(see Focus “Spent fuel pit drainage accident”*).
The IRSN analysis led EDF to implement provisions to strengthen
prevention on all nuclear power plant reactors in the installedbase from 2006 and to facilitate management of such an
accident situation.
In the medium-term, other modifications will be implemented
on the 900 MWe reactors during the third 10-yearly outage
programmes, the first of which will take place in 2009.
In particular, they concern rapid isolation of the reactor’s spent
fuel pit in the event of draining, removal to a safe position ofan assembly during handling and monitoring of the pit level fromthe control room.

102 ]I R S N 2005 ANNUAL REPORT

Details concerning the anomaly on the motor
pump units were published on the IRSN website.

Examination of general operating
rules (GOR)
GORs are used to ensure compliance during operation of the limitations fixed on design. These rules
should evolve according to the modifications madeto the reactors and to feedback.
In 2005, the IRSN sent more than 100 recommendations on the acceptability, from the safety pointof view, of the evolutions proposed by EDF or
occasional concessions to the GOR requested
following operating contingencies. The Instituteexamined the file regarding the restarting ofreactors in the event of a generalised loss of theelectricity network; its recommendation led EDF
to modify its proposals.

Analysis of reactor operation
experience feedback
The IRSN examines the feedback from reactor
operation, in particular the events and anomalies
affecting them.
The 760 significant events reported by EDF in2005 were examined and described in an IRSN
computer database. The most characteristic incidents of safety failings were or will be subjected tothorough analysis, and in some cases considered
to be precursors, probablistic studies will beIn 2005, the IRSN supported basic nuclear
installation inspectors in the preparation of nearly
300 monitoring inspections on EDF reactors. The
IRSN accompanied the inspectors for some of thoseinspections.

On 30 September 2005, when reactor no. 1 in the Nogent-surSeine (Aube) power plant was restarting following a refuelling
shutdown, successive human and material failures led to a spill of
hot water from the secondary circuit in the “electrical” building.
Untimely orders caused automatic shutdown of the reactor andstarting of the safety injection system. In addition, the sudden
appearance of a “high neutron flow” alarm caused the triggeringof the internal emergency plan and the implementation of thenational crisis organisation.
The IRSN’s Technical Crisis Centre was thus activated from 9 am
to 3.15 pm and on 3 October 2005, the Institute participated in
an inspection of the damaged areas. The IRSN then launched anin-depth analysis of this severe incident. If the consequences ofthe leaks had been more serious, the failure of other electricalswitchboards which remained operational on 30 September,could have made control more delicate. During the meeting of
7 December 2005, the IRSN presented its opinion to the membersof the Local Information Commission (CLI).

Protection of reactors against
external hazards
In 2005, the IRSN continued examining theprotection of nuclear power plants against external
hazards. In particular, it examined the autonomy
of reactors and sites against natural hazards which
may simultaneously affect several reactors. In addition, the Institute analysed the doctrine proposedby EDF against the risks of oil spills and flooding.
Moreover, in an international working group, the
IRSN participated in the review of IAEA guidelines
on the protection against risks of flooding.

The IRSN analyses the dossiers sent by EDF.

Safety assessment of the EPR
nuclear reactor project
Since the drawing up of Technical Guidelines in
October 2000, and pending a request for authorisation for an EPR-type reactor in France, the IRSN
has continued to examine the safety of this reactor
project based on technical dossiers which:> deal with compliance with general safety
objectives;> concern innovative technical solutions;> concern provisions which have evolved since
the technical guidelines were drawn up;> describe the evolutions implemented in thereactors in operation.
During the year 2005, a set of technical dossiers
was thus examined by the IRSN, and was presented
and discussed during meetings of the Standing
advisory group for nuclear reactors. These files
concern:> radiological protection of workers in normal
operation;> qualification of equipment to accident
conditions;> “failure prevention” for the main steam pipes;> “practical elimination” of core meltdown
situations with containment by-pass;

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TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESMonitoring inspections

Incident in Nogent-sur-Seine[FOCUS]

conducted to assess their severity in terms of riskof damage to the reactor core. Furthermore, the
IRSN sends reports on the most significant incidents
to the IAEA, in accordance with the terms of theinternational Incident Reporting System.
In order to obtain an overall appreciation of operating safety evolutions in the power plants, the
IRSN has developed a statistical events analysis tool
enabling indicators to be drawn up. These tools
were used in 2005 to conduct a statistical analysisof the incidents occurred between 2000 and 2002.
This work will be completed based on statistical
data regarding events occurred from 1997 to 1999
and from 2003 to 2005.

[T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

> safety requirements for the design of civilengineering works;> design provisions regarding heat-wave situations;> dealing with a significant breach in the cooling
circuit during shutdown;> architecture of command-control systems;> the design of the shutdown station, the pumping
station and the corium recovery system;> principles of the preventive maintenance performed with the reactor in power operation.
In addition, the Institute participated in drawing
up several technical assessment reports presented
to the permanent nuclear section of the Central
committee for pressure vessels. These reports deal
with the examination of design choices for somemajor components such as steam generators, etc.

In 2005, recommendations were made by the
IRSN on the EPR safety standard and on assessment methods for radiological consequences in
accident situations.

Follow up experimental reactors[FOCUS]

The IRSN carries out safety expert assessments on
research reactors and the PHENIX fast-neutron
reactor operated by the CEA and the high-flux
reactor (RHF) in Grenoble (Isère), operated by the
Laue-Langevin Institute.
In 2005, the Institute’s expert assessment work
mainly concerned the MASURCA reactor, in
Cadarache (Bouches-du-Rhône), for which a safety
review is in progress.The IRSN examined the review
procedure selected by the CEA and studied therelevance of orientations regarding modifications

104 ]Bottom view of the MASURCA reactor, during
insertion of fuel rods.

to the plant planned by the operator as part ofrenovation work. Moreover, the IRSN examined
the application for authorisation to install a core
representative of the fast-neutron, gas-cooled
reactors; these reactors are being studied within
the framework of the international R&D forum“Generation IV” dedicated to studying reactors of
the future.
In addition, the IRSN issued recommendations
concerning the disposal of irradiated fuel elementsfrom the OSIRIS reactor in Saclay (Essonne), andthe IRIS TÜM experimental radiation.
In 2005, the Institute analysed the incidents which

Seminar in China on the EPR reactor project
In March 2005, a seminar was held in Beijing on the EPR project. Organised jointly by the DGSNR andthe IRSN, the aim of this seminar was to present the safety options and design principles of the EPR
reactor project to the Chinese safety authority NNSA, and its technical support.
At the NNSA’s request, this seminar was held before the Chinese authorities conduct an assessmentof the proposals submitted by the various constructors in reply to the call for tender issued by China
to build 3rd-generation reactors.
During the seminar, the participants from the DGSNR and the IRSN presented the project’s assessment
approach and shared their experience of the safety assessment, with their Chinese counterparts, on
major design issues.

I R S N 2005 ANNUAL REPORTDate ofmeetingExamination of commissioning of the two Civaux reactors

20/01/2005

Examination of the results of level 1 and 2 probabilistic safety assessments
for 900 MWe reactors

03/02/2005
10/02/2005

Examination of the containment behaviour of 900 MWe reactors

03/03/2005

Examination of the improvement of knowledge on the risks of fire and protectionof installations against explosions which may occur on a site

10/03/2005

Conclusion of studies of the safety assessment associatedwith the third 10-yearly outage programmes for 900 MWe reactors “VD3 90”

24/03/2005
31/03/2005
21/04/2005

Examination of operating experience from French and foreign pressurised water reactors
during the period 2000 to 2002 (2nd session)

16/06/2005

Continuation of the safety assessment of the EPR reactor project (3rd meeting) in particularconcerning radiological protection, risk of bypassing containment and equipment qualification

05/07/2005

Human and organisational factors awareness day

20/10/2005

Continuation of the safety assessment of the EPR reactor project (4th meeting) in particularconcerning control and instrumentation, corium recovery system, the principles
of preventive maintenance

01/12/2005

Safety review associated with the second 10-yearly outage programmes of 1,300 MWe reactors

22/12/2005

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESObject[FOCUS]

Standing advisory group for nuclear reactors

have occurred in the PHENIX plant in Marcoule(Gard), since its restarting in 2003, in particular
those regarding safety threshold rules. In general,these incidents revealed a lack of experience due
to renewal of the teams.
The IRSN sent a recommendation on draft technicaldesign guidelines for the experimental devices in
the CEA reactors in general. It also examined themethods for reporting “significant” events and the
documents regarding safety reviews.

The PHENIX reactor is being monitored by the IRSN.

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T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

SUPPORT FOR
THE SAFETY ANALYSIS
OF REACTORS IN
OPERATION
In 2005, the IRSN continued its activities
in support of the safety analysis ofreactors in operation, in particular in thefields of civil engineering, probabilistic
safety assessments and thermalhydraulics. The Institute also helped toprepare meetings of the permanent
nuclear section of the Central committee
for pressure vessels.

Civil engineering
In 2005, the IRSN continued the review of theseismic behaviour of civil engineering structures:> for the 900 MWe power plants in Fessenheim(Haut-Rhin) and Bugey (Ain);> for electrical buildings and machine rooms in
1,300 MWe power plants.
For the EPR project, the Institute examined therequirements retained by EDF for the design basis
civil engineering works and the design principles ofthe equipment access hatch in the reactor building.
Finally, the IRSN examined the project to revise
the basic safety rules regarding aseismic design of
nuclear power plants, with a view to presenting itto the standing advisory groups in early of 2006.

Preparation of meetings of thePermanent nuclear section (SPN)of the Central committee forpressure vessels (CCAP)
The SPN held seven meetings during 2005. Within
this framework, the IRSN contributed to the investigation and to the reports concerning:> the design of some components in the EPR reactor
project (such as control rod drive mechanisms or
steam generators);> the conditions to be associated with the implementation of the failure prevention hypothesis forthe design of the EPR reactor project;> regulatory reference dossiers regarding the main
secondary circuits in pressurized water reactors;> ageing under irradiation of 900 MWe reactor
vessels.

106 ]I R S N 2005 ANNUAL REPORT

Level 1 probabilistic safetyassessments
Probabilistic safety assessments (PSA) contributeto understanding the arrangements adopted by
the operators. In particular, they enable problems
identified during the design or operation of plants
to be better prioritized, and hence to define themost urgent improvements to be made.
The lessons learnt from level 1 PSA on 900 MWe
reactors were used in 2005 during the safety
review on the VD3 900 and may lead EDF to add
to the modifications associated with this review.
A revision of the level 1 PSA review for 900 MWe
reactors is in progress at the IRSN to take accountof the follow-ups to this review and to obtain arepresentative study of the condition of the plants
following their third 10-yearly outage programmes.

Thermal-hydraulics
In support of the safety analysis of pressurised
water reactors, the IRSN is conducting studies using
thermal-hydraulic software.
In 2005, in collaboration with the Finnish safety
authority STUK, the Institute carried out calculations regarding the steam generator tube rupture
accident, to assess the differences in accident
management, between the Finnish EPR nuclear
reactor project and the French EPR nuclear reactor
project.

Z

Irradiatedpart ofthe vessel

Irradiation makes the reactor vessels fragile.

Radiological consequences of accidents

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESPSAs consist of a systematic investigationof accident scenarios.
Level 1 PSA identifies the scenarios which
may lead to a core meltdown anddetermines their frequencies.
Fire PSA deals with the risks associatedwith fire.
The level 2 PSA can be used to evaluate thenature, extent and frequency of radioactive
discharges outside the containment.

[FOCUS]PROBABILISTIC SAFETYASSESSMENTS (PSA)

In order to prepare the analysis of future EDF
studies, the IRSN initiated expert assessments of
the latest version of the CATHARE software in2005 and appraisal of the associated uncertainties(participation in the OECD BEMUSE project). The
Institute also continued studies into steam pipe
break accidents.
Assessment of radiological consequences: a major study forthe environment around nuclear power plants.

The lessons learnt from the level 1 PSA for
900 MWe reactors were used during the safety
review associated with the VD3 900.

The radiological consequences of accidents were until now
calculated according to two different methods, one French forreactors in operation, the other German for the EPR reactor
project. EDF wishes to harmonise these two methods and use thecommon method mainly derived from the French one, inparticular for the provisional safety report on the EPR reactor
project.
During 2005, the IRSN first examined the principles adopted by
EDF in view of this harmonisation. The Institute also studied theapproach chosen to carry out awareness studies presented in the
preliminary safety report for the EPR reactor project for all
accident operating conditions. The aim of these studies is toevaluate the impact of the chosen method on the results.
The IRSN then started to analyse the new assessment standard
for radiological consequences, which covers both the assessmentof the activity released outside the containment and thedosimetric impact on man and the environment. The Institutewill present its conclusions (excluding core meltdown situations)in 2006.

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HUMAN ANDORGANISATIONALRELIABILITY
2005 was marked by the continuing
development of the IRSN’s expert assessment activities in the field of human andorganisational reliability.

In-depth analysis of events

Nuclear auxiliary building control room.

AGEING OF
PRESSURISED WATER
REACTORS (PWR)
In line with the meeting of the Standing
advisory group for nuclear reactors,
regarding the method adopted by EDF
to control PWR ageing , the IRSN
conducted in 2005 the following additional studies:
examination of the relevance of R&D programmes and the means implemented by EDF to takeaccount of the ageing of 900 MWe reactors beyond
the 10-yearly outage programme;> suitability of monitoring methods for ageing ofactive components to demonstrate maintenanceof their reliability and their qualification to accident
conditions;> exhaustivity, quality and suitability of ageing
analysis sheets used by the operator.
The aim of these sheets, for each item of equipment,
is to show control of ageing given the knowledge
and in-service test programmes planned.
>

108 ]

I R S N 2005 ANNUAL REPORTFive significant safety events which occurred innuclear power plants were examined. The IRSN
reconstructed precise timelines of the actions
carried out by the operators, in parallel with theevolutions of the installation’s parameters. The
Institute examined the relevance of the corrective
measures implemented by EDF to prevent such
events from reoccurring. It recommended that
EDF strengthens its provisions intended to ensure
the quality of activity planning and preparation
phases. It was also able to confirm the central role
played by communication between the actors in
detecting and recovering from errors.

Operation feedback
During the meeting of the Standing advisory groupin June 2005 devoted to examining the operation
feedback from EDF nuclear power plants, threesubjects concerning human and organisationalreliability were examined:> the action plan implemented by EDF to improve
interventions which may lead to failures of electricalswitchboards and to improve operating procedures
to be applied to limit the consequences of such
failures;> the risk analysis approach implemented by EDF
to improve the preparation of interventions;> the ability of the operating manager and thesafety engineer to ensure, in coordination, their
missions in the field of safety.

Skills management
The IRSN examined the arrangements made by
EDF as part of its skills management policy and its
implementation on the sites. Unlike training policy,
the skills management policy gives a central place
to identifying the needs of the agents closest to
the field and enables skills needs to be anticipated.

The IRSN provides the DGSNR with technical support for the study of fuelmanagement provisions proposed by EDF
and, in particular, management changes
planned by the operator by 2007.
As part of fuel management changes, the IRSN
examined in 2005 the feasibility of the ALCADE fuelmanagement system planned for 1,450 MWe
reactors.The goal of EDF is to operate these reactors
in cycles of 17 to 18 months instead of the current
10 to 12 months. In its analysis, the IRSN in particular
brought to light:> reactor vessel modelling issues, in the thermalhydraulic code (CATHARE) used to evaluate the fuelcladding temperature, during a loss of coolant
accident.
> insufficiencies regarding the demonstration of
the conservatism of the study methods of the rod
ejection accident using 3D modelling;> lack of representativity of the tests required atdefining the criteria to be used for the study of theinteraction between pellets and cladding;> yet insufficient feedback concerning the behaviour, in normal operating conditions, of the newfuel assembly structure AFA-3GLr-AA in M5 alloy.
ALCADE management safety studies will be
examined in 2006 and a special meeting of theStanding advisory group for nuclear reactors will
be held on this subject.

ALCADE MANAGEMENT
This differs from current management:
an increase in the enrichment of uranium
235 from fissile matter from 3.4% to 4%;
an increase in the maximum discharge burnup
rate of fuel rods from 48 GWj/t to 52 GWj/t;renewal of the fuel by one third of the coreinstead of by one quarter of the core;
implementation of modified loading plans to
reduce the neutron flow on the vessel.
Compared to current management,ALCADE
management specifically means an increase in
the power differences in the core.

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESFUEL BEHAVIOUR IN
NORMAL AND
ACCIDENT OPERATING
CONDITIONSEXAMINATION OF
RISKS ASSOCIATED
WITH SEVERE REACTOR
CORE MELTDOWNACCIDENTS
The risks associated with severe core
meltdown accidents are continuously
examined by the Institute. This examination is supported by research anddevelopment programmes and regularmeetings of the Standing advisory groupof experts for nuclear reactors are held.
In 2005, the analysis of these risks was continued
as part of the safety review associated with thethird 10-yearly outage programmes for 900 MWe
reactors. In particular, during two meetings of theStanding advisory group of experts for nuclear
reactors (GPR), the lessons to be learnt from thelevel 2 PSA (see Focus*), and the “severe accidents”
standard (see Focus*)proposed by EDF . In addition,
as regards the EPR reactor project, the IRSN continued
to examine the robustness of the corium recovery
concept proposed by EDF. It also examined the
instrumentation provided to monitor the progressof a severe accident.

FOCUS

p.111

FOCUS

p.110

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[FOCUS][T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

FOURTH GENERATIONREACTORS“Severe accidents” standard

Lowestrate

Highestrate

Calculations of the distribution of steam and hydrogen inside
the reactor containment during a severe accident.

In 2005, the IRSN examined the “severe accidents” standard
proposed by EDF for its reactors in operation. This standard aims
at defining:> the approach and objectives sought by EDF in terms of
preventing and limiting the consequences of severe accidents;> the studies required to demonstrate that these objectives arebeing followed;> the practical provisions retained and their sizing bases.
In order to analyse this standard, the IRSN used the conclusionsof previous GPR meetings to examine the risks associated withsevere accidents, and the studies conducted to support its
level 2 PSA. Following this assessment, the Institute put forward
strong reserves as to the probabilistic objectives proposed by
EDF. It also underlined that, in its current state, the standard
presented a large number of issues still under investigation.
On this occasion, the IRSN also examined the new pressure andtemperature profile inside the containment proposed by EDF tocheck the behaviour of the equipment in a severe accident
situation. The IRSN considered that EDF needed to complete thelist of scenarios chosen to define this profile.

110 ]I R S N 2005 ANNUAL REPORTIn 2005, the IRSN signed collaborationagreements concerning fourth generation
reactors.
2005 saw the concrete signing of the Areva/IRSN
protocol governing exchanges on safety issues
associated with the Antares project (a very-hightemperature, graphite-moderated and heliumcooled reactor project). The Institute drew up asummary of the safety approach developed forFrench graphite-gas reactors and the associatedfeedback. The lessons learnt from this work will be
used within the framework of the exchange groupon the Antares project. In addition, the IRSN becamea partner in the integrated European RAPHAEL
project, which is developing research and development work to support in the design of hightemperature reactors.
At the same time, the IRSN made an initial comparison of the safety principles of six nuclear systems
chosen by the international “Generation IV” forum.

FranceCanadaU.S.A.

BrazilUnited Kingdom

MEMBERS OF
E.U.
THE GENERATION IV
INTERNATIONAL
Switzerland
FORUM

✹

Argentina
South Africa

Japan
South Korea

The FIG IV: an international initiative
to develop the next generation of
nuclear systems.

Using the level 2 PSA in safety analysis[FOCUS]SAFETY OF PLANTS,
TRANSPORT ANDDISMANTLING

Installations upstream of cycle
Areva is planning to build a new uranium enrichment plant (George Besse II facility) on the Pierrelattesite (Drôme), which will use the enrichment processby centrifugation.This process enables the quantityof gaseous UF 6 present in the installation to besignificantly reduced. In 2005, the IRSN examined
the preliminary safety report for this new installationand presented its recommendation to the competentStanding advisory group. Significant improvements
in terms of reducing exposure to ionising radiation,
limiting the risks of fire and resistance to external
hazards have already been made by the operator
following these exchanges with the Institute during
the investigation of this issue.
For its part, FBFC is planning to increase the production capacities in its fuel assembly production
plant in Romans-sur-Isère (Drôme). The IRSN
examined the safety report for this project, whichaims to raise the plant’s annual capacity from1,200 to 1,800 tonnes for the manufacture of uranium oxide powder in the conversion workshop,and from 820 to 1,400 tonnes for the manufactureof fuel assemblies. Following its expert assessment,
the IRSN presented its recommendation to thecompetent Standing advisory group, which concluded that the capacity increases requested by theoperator were possible within acceptable safety
conditions, in particular given the planned renovation of the industrial plant. Moreover, the IRSN
formulated recommendations regarding the cleaning operations of the plutonium technology workshop (ATPu) in Cadarache (Bouches-du-Rhône).

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESThe IRSN provides the expert assessments of technical dossiers transmitted
by nuclear installation operators and by
applicants for radioactive materialtransport packages. The Institute alsostudies the risks of dispersion of radioactive materials and criticality present
in most installations and during transport.
The IRSN draws up reports on internal
emergency plans (PUI) for sites containing
nuclear installations.
Home page of the user-friendly PSA 2 application.

The level 2 PSA is used to assess the frequency, extent andmoment of appearance of discharges into the environment
during core meltdown scenarios identified in the level 1 PSA.
During 2005, the IRSN continued to update the level 2 PSA it isconducting for 900 MWe reactors. The aim by the end of 2006 is
to avail of a version which takes account of all accident initiatorsfrom the level 1 PSA and the “events” management.
The IRSN also started preliminary work to carry out a level 2 PSA
for 1,300 MWe reactors.
On the occasion of the safety review associated with the
VD3 900, for the first time EDF presented a level 2 PSA,
conducted in order to prioritize the risks associated with severe
accidents and to evaluate the interest of possible modifications
to the design or operation of the reactors.
To examine this study and the lessons learnt by EDF, the IRSN
based itself largely on its own level 2 PSA. The Institute put
forward recommendations to improve EDF’s study and its
approach to use. Lessons have nevertheless already been learnt
for the VD3 900. In particular, the operator has been asked to
study the interest and feasibility of provisions enabling
discharges of iodine to be limited in the event the drainingfiltration device in the containment is opened.

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Installations “downstream” of cycle
Irradiated fuel reprocessing installations
For installations downstream of the fuel cycle, amajor portion of the IRSN’s work was devoted to
examining changes in the operating ranges ofirradiated fuel reprocessing installations UP2-800
and UP3-A in La Hague (Manche). Four specificdossiers were examined by the Institute in 2005
which led to the publication of four interministerial
decrees. In particular, the IRSN examined changes
in the risks related to heat releases and radiolysis,risks of external exposure and criticality risks andthe provisions made by the operator to protect
workers and the environment.
In 2005, the IRSN also investigated a dossier regarding the waste management policy at the La Hague
site. The Institute estimated that the plant’s means
and the changes in the short- and medium-term
appear globally coherent with the strategy proposed
to process, package and store waste related toprogrammes that the plant is planning to implement over the coming years.
The IRSN gave its opinion on the safety of recovery
operations for “old” radioactive sludge planned by
the operator. This sludge comes from waste
treatment produced by the UP2-400 plant, currently
shutdown. The operator is planning to hot precoat
it with bitumen within the STE3 plant. The mainrisks examined by the Institute were risks of fire andexplosion due to the reactivity of the chemical
species coated. This expert assessment was basedin particular on feedback from the Tokaï-Muraaccident in 1997.The IRSN concluded that the safety
demonstration presented by the operator was
insufficient, and that additional studies were necessary to justify control of the above-mentioned risks
and, if necessary to adapt the process envisaged.
The Institute estimated that the operator would
have to further its knowledge of the chemical natureof the sludge and the hazardous phenomena
associated with the hot pre-coating process.
Finally, the IRSN examined the Definitive End of
Operation (DEO) dossier for installations at theUP2-400 plant in La Hague, describing the operations planned during this phase, the organisational
modifications announced and their scheduling,
and the planned state of the installations at theend of the DEO phase.The Institute estimated thatthe operator would have to propose a sufficiently

112 ]I R S N 2005 ANNUAL REPORT

extensive change in the operating safety standard
for the installations concerned and demonstratethat the provisions put in place will enable these
operations to be conducted safely.
Long-term disposal
The IRSN examined the safety orientation dossierspresented by the CEA as part of the 3rd axis of thelaw of 1991, regarding the packaging and long-term
disposal of radioactive waste. This investigation
looked at four concepts for long-term disposal
installations for HLLL or MLLL waste, on the surface
or subsurface, on virtual sites.
On this occasion, the Institute provided an initial
appreciation of the relevance of the design provisions
envisaged by the CEA, pending the drawing up ofsafety option dossiers for given sites.

Safety of laboratory anddismantling of definitively
shutdown nuclear installations
For laboratories, the IRSN examined in 2005 thesafety of operations safety of CEA installations in
Saclay (Essonne) and in Cadarache, and of the Large
national heavy ion accelerator (GANIL) in Caen
(Calvados), the SOCATRI uranium recovery andclean-up facility in Tricastin (Drôme), and finally,
the EDF irradiated materials workshop in Chinon(Indre-et-Loire).
In addition, the main nuclear operators followed
significant nuclear plant dismantling programmes
which by 2025 should lead to the dismantling ofabout 40 basic nuclear installations. Within thisframework, the IRSN examined the dossiers regarding
the gas diffusion facilities (UDG) in Pierrelatte(Drôme), the EL4 reactor in Brennilis (Finistère) andthe CEA’s BNI in Fontenay-aux-Roses (Hauts-deSeine).

Safety of radioactive wastetransport
The IRSN examined over 100 safety dossiers
regarding civilian transport of radioactive waste
in 2005 (applications for approval, extension of
approval, validation, certification, special arrangement or transport).
A special study to evaluate the risks of sinking in
unconsolidated strata of irradiated fuel transport
packages was completed in 2005.Various accidents

The IRSN examined the provisions chosen by nuclear
operators to ensure the confinement of radioactive
or toxic materials, in order to protect workers, thepublic and the environment. In 2005, expert assessments on this issue in particular concerned theGeorges Besse II facility project in Pierrelatte,
installations being dismantled (UP2-400 plant in
La Hague, EDF first generation reactors), deep
disposal projects for radioactive waste, and ancillarybuildings for EDF 900 MWe reactors.

Civil engineering expert
assessments
Expert assessments regarding civil engineering offuel cycle installations, laboratories and installations
for waste management mainly concerned the risks
associated with external hazards such as earthquakes
or explosions, and monitoring of strengthening work
on existing installations.Within this framework, the
IRSN examined the Georges Besse II facility projectin Pierrelatte, FBFC installations in Romans-surIsère, CEA installations Atalante Marcoule (Gard)and LECI in Saclay.

Expert assessments of criticality
risks
The prevention of criticality risks are subject tospecialised expert assessments. In 2005, the IRSN
examined 106 dossiers with, in some cases, countercalculations, or specific studies.The aim is to assessthat the justifications presented in the dossiers of
the nuclear operators and applicants are wellfounded, as regards transport packages of fissile
radioactive materials. It is also to check that theUse of feedback of incidents
Events regarding transport of radioactive materials
In 2005, the IRSN drew up a new database on the events which
occurred during the transport of radioactive materials in France.
This tool is used to monitor yearly changes in the number ofincidents according to their gravity, causes and the sector of
activity concerned, then to learn the technical lessons possibly topropose changes to international legislation. More than
700 events occurring since 1999 are stored in this database.

Incidents in laboratories, plants and installations being
dismantled
The IRSN uses the feedback from events and incidents as part ofits expert assessment of the safety of installations, especiallyduring modifications or safety reviews. To do so, a database,called SAPIDE/LUDD has been developed since 2004.
It contains all the unclassified technical data and the
documentary references associated with the events andincidents affecting the laboratories, plants and installations being
dismantled. Today it holds some 3,650 events and incidents,
some of which occurred abroad.
In 2005, the possibility to effectively use the database was
extended to all Institute’s specialists. It is updated by entering
the information contained in the incident reports sent by
operators. They are systematically analysed to identify both theelements requiring immediate actions, and relevant feedback
information for the Institute’s missions.

safety margins associated with the calculations
made, in relation to the qualification level of thecalculation tools used, are sufficient. Calculations
to specify the criticality risks within a geologicaldisposal of radioactive waste in very long-term
evolution scenarios were carried out by the Institute.
Furthermore, the IRSN analysed incidents related
to the criticality risk and provided support to the
DGSNR for surveillance inspections and crisis
exercises for which questions of criticality could
arise. Finally, the IRSN participated in the IAEA workas part of the changing international safety rules
for the transport of radioactive waste.

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TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIES

Expert assessments of risksof dispersal of radioactive
materials[FOCUS]

may occur during the transport of irradiated fuelpackages to the reprocessing facility in La Hague,
some of which could lead to the sinking of a package.
Such a situation could affect the performances ofthe package as regards heat dissipation andcontainment of the radioactive material. The IRSN
estimated the probability of such an accident andstudied the thermal behaviour of the package
according in particular to the depth to which it sinks.
Means of intervention such as installing a coolingsystem were thus determined as were the times
required to implement them in order to maintaincontainment.

[FOCUS][T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

Key figures of the Dossier 2005 Argile> 6 months of investigation, fed by research and work carried out
by the Institute over the last 20 years on the safety of radioactive
waste disposal;> 82 documents in the initial dossier (more than
12,000 pages), to which are added 57 additional documents (readand analysed) transmitted by Andra at the request of the IRSN;> 20 IRSN engineers mobilised for support studies or expert
assessments, with more than 10 specialities (earth sciences,materials, transfer of radionuclides in the geosphere, radiologicalprotection, fire, containment, etc.);> 5 organisations called upon for studies to support the expert
assessments conducted by the IRSN, including the GRS, theGerman counterpart of the IRSN;> 18 technical meetings with Andra, based on 280 questions
raised by the IRSN;> 16 summary reports on the work carried out by the IRSN aspart of this assessment (other summaries are in preparation);> 1 report available on the Institute’s website, presenting a 230page opinion of the IRSN on the whole dossier;> 5 pages of IRSN presentation presenting this opinion to theStanding advisory group of experts for installations for long-term
disposal of radioactive waste, and 10 hours of discussions.

Expert assessments of internal
emergency plans
In 2005, the IRSN analysed the operational natureof the PUIs of three Ionisos facilities, the Strasburg
university reactor (Bas-Rhin), the Laue-LangevinInstitute, the FBFC facility in Romans-sur-Isèreand the CIS Bio international facility in Saclay. In
addition, at the request of the Drôme, concernedwith the setting up of an annual fair near the FBFC
facility in Romans-sur-Isère, the Institute re-assessed
the consequences of the accidents presented in thisinstallation’s PUI after the recent modifications
that were made to it.

RADIOACTIVE WASTE
MANAGEMENT SAFETY
The IRSN worked on the safety of thevarious stages in the radioactive waste
management: processing, packaging,transport, storage and disposal. Different
categories of waste are involved: waste
of all levels of activity, mining residues
and polluted soils, etc.
In 2005, given the deadline fixed by the law of 1991
on research into the management of HLLL waste,
the Institute mainly examined the Dossier 2005
Argile, drawn up by the Andra and regarding thefeasibility of geological disposal in the clay layer
studied by means of the Bure (Meuse) undergroundlaboratory.
This assessment considerably mobilised the IRSN
teams in charge of this field from the summer of2005 (see Focus below).
The Institute’s conclusions were presented on 12
and 13 December 2005 to the Standing advisory ofcompetent experts. They indicate that disposal ofradioactive waste in the layer studied appears
technically feasible.The IRSN in particular revealed
that the clay deposit presents intrinsic properties
favourable to the containment of radionuclides andthat Andra defined disposal concepts taking accountof the main disturbances which could affect thewhole containment capacity of the disposal. In viewof the studies examined, this capacity should remain
sufficient as regards the basic safety rule no. III.2.f
to maintain satisfactory protection of man and114 ]I R S N 2005 ANNUAL REPORTThe IRSN nevertheless underlined that many
points need to be developed in order to draw up asafety dossier associated with a possible application
to create disposal: identification of any possible
fracturing of the terrain at the disposal zone, validation of the performance of the containment
barriers by in situ tests and structure “demonstrators”, etc.
The Institute also examined the Dossier 2005
Granite regarding the interest of French granite
formations as a medium for disposing of HLLL waste.
This completes the Dossier 2002 Granite examinedby the IRSN in 2004. The Institute confirms theconclusions it presented in its 2004 annual report,
i.e. that these deep formations do not, generically,present any geological properties which hinder the
installation of possible disposal.

> by taking part, invited by the IAEA, in an expert
assessment mission of a surface disposal project inSouth Korea;> by organising the international Tokyo conference on the safety of radioactive waste management. The IRSN presided over the programmes
committee for this conference organised by the
IAEA from 3 to 7 October 2005.

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIES

the environment. Respect for this rule, regarding
the safety objectives of a disposal installation in a
deep geological layer in particular supposes thatthe radiological impact at lower levels be limited
to the prescribed constraint (0.25 mSv/year forthe reference situation).

Impact studies on former
uranium mine sites
The IRSN continued its assessment of the environmental impact of former uranium mine sites. At
the request of the Prefect of the Cantal department,
an expert assessment was begun into the radiologicalsituation of the Saint-Pierre site. It aims to improvethe monitoring set up when the mining activity
ceased. Analysis of existing data during an initial
phase, enabled the additional investigations
required to study the radiological condition of thesite to be specified. This work will continue in 2006
when field study and measurement campaigns arelaunched, following a presentation to the SaintPierre Local Information Commission. (See Focus
opposite).

Disposal facilities
For surface disposal installations of low- andmedium-level waste, the IRSN examined specificAndra dossiers concerning the Aube disposal
centre and the Manche disposal centre (general
operating rules, package acceptance specifications,
incident on a structure wall, extension of structure
implantation zones within the scope of the BNI).
The IRSN also participated in reflections accompanying projects for radiferous and graphite waste
disposal, in the subsurface or an existing cavity,
developed by Andra.

Regulations on waste safety
The IRSN participates in work to draw up or revise
policies concerning waste safety. Thus in 2005, theInstitute continued on work concerning the requiredchanges to the basic safety rule III.2.f, which deals
with the safety of long-term disposal of radioactive
waste in deep geological formations.
In addition in 2005, the Institute took part in international work by the bodies in charge of radioactive waste management, in particular:

Dosimeter on the Cogema site to monitor
the former mine site of Saint-Pierre du Cantal.

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[FOCUS][T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

Assessment of the dossier regarding
the mine site at Les Bois Noirs

At the same time, the IRSN continued with the
MIMAUSA programme (Memory and Impact of
Uranium Mines: Summary and Archives), with thedevelopment of an IT database to enable thestructuring and archiving of current knowledge on
former French uranium mine sites.
In addition, at the request of the ministries of
Ecology and Sustainable Development, of Industry
and of Health, the Institute will provide technicalsupport to the pluralistic group of experts currently
being set up, whose mission will be to examine
the environmental report on all former mine sites
in the Haute-Vienne drawn up by Cogema , inaccordance with the decree of 13 January 2004.
This group should hold its first meeting in April
2006.

View of the settling and treatment basins for water fromthe mine site in Saint-Priest-La-Prugne (Loire) before release
into the environment (Besbre river).

In reply to a request from the prefect of the Loire department,
the IRSN handed over an expert assessment report in 2005 on
the file submitted by Cogema with a view to demolishing the
SIMO facility at the Les Bois Noirs mine site in Saint-Priest-laPrugne (Loire). Following the first dismantling phase at the startof the 1980’s, the buildings had been kept and the land sold tothe commune with a view to industrial conversion. This had
never happened, and the buildings had been gradually
deteriorating to the point where demolition was required. This
demolition, and an additional clean-up of the site are paid for by
Cogema. The dossier sent to the prefect aimed at depositing
demolition products and “mine tailings” from the site in the
open-cast mine. These “tailings”, identified during aradioecological study conducted from 2000 to 2003, had beenused as backfill, in particular under the sawmill platforms.
The IRSN expert assessment dealt with three main points:> the methods used to demolish the buildings and clean andrehabilitate the facility lands;> the methods for storage in the open-cast mine;> the efficiency of the waste water collection and management
network.
The Institute’s conclusions and recommendations were
presented to the Local Information and Monitoring Commission
for the site in 2005. They were used in the prefectoral decrees
authorising demolition and storage.

116 ]I R S N 2005 ANNUAL REPORT

Writing of a guide concerning
the disposal of naturally
reinforced radioactive waste
At the request of the ministry of the Environment,
the IRSN contributed to defining the methods ofaccepting waste with radioactivity which is naturally reinforced or concentrated in the disposal
centres. A technical guide was written and submitted for national consultation to accompany a draft
ministerial circular. Several disposal centre operators have already approached the Institute toapply the method recommended.

To successfully complete these assessments, the
IRSN bases its work on: the results of researchcarried out by the Institute or other recognised
bodies, the results of calculations to better appreciate phenomena, specific probabilistic safetyassessments (PSA), international practices andfeedback from incidents occurring in nuclear andnon-nuclear facilities, in France and abroad.

Safety review of
900 MWe reactors
In 2005, the Standing advisory group of experts fornuclear reactors discussed the results of the safety
review for 900 MWe reactors associated with thethird 10-yearly outage programmes, as regards therisks of fire and explosion. On this occasion, the
IRSN in particular analysed EDF’s method to assessand control the explosion risks linked to the use
and storage of flammable gases in nuclear power
plants.
The results of the IRSN’s fire PSA were also presented during the same meeting of the Standing
advisory group.While these results confirm that thematerial provisions and procedures implemented
by EDF as part of the fire action plan lead to asignificant improvement in safety, they also show
the interest of strengthening protection in someareas.
For its part, EDF will carry out a fire PSA for 1,300 MWe
reactors as part of the safety review associated with
their third 10-yearly outage programmes. In order
to use of its own assessment tool, the IRSN also
started a study into these reactors.

The IRSN examined the safety options adopted by
the operators of future nuclear installations (PSA,
Georges Besse II uranium enrichment facility)
concerning the risks of fire and explosion. Similarly,
the Institute examined the provisions maderegarding these risks in the dossier presented byAndra on the feasibility of waste disposal in theclay formation studies using the Bure undergroundlaboratory (Meuse).

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESThe expert assessment of safety dossiers
regarding the risks of fire and explosion
consists in assessing the validity of theprovisions adopted by the operators forprevention and limitation of the consequences.

Future installations

International collaboration
In the field of international collaboration, as wellas continuing technical exchanges with Ukraine andBelgium, the IRSN also established contacts, inparticular with technical support for the Romaniansafety authority, aiming at drawing up a rule todefine the provisions to be made to control the risksof fire in Romanian nuclear power plants.

RISKS ASSOCIATED
WITH EXTERNALHAZARDS
In 2005, the IRSN continued to examine
the protection of nuclear sites against
earthquakes and floods.

Seismic hazard
In 2005, the Institute examined the assessmentsof the risk of earthquake produced by the operatorsof several nuclear sites: Tricastin (Drôme), CEA’s
CESTA (Gironde), Cadarache (Bouches-du-Rhône).

Guide to assess the risks of explosion
An explosion in a nuclear installation may lead to a major
accident. The IRSN assesses the corresponding risks as part of its
safety expert assessments of these installations.

[FOCUS]PROTECTION OF
INSTALLATIONSAGAINST FIRE AND
EXPLOSION

In 2005, a focus group of special skills developed within the IRSN
in the field of explosion was set up. This group aims to capitaliseon knowledge and formalise expert assessment practices
concerning the risks of explosion in a guide.

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T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

These investigations are carried out as part ofapplications to create new installations (Georges
Besse II facility, Laser Mega Joule, Agate and Cedra)or to review the documents governing the operationof existing installations (Masurca).
The Institute also gave an opinion on the relevance of the earthquake detection system for the
Grenoble high flux reactor (Isère). In addition, the
IRSN analysed the hypotheses retained for the
EDF interregional fuel stores in Chinon (Indre-etLoire) and Bugey (Ain), and the earthquake risk
at the Brennilis site (Finistère), whose installations are currently being dismantled. Abroad,the Institute examined the hypotheses to be retained to size the sarcophage around the damaged
Chernobyl reactor.
Finally, review work on technical rules regarding
earthquake risk continued. After proposing anapproach to define the seismic movements to beretained for each site (basic safety rule 2001.01),
the Institute started a review of the rule regarding
aseismic construction provisions for civil engineering works (RFS V.2.g).

Flood risk
Following the flooding of the Blayais site (Gironde)at the end of 1999, EDF re-examined the protection
provisions for all its installations, and the methods
for characterising the risk of flooding, in particulartaking account of rainfall, tides, the level of aquifers,etc.).
In 2005, the IRSN started to investigate themethodological elements presented by EDF. A
hydrogeological model was developed for thispurpose, in collaboration with the Ecole nationalesupérieure des mines (engineering school) in Paris,
to assess percolation flowrates through the DonzèreMondragon canal embankment (Tricastin site).
At the request of the DGSNR, the Institute also led
a focus group comprising safety authorities, nuclear
operators and flood specialist, with the aim ofreviewing BSR I.2.e.

118 ]I R S N 2005 ANNUAL REPORTPOPULATIONEXPOSURE TO FALLOUTFROM NUCLEAR
WEAPONSIn 2005, the IRSN dealt with the final
part of the study ordered by the DPPR
(Division for prevention of pollutions andrisks) of the ministry of the Environment
in 2003 regarding exposure of theMetropolitan population to fallout fromatmospheric testing of nuclear weapons
in the 1960’s and 1970’s.
The Institute assessed in 2005 the doses
received by the population afterreconstituting the evolutions of theactivity of the main radionuclides present
in the air, deposits and transfer into thefood chain.
The reconstitutions made are based on over
45,000 results of measurements carried out by the
SCPRI and the CEA between 1961 and 1980 andconcern the fission products released by these
explosions, measured in the air, rainwater, the main
components in the food chain and the meals servedin school canteens.
These data were used to assess the French population’s exposure to the fallout, by inhaling theradionuclides present in the air, by irradiation andingestion of contaminated foodstuffs. As well as
the effective dose, doses to the thyroid and bonemarrow were also calculated.
The wealth of the data also revealed the regionalvariability in the doses received, with maximum
levels up to twice the average for high rainfall regions,such as the Massif Central, the Vosges, the Jura andthe Alps.
The most exposed generation were people bornin 1961 who were growing up when the fallout was
the strongest (from 1961 to 1963). For these people,
the effective dose is of the order of 1.5 mSv, with
300 μSv attributed to 1963 alone.
It should however be underlined, that the doses
calculated do not take account of carbon 14, whose
specific contribution is currently being assessed.
Similarly, this work does not deal with special eating
habits which may have led to an increase in thedoses received.

Health impact of medical-origin effluents

Monitoring of effluent releases
from nuclear installations
At the request of the DGSNR, the IRSN controls
liquid and gaseous radioactive effluent releases
from all installations in the nuclear fuel cycle. The
aim is to verify the release values reported by theoperators. These measurements are also used tofurther the knowledge of releases from installations and to improve environmental monitoringplans accordingly.
In 2005, this activity was made concrete by a lesssystematic monitoring but better targeted and morein-depth from the point of view of the radionuclides
measured.
A specificity in the decree of 5 March 1990 regarding
the authorisation of liquid radioactive effluent
releases by the Golfech (Tarn et Garonne) nuclear
power plant requires special controls on activity in
the Garonne immediately upstream of water intakes for supply to the town of Agen. To meet thisrequirement, the IRSN has set up a new automated

Reception of samples from BNI to monitor
their discharges.

Portable Telehydro probe immersed at the exit of a waste watercollector in a Toulouse hospital.

In 2005, at the request of the DGSNR, the IRSN drew up an
inventory of the practices and radionuclides used in nuclear
medicine, and assessed the dosimetric impact of effluentscontaining patients’ urine discharged into the environment.
A study was able to assess the internal and external exposure
which could be attributed to iodine 131 and technetium 99
metastable which may be found in the sewer networks andtreatment plants.
This study shows in particular that despite concentrations which
are occasionally high in these radionuclides, personal exposure
does not exceed one tenth of the effective admissible dose forthe public, due to the short half-lives of these radionuclides andexposure times.
As treatment plants were not designed to deal with radioactivity,
it may be released into the environment. Medium- and longterm environmental marking by these radionuclides remains
to be studied.

I R S N 2005 ANNUAL REPORT[ 119

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESTechnical support for environmental
monitoring includes several actions:radiological analyses, assistance withinspections and organisation of crosscomparison exercises of measurementsof radioactivity in the environment.

station to measure the radioactivity of the Garonne
water, due to the operating difficulties encounteredwith the previous station.The results are sent every
month to the administrative departments
concernedand to the local authorities (Drire, Ddass,town halls, CLI).

[FOCUS]ENVIRONMENTAL
MONITORING

[FOCUS][T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

Support for inspections

Increase in participationin cross-comparison exercises

The IRSN assisted inspectors of basic nuclear installations during certain site visits – Chooz (Ardennes) in
June, Nogent-sur-Seine (Aube) in October, Pierrelatte(Drôme) in October – and carried out individualised
sampling of releases at the request of the inspectors.

National network ofenvironmental radioactivity
measurements

Preparation of samples for interlaboratory test campaigns.

Laboratories which can feed the national network withmeasurements of environmental radioactivity must comply withcertain qualification criteria specified in the public health codeand in a decree of 27 June 2005.
In this regard, at the request of the DGSNR, the IRSN organises
exercises of cross-comparison of environmental radioactivity
measurements. These exercises deal with the analysis of low level
radionuclides, of natural or artificial origin, in various samples(water, soils, biological matrices, filters, etc.). In 2005, 123participants from 45 different laboratories participated in these
exercises, representing a 20% increase on 2004. Indeed, the samelaboratory can participate in several exercises during the sameyear.
In order to facilitate the traceability of these test results, the
IRSN developed special software in 2005. Its aim is to manage
the database of participating laboratories (enrolment,
communication and recording of results) and to carry out thevarious statistical processes on the measurement results.
In addition, the Institute’s means of preparation andmeasurement enabled cross-comparison to be proposed for the
first time in 2005, on measurements of aerosols deposited infilters. The use of the ICARE bank located in Saclay (Essonne)
enabled uniform deposits of strontium and caesium aerosols tobe created with properties representative of the deposits
commonly encountered by laboratories.
The Institute continued its approach with a view to obtain Cofrac
accreditation as an “organiser of interlaboratory comparisons”.

120 ]I R S N 2005 ANNUAL REPORTAn order issued on 17 October 2003 placed thetechnical management of the National network forenvironmental radioactivity measurements under
IRSN responsibility. This network will compile theresults of measurements collected over the years
by public establishments, government departments,
nuclear operators, local authorities and associations.
In particular, the IRSN is to provide the secretarial
services for the steering committee prescribed by
the order and take charge of the centralisation,
processing and archiving of analysis results.
It is also required to make data available to thegeneral public on a website. In 2005, the principal
strategic and technical orientations were defined
and the audits conducted by the Institute on thesteering committee members were used to design
the specifications of the future information system.

TECHNICAL SUPPORTIN THE FIELD OF RADONAt the request of the DGSNR in 2005, the
IRSN drew up a list of the various cartographic studies predicting zones affectedby radon conducted in around 40 departments on behalf of the Ddass or Drass.
These local studies were carried out by 10 or so
different bodies (BRGM, university laboratories,
private firms, decentralised administrations) andaccording to different methods.The work performedby the IRSN enabled it to offer general elements tobe retained to classify geographic zones according
to their potential to be radon sources.The accuracyof the mapping may, in the best cases, reachseveral hundreds of hectares.

Radon measurement in spas

Z11

1st floor

Z14

For example, final radiological testing after cleaning
in a residence contaminated by radium in the rue
du Paradis in Paris.This type of intervention consistsof characterising the quantity and quality of theradionuclides present and the extent of the contaminated zones, then making the premises safe bysuitably packing and storing of the contaminatedmaterials or sources with a view to their final disposal
by suitable means.
Other types of intervention were carried out by
the Institute in 2005: radiological protection assistance for interventions on contaminated sites, suchas in Bandol (Var) to clear land contaminated byradium, technical support during inspections
conducted by the public authorities (SATURNE
accelerator in Saclay) or work on sites contaminatedby radium (Gif-sur-Yvette).

Type of object used by the department of intervention
and assistance in radiological protection in its mission
to collect sources.

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESIn 2005, the public authorities, at nationalor local level, called on the IRSN 12 times
for various work, following the discovery
of sources of ionising radiation in inappropriate places.

[FOCUS]RADIOLOGICALPROTECTION RESPONSE
AND ASSISTANCE

Z13

Z12
Z10

Z17 Z16 Z15
Ground
floor

Z3

Z4

Z2

Z5
Z3

Z8

Z9

Z1

Z6

Determination of homogenous occupied zones (Z)from the Bagnères-de-Luchon establishment for radon.

Radon measurements must be carried out in spas to meetchanges in French legislation regarding the management of therisk associated with radon in premises open to the public. Given
the special nature of these establishments (existence of several
sources of radon, especially damp atmosphere, seasonal activity),
the provisions of the AFNOR standard NF M60-771 regarding
detection cannot be complied with.
A special method was drawn up in 2005 by the IRSN at therequest of the DGSNR. The changes made in relation to thestandard mainly concern the type of measurement devices to be
used and the determination of homogenous zones in buildings(zones with the same properties in terms of penetration anddistribution of the radon).
For treatment premises, the determination of these zones
requires the estimation of the radon dose by the therapeutic
agent (water, gas, steam, mud), the influence of the “ground”
source (basement, ground floor, etc.) and the ventilation
conditions, be they continuous, partial or inexistant.
This method was tested and validated in 2005 at the
Bagnères-de-Luchon (Haute-Garonne) spa before being
implemented nationwide.

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[FOCUS][T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

Reconstitution of a dose after aradiological protection incident

RADIOLOGICALPROTECTION OF
WORKERSThe IRSN technical support for the
Department for labour relations as
regards radiological protection ofworkers in particular concerns participating in drawing up regulatory texts
and knowledge of the exposure.

Counting of chromosomal aberrations inbiological dosimetry.

During 2005, the IRSN made a dose reconstitution following theaccidental exposure of a worker during the characterisation of a
new X-ray generator. The victim, who was not wearing his
individual dosimeter, showed redness on the right clavicle a few
hours after the exposure. Clinical, biological and physicalestimations of the dose were immediately carried out in parallel.
The clinical examination indicated exposure of the skin of several
grays. Biological dosimetry, using dicentric chromosomal
aberrations within the lymphocytes, led to an estimated dose of
100 mGy. The associated confidence interval [0-250] does notenable a zero dose to be excluded. Finally, the physical dosimetry
specified that, given the very low energy of the radiation, thedose was deposited very locally and superficially. Thus, although
the dose received on the skin is high, it is not inconsistent tomeasure a low dose by biological dosimetry.
All these elements were used by the occupational physician todecide whether or not to keep the worker in controlled zone.
This incident shows the advantage of collaboration within theInstitute between the teams working on the physical and biologicalcharacterisation of the dose.

In 2005, the IRSN gave its opinion on various draft
legislation concerning training of competentpersons in radiological protection, worker exposure
to radon, zoning of installations, radiologicalprotection tests and declaration of incidents
occurring in the installations (excluding BNI).
In addition, the Institute approved the dosimetricmonitoring techniques implemented by threeorganisations for external dosimetry and threeorganisations for internal dosimetry. These opinions are provided as part of the investigation forcertification of these organisations by the ministry
for Labour.
The results of exposure of workers in 2004 weredrawn up based on data sent by IRSN passive
dosimetry laboratories and by approved organisations. Roughly 255,000 workers are concerned.
The medical and veterinary sectors employ 56% of
these workers. The total collective dose received
amounts to 64 man.sievert.This total dose has beenfalling steadily for the last 10 years. In 2004, 51
people received a dose greater than the statutory
limit (20 mSv/year).The number of these excessive
values has remained relatively stable since 2000.

Scanner interpretation room at the Cochin hospital.

122 ]I R S N 2005 ANNUAL REPORTTECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIES

However, three sectors of activity repeatedly present
doses greater than 20 mSv: medical radiology, thenon-nuclear industry (mainly non-destructive
testing using gammagraphy) and the subcontratingcompanies for the main nuclear operators.
Depending on the specificity of the work stations
and the radionuclides handled, a certain number ofworkers are also subjected to additional dosimetries: “neutron” dosimetry and dosimetry of theextremities.
The global result that can be concluded is that thefall in collective doses observed since 1990 is continuing, while the number of workers in the same
period has risen overall.

RADIOLOGICALPROTECTION IN
THE MEDICAL FIELDRadiological protection of exposed
personnel for medical purposes is basedon two principles: justification of medical
acts and optimisation of exposure.
In 2005, as part of the action plan to monitor the
exposure of patients to ionising radiation of medical
origin (PASEPRI) drawn up by the DGSNR, IRSN
actions were carried out in three fields: completionof a report into medical exposure of the French
population, jointly written with the InVS, thecollection of dosimetric information to draw up
diagnostic reference levels and dosimetric studies
regarding premature babies and dental radiology.

Medical exposureof the French population
to ionising radiation
In 2005, collaboration between InVS and the IRSN
enabled a report to be drawn up on the medical
exposure of the French population to ionisingradiation. Knowledge of the distribution of radiological examinations and their associated doses isnecessary to estimate the contribution of medical
exposure to the doses received by the population.
It also enables changes to be understood in orderto specify the impact of new techniques, newprotocols, or even new legislatory provisions.
Under these conditions, the IRSN and InVS have

Report on medical exposure of
the French population.

decided to coordinate their efforts to implement asustainable information system on medical exposure of the French population to ionising radiation.
A report of the data available (CNAMTS and Annual
health establishment statistics) was drawn up.
This report shows that, according to the hypotheses
taken, 61 to 74 million acts (including dental
radiology) were carried out in France in 2002.
Conventional x-rays represent 90% of examinations, scans 7% to 8% of examinations and interventional radiology and nuclear medicine together
about 2%.
The trends noted in this study compared to previous
studies (1982, 1988, 1994) reveal:> a marked reduction in some traditional x-ray
examinations without preparation such as x-raysof the thorax and skull, examinations which havefallen by about half in the last 15 years;> a significant fall in examinations with opacification which are 10 times less numerous thanin 1982;> stability in x-rays of the abdomen and thevertebral column;> a significant development in scanning which
has tripled in 15 years.
The average individual effective dose is between
0.66 and 0.84 mSv per year. Traditional x-ray
examinations contribute to 35% of the total dose
given to the population, those of scans to about
40% and nuclear medicine and interventional
radiology to 20 to 25%.

I R S N 2005 ANNUAL REPORT[ 123

[FOCUS][T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E STechnical support with regard to nuclear and radiological risk

Study of the doses received by prematurebabiesUpdating of diagnostic
reference levels
Since March 2004, legislation obliges the managersof radiology and nuclear medicine installations
to provide the IRSN every year with dosimetric
information regarding the most common examinations.These provisions concern almost 4,000 x-ray
installations, 700 scanners and 200 nuclear medicine
departments.
A professional information phase concerning thisnew legal obligation was initiated by the IRSN. At
the end of 2005, data from 29 radiology departments (including scanning) and from 78 nuclear
medicine departments was collected. These data
show the variable practices in place according to
the establishments: for example, in nuclear medicine, the activity administered for a given type of
examination may vary by a factor of almost four.

Traditional x-ray.

In 2005, the IRSN conducted a study into the doses received bypremature babies, one of the most sensitive populations toradiation. For clinical monitoring, these newborns are subject tomore and more x-rays. The IRSN study looked at 184
examinations carried out on the reanimation ward at the
Antoine-Béclère hospital on 63 premature babies weighing from
500 grams to more than 2,500 grams. The dose to the skin, which
depends mainly on weight, varies from 20 μGy to 37 μGy per xray and the average number of x-rays per premature baby canreach 20 during its stay. The study showed that a 30% saving in
the dose can be envisaged by using digital detectors. This saving
will be validated at a later date when this technique has been
implemented and adapted to the characteristics of x-ray
examinations in premature babies.

Awareness and information campaigns for the
personnel concerned will be continued in order
to increase the data collected.

Dosimetric studies indental radiology
In order to contribute to guidelines for prescriptions
and dental radiology examination procedures, a firstphase had to be initiated to draw up diagnostic
reference levels in this field.
To do so, the IRSN conducted dosimetric assessments
for 16 of the most common procedures and for 11
radiological devices, including the scanner, in 2005.
The doses measured on the skin range from lessthan 1 mGy for a traditional x-ray to 25 mGy for
tomography.
With the advance in technology, digital detectors
are replacing photographic film. The fall in dose
often associated with digital detectors however,has not been observed for all procedures. This canonly be realised after a concrete approach to optimise procedures.

124 ]I R S N 2005 ANNUAL REPORTThe role of these meetings was to:> enable the Agency managers to better know themissions and activities of the IRSN;> know better the activities the Agency wants todevelop, and the possible collaborations between
the two organisations;> reinforce the IRSN’s contribution to IAEA workin drawing up standards and international consensus.
New actions were undertaken to follow on fromthese meetings: preparation of the IRSN interventions during international conferences and its
contribution to organising an IAEA conference inFrance on safety expert assessment in April 2007.
Every year, participation in IAEA focus groups andtraining activities represents more than one
person/year and security inspection missions
correspond to two people. In addition, six IRSN
experts were seconded to the IAEA on 31 December
2005. The Institute also strengthened its presence
within NEA bodies, with the election of Mr Philippe
Jamet to the position of vice-president of the
CSNI committee for research into nuclear safety.
In 2005, the Institute continued its contribution toseveral focus groups in this organisation.

EUROSAFE 2005
The EUROSAFE project aims to contribute to converging technical
nuclear safety practices in a widened European context. Thisapproach is backed up by three supports: the EUROSAFE Forum, theEUROSAFE Tribune and the EUROSAFE website. Until now organisedby the IRSN and the GRS alternately in France and Germany, the2005 Forum was organised with the AVN in Brussels for the firsttime, and was devoted to improvements in safety. One and a halfdays of scientific and technical presentations brought together
almost 420 experts from safety organisations, research institutes,
safety authorities, industries, public authorities and NGOs from theEuropean Union, Switzerland and Eastern European countries. All
information on the forum, the texts of the presentations and issuesof the EUROSAFE Tribune are available from www.eurosafeforum.org.
The next days, jointly organised by AVN, the IRSN and the GRS, willtake place in Paris on 13 and 14 November 2006.

I R S N 2005 ANNUAL REPORT[FOCUS]

Co-operation between the IRSN and Chinese radiologicalprotection health organisations continued in 2005 at a steadypace, with monitoring by means of meetings of the boards. The
Institute welcomed seven Chinese trainees for stays of six
months to one year. These training courses dealt withradiological protection for man and questions of nuclear safety(probabilistic safety assessments, safety examinations, use of thethermohydraulic accident code CATHARE and the ASTEC code forsevere accidents). The training courses concerned engineers fromthe Chinese safety authority NNSA, its technical support NSC andthe China National Nuclear Corporation (CNNC) with whom the
IRSN signed co-operation agreements.
Similarly, two visits (one to France and the other to China) took
place in 2005, as part of the safety review of the experimental
Chinese fast neutron reactor CEFR.
In addition, at the end of May 2005, the IRSN hosted a largedelegation from the CNNC, which enabled new areas of
co-operation in the field of human radiological protection to be
identified. Finally, IRSN played a significant role in theorganisation of two seminars in China, one dealing with thesafety of the EPR reactor project (see Focus Seminar in China on
the EPR reactor project*), the other devoted to research anddevelopment into severe accidents.

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESAt the end of May 2005, an IRSN delegation, led by the general manager, met
the heads of nuclear safety and security
programmes and of IAEA technical cooperation in Vienna.

Strengthening of co-operation with China

FOCUS

p.104

[FOCUS]

MULTILATERALSCIENTIFIC
CO-OPERATION:
STRENGTHENING
THE IRSN’SCONTRIBUTION TO
IAEA AND OECD/NEA
WORK

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T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E S
Operational support in the event of a crisis or radiological emergency

Operational support in
the event of a crisis orradiological emergency
The IRSN provides support to the public authorities on regulatory, methodologicaland operational aspects of the national organisation to be implemented in order torelevant to a crisis or radiological emergency.The Institute ensures that this assessment
is relevant by permanently evolving its assessment tools and means of intervention andby forging close relations with the various actors and parties concerned.

2005 and 23 December 2005, in particular specify
the operational missions of the IRSN to the local
public authorities who may be in charge of managing radiological emergencies.
The interministerial directive of 30 November 2005
regarding the application of the international
convention on assistance in the event of a nuclear
accident also specified the means for implementing
this assistance, to which the Institute may contribute,in particular in terms of aid in diagnostics andtreatment of contaminated or irradiated victims.

CRISIS MANAGEMENT

Treatments of individuals potentially irradiated in the Institute’s LMR
laboratory truck.

Regulatory aspects of emergency
situation management
As part of its support to the authorities in drawing
up legislation, in 2005 the IRSN contributed todeveloping an interministerial directive on the
conducting and processing of measurements ofenvironmental radioactivity. The Institute also
participated in developing a circular defining theprinciples of intervention for an event which could
lead to a radiological emergency excluding situations covered by a contingency or intervention plan.
These two texts, dated respectively 29 November

126 ]I R S N 2005 ANNUAL REPORTThe IRSN provides operational support
to the public authorities in a radiologicalemergency. Depending on the circumstances, the Institute may engage all orpart of its expert assessments or intervention means.
To do so, the Institute avails of:> a Technical Crisis Centre equipped with a wide
range of assessment tools;> mobile intervention means enabling testing ofpeople and measurement of environmental
radioactivity;> methods to assess individual exposure (biologicaldosimetry, dosimetric reconstitutions, etc.)
Continuous improvement of these means andtheir engagement during exercises, or real situations, regularly enable their effectiveness to beappreciated.

Real actions of the IRSN’s CTC for
real situations

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESIn terms of organisation, 2005 saw a strengtheningof the IRSN mobile cell sent to the location of aradiological emergency, with in particular, thecreation of the position of head of this cell andimprovement of its links with the Institute’s Technical
Crisis Centre (CTC). In addition, all the job descriptions for crisis team members at the CTC were drawn
up or revised.
In order to ensure continuous development andimprovement of the expert assessment methods
used at the CTC, an initial reflection was conducted
in 2005 on changing the diagnostic/prognostic
method used to manage an accident which might
affect an EDF reactor in operation.At the same time,
adaptation of this method to the reactors onboard
new generation submarines (SNG) was examinedin concertation with French Navy staff.
Not only for methods, major evolutions were madeto some expert assessment aid tools, in particular
the SESAME system which enables releases in theevent of an accident affecting an EDF reactor to beassessed and the atmospheric dispersion codes andcalculation of the radiological consequences. The
development of a new tool for post-processing ofdata and cartographic representation was alsocommenced. The operational documentation(summary description sheets of installations, model
accident sheets, data on the instrumentation of
installation chimneys) regarding laboratories andfacilities, Navy installations and transports has
been completed.

[FOCUS]

Organisation, methods andmaterials

The Institute’s Crisis Centre was activated on 30 September 2005
following a water leak at the Nogent-sur-Seine power plant.

In 2005, two incidents concerning EDF plants led to theimplementation of the national crisis organisations and thus toreal actions by the Institute’s CTC.
The first took place on 30 September at the Nogent-sur-Seine
plant (Aube) after a water leak from the secondary circuit via thedrainage valves left abnormally open which led to the appearanceof faults in the protection system equipment on reactor no. 1 (see
Focus Incident in Nogent-sur-Seine*). The second occurred on
Thursday 27 October when the untimely closure of a valve caused
an increase in the pressure of the primary water circuit in reactor
no. 3 at the Blayais power plant (Gironde).
These two incidents confirmed the responsiveness of the IRSN
crisis teams. In both cases, the assessment mainly consisted of
diagnosing the condition of the installation and examining thesafety level resulting from operations to make the installation
safe. Using feedback from these incidents, reflection is being
conducted on the role of the IRSN in “infra-PUI” situations(situations which could trigger the internal emergency plan [PUI]).

The manager of the IRSN mobile cell in discussion
with his team members defining the appropriate
action plan.

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[FOCUS][T E C H N I C A L S U P P O R T A N D A S S I S TA N C E F O R P U B L I C A U T H O R I T I E S
Operational support in the event of a crisis or radiological emergency

Use of pectin to decorporate caesium 137
In April 2005, the French ambassador to Belarus called on the
IRSN with a view to making a pluralistic assessment of theeffectiveness of pectin and the opportunity for its use on land
contaminated following the Chernobyl accident. The IRSN
initially conducted a bibliographical analysis of the advanced
scientific and technical arguments to clearly identify thecontroversial points and any gaps in knowledge concerning theuse of pectin as a food additive to capture radionuclides(especially caesium 137) in order to help their elimination. The
summary of the 54 documents examined reveals that the work
undertaken to assess the effectiveness of pectin does not enablea definitive opinion to be given on whether it is helpful toadminister pectin in order to reduce the concentration of
caesium 137 in the human body. Following its analysis, the IRSN
specified that it would be useful to complete knowledge
regarding the advantages of the use of pectin. Only experimental
studies on animals supplemented by clinical studies would
provide the information essential for assessing the advantages ofpectin for children living on land contaminated by the Chernobyl
accident.

Acquisition
Reception andprocessing of data
3D/3P
Diagnosis of the conditionof the installation

Releases - types
Pre-calculated
source term

Systems
Diagnosis of thecondition of systems
Brèchemètre
Estimation of the sizeof the break

Brèchemètre
Evaluation of the numberof tubes ruptured

Schéhérasade
Evaluation of the time
before the core is exposed

SGTR (Steam generator
tube rupture)

Hydromel
Evaluation of
the hydrogen risk

Estimation of
the source term

PersanEstimation of
the source term

The SESAME system is comprised of a set of modules used to assessradioactive discharges in the event of an accident on a PWR.

128 ]I R S N 2005 ANNUAL REPORT

Evaluation of radioactive
releases in the event ofan accident
Version 3 of the SESAME system is currently the IT
tool used by the CTC to evaluate radioactive releases
in the event of an accident affecting an EDF nuclear
reactor.
In 2005, EDF modified the data transfer system fromreactors to the crisis centres. These modifications
led the IRSN to develop new software during thesame year to collect the parameters from a
supposedly damaged reactor. This software, called
ACQUISITION 4, is the first element in the development of version 4 of the SESAME system carriedout in full by the Institute as part of continuous
improvement of its crisis tools. Thus, SESAME 4
will take account of changes in hardare and softwareand advances in R&D in the field of severe accidents,
to develop the physical models used in the various
modules.
The scope of application of the SESAME system will
also be extended to new accident situations(shutdown situations).
These changes to the SESAME system will takeaccount of feedback from the use of the previous
version and of the needs expressed by the experts
who may be called to the CTC.
Special attention will be paid to maintaining compatibility between the modules of the old tool andthose of the new, in order to enable simultaneoususe during the gradual implementation of the nine
programmes which will make up the SESAME 4
system by the end of 2007.

Evaluation of environmental
consequences in the event ofan accident
Feedback from the use of operational tools to evaluate the environmental consequences of an accident situation and the appearance of new needs,
in particular as regards centralising and interpreting measurements from the environment, will
require a new operational platform to be developed at the CTC.
This will include:> a new tool to calculate the consequences,whose the main specifications were defined in
2005, used to make all the atmospheric dispersion
calculations and the radiological consequences inthe event of an accident and will be based ondispersion models on the local and national scales;

TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIES

Gammagraphy source accident in Chile[FOCUS]> a tool to centralise the results of environmental
measurements, a new version of which was developed in 2005;> a new post-processing tool for all results calculated or measured.
This operational platform will be installed at the
CTC from 2006.

Exercises and feedback
15 national exercises were organised in 2005 by
the public authorities in order to test the national
crisis organisation and systematically led to theactivation of the Institute’s CTC and dispatchingof its mobile cell to the prefecture’s operationalcommand post (PCO). These exercises on various
installations such as power reactors, transport,
military installations, etc., with a wide range ofsituations, showed the need to progress in harmonising working methods (expert assessment method,
permanent links, specific preformatted messages,etc.) between the IRSN and the operators, in orderto enhance exchanges during a crisis situation.
These exercises also confirmed the need to continue
with efforts undertaken to improve coordinationand interpretation of environmental radioactivity
measurements, in order to fully fulfill the missions
entrusted to the IRSN by the interministerial
directive of 29 Novermber 2005 regarding taking
and processing of environmental radioactivity
measurements.

Gammagraphy source accidentally handled by a Chilean worker.

On 15 December 2005, three workers were accidentally
irradiated by a source of iridium 192 (3 TBq) used in industrial
gammagraphy in a cellulose factory under construction in Chile.
The Chilean government called on international aid, and a teamfrom the IAEA including a physician from the IRSN conducted
an expert assessment and assistance mission with the medical
teams in charge of the victims. As one of the victims had been
severely irradiated, the experts recommended transfer to aninternational centre specialised in the treatment of accidental
irradiation victims. The worker was thus hospitalised on
29 December in the burns unit of the Percy army teaching
hospital in Clamart (Hauts-de-Seine).
The IRSN technical support was decisive in guiding the surgicalprocedure to remove an extended zone of tissue which hadreceived doses in excess of 20 Gy. The IRSN was able to provide
quick and accurate dose mapping on the surface and indepth of
the irradiated zone. This mapping is based on the distribution ofdoses assessed using digital modelling and on the measurementof the dose at a point of the body, i.e. the exposed iliac crest. For
the first time, it combines digital modelling with electronicparamagnetic resonance (EPR) measurements conducted on abone biopsy. This association enabled a new treatment strategy
to be drawn up.

IRSN Technical Crisis Centre: audioconference with
EDF during an exercise.

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Operational support in the event of a crisis or radiological emergency

Post-accident crisis exercise

Finally, the principle of regular technical meetings
between the IRSN and the DGSNR, and between
the Institute and the DSND was reviewed in 2005,
in order to examine bilaterally and in detail thelessons to be learnt from the crisis exercises andthe areas for improvement in terms of advice to the
local authorities.

SUPPORT IN
MANAGING POSTACCIDENT SITUATIONS

Testing of decontamination techniques on buildings by SDIS teams in
the Cher department.

National exercise in Belleville-sur-Loire
The national crisis exercise scenario on 22 March 2005 which
involved the EDF site at Belleville-sur-Loire (Cher) enabledcertain specific issues arising in the first hours of a post-accident
phase to be dealt with: implementation of sales restriction
orders, lifting of population sheltering, deployment of means tocharacterise radioactivity in the environment, etc.
Following this exercise, a focus group piloted by the IRSN andcomprised of representatives from decentralised government
departments (DDE, SDIS, Ddass), representatives from local
associations and town halls, discussed the rehabilitation
operations to be undertaken on buildings contaminated during
the first days. This reflection led the fire and safety departmentsof the Cher and the IRSN to organise in November 2005 a
simulation of the implementation of cleaning counter-measures ofa building in order to specify the order of magnitude of someparameters such as the quantities of water required for cleaning,
the times to carry out actions of the material and human means
required for this purpose. This exercise and the actions which
followed it confirmed the advantage:> for the local authorities of availing of the Institute’s support at
the prefecture’s fixed command post, in particular to supplying thetechnical explanations required to understand the situation andappreciate the challenges associated with the various actions to beundertaken from the very start of the post-accident
phase;> for the IRSN, of availing of operational data and involving thevarious stakeholders concerned in defining rehabilitation actions
and the way of implementing them.

130 ]I R S N 2005 ANNUAL REPORTThe IRSN’s operational organisation todeal with post-accident situations wasdeveloped in 2005. New IT tools weredeveloped and, as part of consultation
with local actors, the expert assessment
approach was improved, in order to better
anticipate the actions to be taken in the
post-accident phase immediately fromthe emergency phase.

Changes to DATARAD datacollection tool
In 2005, the Institute developed version 2 of
DATARAD, a tool to collect environmental radioactivity measurements during an accident situation.
This tool is used to centralise and interpret, at anational level, all the results of measurements andsample analyses made in the environment during
the crisis, within the framework defined in 2005 by
the public authorities.
Changes to the tool concerned:> improvement of the integration of DATARAD into
the operational chain of CTC IT tools;> repatriation to the CTC of the values measured
by the IRSN monitoring networks and operators,
centralised at the IRSN site in Le Vésinet (Yvelines);> ergonomy of the user interface given feedback
from the use of version 1 of DATARAD;> implementation of recent IT technology.

Rehabilitation strategies
Rehabilitation of a contaminated environment
following a nuclear accident aims to reduce thelevels of radioactivity in the environment and its
impact in terms of the doses to populations. Numerous actions can be undertaken to rehabilitatecontaminated land. However, their application

In April 2005, the public authorities implemented
a steering committee in charge of drawing up
doctrine regarding the management of the postaccident phase of a nuclear accident.
In an initial phase, six interministerial focus groups
were created to lead reflection on the following
aspects:> evaluation of the radiological and dosimetricconsequences;> health monitoring of victims and populations;> life in contaminated rural territories, agriculture,
water;> waste management, contaminated products
and soils;> compensation;> lifting of emergency population protection
measures and rehabilitation of buildings.
The IRSN led the group responsible for evaluating
the radiological and dosimetric consequences andwill be participating in other focus groups.
In addition, the IRSN participated in the indoor
exercise INEX 3 organised by the OECD/NEA on 9
December 2005. This dealt with the consequences
and the measures to be taken following a radioactive
release: decontamination, rehabilitation, waste
management, impact on trade, compensation of acontaminated agricultural sector (cereals), etc.This
exercise brought together local and national actors.
The IRSN participated in preparing and leading the
scenario and, as an actor, in the different focus
groups set up.
Although voluntarily limited to the agricultural
sector, the lessons learnt from this exercise are manyand should contribute to feeding the reflections of
the post-accident steering committee.
This exercise, conducted by several countries, will
be debriefed at the start of 2006.

During 2005, the IRSN developed a replacement andmodernisation plan for its mobile intervention means inradiological emergency situations. This plan has the following
goals:> greater efficiency, by abandoning versatime means in favour ofmeans dedicated to measuring or analysing environmental
samples and radiological testing of individuals;> greater flexibility and rapidity of deployment by replacing
heavy or semi-heavy-duty means with light vehicles;> total communication autonomy, even when standard
telephone networks are saturated.
Four emergency intervention vehicles were acquired in 2005.
During the coming years, they will gradually be associated withthree laboratory vehicles, six vehicles for radiological testing ofindividuals and a vehicle to coordinate all the means deployed by
the Institute in the field.

Operational support
in case of crisis
The IRSN provides the prefect with the various
elements of its mobile cell, according to the natureof the crisis situation:> a “measurement coordination” team, in chargeof drawing up measurement and sampling plans,collecting and controlling all the results ofmeasurements and analyses;> a “measurement means” team, in charge ofconducting measurements and samples in theenvironment and radiological monitoring of people.
> a “package inspection” team, in charge ofevaluating the condition of the damaged packagesin the event of a transport accident.
In 2005, the first two elements of the Institute’s
mobile cell were mobilised for each exercise. During
the “transport” exercise in the Val-d’Oise on
22 September, the “package inspection” team wasalso mobilised.

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TECHNICAL SUPPORT AND ASSISTANCEFOR PUBLIC AUTHORITIESManagement ofa post-accident phase

IRSN mobile intervention means[FOCUS]requires the use of often heavy human and technicalmeans and must take account of the times required
to carry them out, the exposure of workers and thewaste produced.
In this regard in 2005, the IRSN undertook to develop
a tool to compare rahabilitation actions (ICAR
project) in post-accident phase, taking account of
the many aspects of such a situation.

Key figures 2005
Key figures 2004

1,610,000 personal dosimeters supplied and used
1,714,000

856 analyses of drinking water carried out
1,019

145 analyses of foodstuffs carried out
150

127 radiological protection operations
150

42 third-party surveys
43

132 ]

I R S N 2005 ANNUAL REPORTCONTRACTUALSERVICES IN
EXPERTISE,RESEARCH AND
MEASUREMENTS
The IRSN carries out expert assessment and measurementservices
on behalf on institutions and industrialists who request them.
The Institute provides its skills and know-how, while at thesame time ensuring that these services remain compatible withits mission to provide technical support and assistance to the
public authorities. Some of these services are related to statutory

CONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENTS

requirements. Selling services is also a way of optimising theuse of technical tools developed for research programmes.
The services provided, excluding co-financing of research,correspond to about 5% of the Institute’s current budget.

134

Services related to statutory requirements

138

Services not related to statutory
requirements

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Services related to statutory requirements

Services related tostatutory requirements
RADIOLOGICALTESTING OF WATERINTENDED FOR
HUMAN
CONSUMPTION
Within the framework of legislation toprotect consumers, the IRSN provides
radiological analysis services of water
intended for human consumption.
The IRSN analysed 856 water samples in 2005.
The radiological quality of water intended forhuman consumption is assessed according to a
protocol, defined in the order of 12 May 2004, whichsets out the inspection methods. According to thevalues obtained for certain parameters (activity atotal, b total, tritium), additional analyses may
be required, as was the case in 13% of the waterinspected in 2005.

150,000 workers
monitored by external
dosimetry(150,000 in 2004)

However, less than 1% of the water led to an effective dose, due to the incorporation of radionuclides
present in the water during one year of consumption,
greater than the threshold value of 0.1 mSv fixed
by a Euratom directive, based on WHO recommendations.

RADON DETECTION

20,234radiotoxicological

Within the framework of risk management related
to radon in buildings, the IRSN provides detection
services and conducts further investigations as
defined in the regulations. In 2005, radon measurements were conducted in several establishments
open to the public (schools, town halls, creches,
holiday centres, retirement homes, hospitals, etc.).

analyses(21,089 in 2004)

208

anthropogammametricanalyses(125 in 2004)

8 dose assessments
by biological dosimetry(15 in 2004)

134 ]In 2005, the IRSN published a descriptive fileof services it is able to provide concerning radon.

Laboratory in which radiological waterinspection is carried out (Le Vésinet).

I R S N 2005 ANNUAL REPORTThe IRSN’s department concerned received ISO
9001 certification from Afaq for studies and expert
assessments conducted in radon control. In 2005,
the revenues from these services increased by 120%.

[FOCUS]RADIOLOGICALPROTECTION OF
WORKERS

Changes in external
exposure monitoring

Within the framework of the decree
no. 2003-296 of 31 March 2003, regarding
the protection of workers against ionisingradiation, the IRSN conducts measurements on the exposure of workers. It also
carries out expert assessments such asworkstation studies, and consultancy, forexample to support occupational physicians and people involved in radiologicalprotection.

Monitoring of external exposureof exposed workers

Monitoring of internal
contamination of exposed
workers
Assessing the exposure of workers at risk of internal contamination is conducted by determining
the incorporated activity in the body. Two types ofanalysis are used: measurement of incorporated
activity via whole-body radiometry and measurement of excretion activity via radiotoxicologicalanalyses of urine and stools. In the course of 2005,
the IRSN conducted 208 whole-body radiometry
examinations. Radiotoxicological monitoring was
conducted for 3,600 workers. For this purpose, ofthe various biological samples processed, 20,234
analyses were carried out. 64 different radionuclides were thus measured.

Passive dosimeter.

In 2005, three major projects regarding external exposure
monitoring were started by the IRSN.
The main aim is to replace the photographic dosimeter with athermoluminescent dosimeter (TLD) or a radiophotoluminescent(RPL) glass dosimeter.
This action is partly motivated by the uncertain future of
production of the silver film used in current dosimeters.
To do so, a call for tender was launched in November 2005,
the aim being to start implementation of the new techniquetowards the middle of 2007.
At the same time, a unique laboratory management IT system
more geared towards various customers (DOSIP) is in progress.
Finally, it is planned to obtain laboratory certification according
to the ISO 17 025 standard in 2006 and preparations for thiscertification were initiated in 2005.

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CONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENTS

The IRSN avails of one of the main laboratories inFrance to determine the external exposure of workers exposed to ionising radiation.
In 2005, roughly 150,000 workers belonging to
17,000 establishments wore dosimeters suppliedand developed by the Institute. This laboratory
processed 1,500,000 photographic dosimeters,
60,000 thermoluminescent dosimeters for exposure to gamma and beta radiation, and 50, 000 trace
detection dosimeters (PN3) for exposure to neutrons.

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Services related to statutory requirements

CONFORMITY
OF MATERIALSAND EQUIPMENT[FOCUS]

Within the IRSN, two technical centres
can conduct actions regarding theconformity of materials and equipmentwith regard to technical standards or
specifications. In their fields of expertise,
they take part in drawing up statutory
and normative texts for France and forother countries.

Cross-comparison of operational
dosimeters

Active dosimeters.

The IAEA organised an international cross-comparison exercise ofindividual operational dosimeters, targeted on measuring
the dose equivalent in a β and γ radiation field. During 2005,
the IRSN, the Mol research centre (SCK-CEN, Belgium) andthe CEA also defined and produced the various irradiation
conditions used for this cross-comparison in their installations.
During the cross-comparison, the performance of the operational
dosimeters were assessed in relation to the requirements of the
CEI 61526 standard for typical beams and for realistic radiation
fields simulating workstations. In total, 13 different models of
operational dosimeters from nine suppliers were tested.
The IRSN thus irradiated these dosimeters in its facilities
producing reference photons. The IAEA report presenting
the results of the cross-comparison will be published in
the course of 2006.

136 ]I R S N 2005 ANNUAL REPORTThe expertise of the IRSN’s Technical Centre forRadiological Protection Instrumentation Approval(CTHIR) involve measurements of individual
dosimetry and atmospheric dosimetry, measurements of air contamination and detection ofcriticality accidents. Since the end of 2002, the conformity of materials associated with these measurements is examined within the framework of theISO 9001 quality system.
In December 2005, the AFAQ granted renewal ofcertification for a period of three years. The CTHIR
uses the IRMA irradiator, an installation in which
irradiations designed to assess the resistance ofmaterials to gamma radiation are carried out. The
campaigns conducted in 2005 lasted 34 weeks intotal.

STATUTORYINSPECTIONS IN
RADIOLOGICALPROTECTION
On behalf of third parties or users of sealed or
non-sealed sources, operators of equipment or
installations using ionising radiation sources, the
IRSN conducts inspections relating to the statutory
requirements to which the latter are subject.These
services deal with the protection of individuals
against the dangers of ionising radiation, as part ofthe public health code or the labour code.
Numbering 15 in 2005, these inspections consistedof checking that sealed sources were not contaminating, conducting a radiological inspection for
the absence of contamination of certain premises

Statutory inspection in radiological protection at
the CRECEP (94).

for the purposes of radiological declassification or
ensuring satisfactory radiological safety of equipment operation.
The IRSN also carries out in situ inspections of theefficiency of very-high efficiency (VHE) filters andiodine traps in the ventilation circuits of basic nuclear
installations: 16 such inspections were carried out
in 2005.

NON NUCLEARSERVICES
The IRSN puts the skills it has acquiredin the nuclear field to use in services
provided to industrialists outside thisdomain.

For more than 30 years, the IRSN has provided
expertise in the field of odors, thus enablingindustrialists to take the appropriate corrective
measures if necessary.
With the improvement in the quality of living, thepopulation is less and less tolerant of olfactory
pollution, the second reason behind complaints inFrance. The answer to this evolution is based on
statutory and normative elements. Legislation,centered originally on the issuing environment
and more specifically on the channeled sources, did
not meet the concerns of residents. Despite compliance with provisions regarding the emission ofpolluting substances, these residents continued toexpressed a disturbance. Based on this situation,
the new regulatory texts require that all sources
are taken into consideration and fix limit values in
the receiving environment. Within this context,
the IRSN was consulted in 2005 by the ministry for
the Environment concerning the future orderregarding composting sites, in the same way as forthe drawing up of the order of 12 February 2003
regarding rendering plants, currently in application.
In 2005, the IRSN conducted 15 expert assessments
in various industrial installations. In addition, theInstitute continued to pilot the Afnor X43F Commission, research work in collaboration with Ineris andteaching activities in initial training (DUT, engineering school [Esigec]). It also started a study programme into olfactory disturbance.

Non-nuclear third-party surveys
The IRSN is recognised as a third-party expert by
the ministry for the Environment, to carry out criticalanalyses of studies of the dangers of industrial
installations classified for the protection of theenvironment. In order to carry out these analyses,
the Institute relies in particular on its skills acquiredin the field of nuclear safety.
Among the 40 or so critical analyses carried out by
the IRSN in 2005, can be mentioned those regarding
the Total refinery at Donges (Loire-Atlantique),
Arkema chemical plants in Saint-Auban (Alpesde-Haute-Provence), Pierre-Bénite (Rhône) andCarling (Moselle), and Dislaub alcohol distilling andsolvent processing plants in Buchères (Aube).

CONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENTS

Odor expertise

The team from the BAIN (Bureau of Analysis of
non-nuclear installation safety).

The IRSN also provides technical support to theministry for the Environment. It actively participatesin the focus groups set up by the ministry regarding prevention plans for technological risks,
toxicological reference values or sectorial aspects(chlorine, ammonia, flammable liquids, finechemicals, etc.).
Finally, in 2005 the Institute completed a probabilistic study regarding the risk of gas explosion in aliquid petroleum gas storage facility. The results
obtained were presented to the ministry and thewhole gas profession.

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Services not related to statutory requirements

Services not related tostatutory requirements
STUDY OF THE
RADIOACTIVITY OF
EFFLUENTS FROM THE
TOURS TREATMENT
PLANT[FOCUS]

Beyond the regulatory aspects, the IRSN is regularly
called on by urban waste water treatment network
operators to assess the radioactive marking relating
to acts of nuclear medicine and the corresponding
health impact in water treatment plants. In 2005,
the town of Tours ordered such a study. To do so,
continuous gamma measurements on waste water
were carried out, along with integrated gamma dose
flow measurements, in a treatment station, in six
specific premises and a control zone.The significant
values recorded in the waste water at the entrance

Sale of low-activity
standard sources

to the plant were used to quantify transit times,
the effect of dilution of the urban network and theflows of radionuclides. These values complied withthe recommendations of the DGS/DHOS circular
no. 2001/323 of 9 July 2001 regarding the management of effluent and treatment waste contaminated by radionuclides. The dosimetric impact
calculated majoritairely is very low, mainly due tothe low half life of metastable technitium 99, themain radionuclide discharged.

SAFETY OF PLANTS,
TRANSPORT ANDDISMANTLING
Criticality risk studies related to the use of fissile
materials in nuclear installations or during transport,

To meet the demand for the supply of low-activity
standard radioactive sources, the IRSN obtained
authorisation from the DGSNR in June 2005 “to hold for
distribution, use, sale, import and export, sealed and nonsealed radionuclide sources”.
1,000 to 2,000 sources, concerning more than 50 different
radionuclides, are prepared every year for the internal
needs of the Institute, in various forms:> sources in liquid or gel form, occasional deposit or
deposit on a filter, a cup or a stainless steel disk,
electroplated sources;> natural samples recharged with radioactivity;> standard solutions;> tracer solutions for marking of samples anddetermination of chemical separation yields for samples
prior to measurement.

The preparation of standard sources requires rigour andprecision. Here a grid-type crushing system is used toperfectly homogenise the sample to be prepared.

138 ]I R S N 2005 ANNUAL REPORT

Thus, the environmental radioactivity measurementlaboratories can obtain the standard sources from theInstitute, specific to low-activity measurements.

[FOCUS]requires the use of qualified calculation software.
In collaboration with industrialists, the IRSN isdeveloping the CRISTAL criticality package toenable such studies to be carried out.
It is making this tool available to a number of users
for whom installation support is also offered.

Support services for the users of
the CRISTAL package

STUDIES REGARDINGNIGERIAN AREVAMINING SITESIn 2005, the IRSN, at the request of thecompany Areva, carried out two studies
relating to the uranium mines operated
in north Niger by the companies Cominakand Somaïr.

Modelling using the CRISTAL package.

The CRISTAL package is used to carry out all types of calculations
required in criticality risk studies. In order to ensure a high level ofquality of the criticality studies conducted using this package,significant technical support and training is provided to users
when it is distributed, coordinated by the IRSN.
The IRSN support services include:> supply and validation of the installation at the customer of thecodes and tools developed by the IRSN;> assistance in the use of these codes and tools in the form of a
hotline;> corrective and evolutive maintenance, based on a computerised
call-out management tool, directly accessible to users via theInternet;> publication of information regarding qualification of the“standard method” of calculation (APOLLO 2-MORET 4);> management of a website reserved for users, enabling them toaccess all technical documentation, put in requests forintervention and remain informed of the follow-up to theirrequests, and to download the various versions of the codes andtools developed by the IRSN;> training sessions conducted at the IRSN or at the National
institute of nuclear sciences and techniques, in collaboration withthe developers.
In 2005, the IRSN installed version 1.0 of the package in 15 facilities
belonging to the CEA, Areva and EDF. The Institute also replied to
262 calls and processed 129 requests for intervention for the two
versions supplied of the CRISTAL package.

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CONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENT

Partly based on a mission on site, these two studies
consisted of assessing the environmental radioactivity monitoring networks around the sites andevaluating the dosimetric impact of the mines on
the population. The impact of the recovery anddomestic use of contaminated scrap iron from themines was also examined. The results, publishedon the IRSN website, showed that the monitoring
networks set up by Areva around the two minesites generally comply with the requirements
applicable to the storage of uranium waste inFrance.
Nevertheless, improvements were deemed necessary to specify or reduce the exposure of somecategories of people. The recommendations madeled Areva to call on the Institute once again to takethe samples and analyse the groundwater supplying the water distribution network, so as to beable to assess more accurately the impact due tothe consumption of drinking water.

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Services not related to statutory requirements

RADIOECOLOGYSERVICES
The IRSN provides measurement andstudy services in the radioecological field
for industrialists and public authorities.

Radioecological follow-up
of nuclear power plants
Since 1991, an agreement between the IRSN and
EDF concerns the determination of levels ofradioactivity around nuclear power plants. This is
EDF’s willingness to go further than strictly statutory obligations, and for this purpose to measure
the very low concentrations of artificial radionuclides in the land, rivers or seas surrounding its
installations. This monitoring also enables questions to be answered from the public authorities orthe company as regards protection of the environment and the population.
Currently, the agreement comprises three sections:annual radioecological monitoring around eachnuclear power plant, ten-yearly reports and a
research part into the behaviour of specificradionuclides such as tritium and carbon 14.
Today, the data acquired enables the Institute to
draw up a report of the environmental consequences

Radioecological follow-up at the Tricastin power
plant (Drôme) by sample taking.

over 20 years of the operation of nuclear power
plants. The radionuclides present in measurable
quantities (caesium 137, plutonium, etc.) in the soil,
wild plants and agricultural production, comealmost exclusively from fallout from atmospherictesting of nuclear weapons and from the Chernobyl
accident. Only a very low but significant environmental marking by carbon 14 from plant discharges
was revealed.

Survey of eating habits around
Pierrelatte
From the summer of 2004 to the spring of 2005,
the IRSN piloted a survey ordered by Cogema into
the eating and consumption habits of the populations living around the nuclear site in Pierrelatte(Drôme). This survey aims at better taking accountof local practices to assess the doses linked todischarges from site installations. The survey was
conducted on 80 households. In particular, the results
show that a population exists, which is still significant
in these semi-rural zones, who produces a major
proportion of the food it consumes.

Studies around the
Cogema site in La Hague
Validation of the DISPRO calculation code requires a large number ofsamples collected in the field to be measured, to compare the results to
those obtained by modelling.

140 ]I R S N 2005 ANNUAL REPORTThe services contract of several years’ standing
between the IRSN and Cogema has been extended
in 2005 to cover two topics concerning the irradiatedfuel processing plant in La Hague (Manche). A firststudy was conducted to validate the DISPRO
calculation code used to predict the dispersal ofradionuclide releases in the Manche area of France
from the plant. To improve the knowledge of thesefactory discharges, a second study was conductedconcerning the granulometry of aerosols from theUP3 facility and on the assessment of deposit
rates of aerosols released into the environment by
the facility.

Transfers of tritium andcarbon 14 into the water andthe atmosphere
In 2005, the CEA asked the Institute, as part of a
sub-contracting contract between the CEA and
EDF, to conduct experimental studies to assess thetransfer flows from water to the atmosphere oftritium and carbon 14 downstream of nuclear power
plants along the Loire.

and Combarelles [Dordogne]), the IRSN proposeda protocol systematically applicable to this type ofcave.

Radon and thoron measurementsin the premises of
the French Navy
In 2005, for the ministry of Defense, the IRSN
conducted measurements to characterise, from aradiological point of view, the inner atmosphere insome underground premises. Quantification of radon
and thoron daughters by integrated measurements
enabled the exposure of the personnel working inthese areas to be estimated.

Replies to tenders

SERVICES CONCERNING
RADON
Radon measurements inprehistoric caves
Following the discovery of high concentrations ofradon in the Chauvet-Pont-d’Arc cave (Ardèche),theministry for Culture asked the IRSN to conduct
measurements of the radon activity concentrationin the caves under its management, to asses the
exposure of the people working in these caves(guides, researchers, etc.).
Due to the extremely humid atmosphere in thesecaves, a special method was defined to best
characterise the radon contents and to determine
the most suitable instrument.
Following a protocol validation phase in five caves(Chauvet, Niaux [Ariège], Lascaux, Font-de-GaumeCONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENTS

About 10 projects proposed by the Institute on thesubject of the fate and effects of radioactive
contaminants in the environment, were chosen in2005. These projects, conducted in collaboration
with other research partners, reply to various calls
for tender from various public organisations (Andra,
Seine-Normandy water agency, Haute-Normandie
region, Provence-Alpes-Côte d’Azur region, ministryfor Research, ministry for the Environment, etc.).

Devices to measure radon concentration in a cave.

MODELLING OF
FACILITY VENTILATION
The premises of nuclear installations in which there
is a risk of dispersion of radioactive materials orcontaminants requires ventilation and monitoringof their atmosphere by air sampling.
The most homogenous renewal possible of the air
in these areas is sought in order to prevent any local
accumulation of radioactive aerosols or pollutants.
The IRSN develops and installs techniques to measure ventilation performance and transfers of theassociated radioactive materials or pollutants (see
Focus*).

FOCUS

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Services not related to statutory requirements

Ventilation performance transfer of pollutants

DOSIMETRICSERVICES
Biological dosimetry
In 2005, the IRSN’s biological dosimetric laboratory,
the only one in France recognised for this type ofexpert assessment, carried out eight estimations ofindividual doses in reply to requests from generalpractitioners or occupational physicians: two retrospective estimates and six for suspicious recent
irradiations in a professional setting. The estimateof the doses received using biological dosimetry isbased on the observation of chromosomal aberrations (dicentric) formed in the lymphocytes of thepeople concerned.

Gas and particulate tracing devices used by the IRSN.

In 2005, the IRSN carried out in situ measurements at the requestof nuclear operators or industrialists to check the ventilation
performance in the premises concerned, in particular, the absenceof low ventilated zones and the relevance of installing air
sampling monitoring devices (APA, explosion meters, etc.).

The retrospective estimates concerned people who
had consulted a physician for various pathologies.
In both cases, the number of chromosomal
aberrations observed was greater than that for the
non-exposed population taken for reference.
For recent suspicious irradiations, the doses estimated by biological dosimetry did not differ
significantly from zero, for various reasons: no real
exposure despite the positive reading on thedosimeter; the dose to the whole body is too low
to be measured by biological dosimetry; thesensitivity of the traditional biological dosimeter
is not suitable for cases of heterogeneous irradiation.

Two complementary approaches were used. The first consisted ofmeasuring the evolution over time in the air extracted from thearea of the concentration of a gas tracer (helium or sulfur
hexafluoride) continuously injected by blowing.
The second approach consisted of characterising the transfer
of a gas or particulate pollutant (simulated by an aerosol of
sodium fluorescein of given diameter) from a source point S
to any point M in the premises.
In addition, the IRSN teams use similar tracing techniques forother applications (flow measurement, barrier sealingmeasurements, verification of the representativity of a sample ina chimney, etc.) in the field of containment and filtering ofaerosols and pollutants.
Numbering of chromosomal aberrations.

142 ]I R S N 2005 ANNUAL REPORTRADIOLOGICALPROTECTION IN
THE MEDICAL FIELD

Assessment of the exposure of
the public and workers
The IRSN is regularly called on by companies or
institutions to assess the doses received in specificcontexts.
In 2005, studies were carried out to assess thedoses which may have been received:> by the public during a cure at a spa, due to theradioactivity present in the water;> by people living in a chalet built with wood from
Belarus;> by the employees of a waste water treatment
plant possibly containing radionuclides in particularfrom radiotherapies.

Dosimetric assessment following
an incident in Paluel
In July 2005, the IRSN conducted a dosimetricreconstitution at the request of the occupational
physician at the EDF power plant in Paluel (SeineMaritime).
An incident had occurred during the cleaning of asteam generator and several workers had handled
a radioactive metal part. The IRSN conductedcalculations of the dose to the skin by considering
several plausible scenarios (part in contact, glovesworn).
Although wearing gloves protects almost entirely
against beta radiation, the dose rate absorbed
remained high because the contribution of photons
was high.
The reconstitutions conducted by EDF showed thatthe exposure time had been short. Consequently,
the dose equivalents to the skin calculated are far
lower than the annual limit of 500 mSv.

The sectors most interested in these services areradiology, and more specifically interventional
radiology, and nuclear medicine. In general, special
attention is paid to all activities where the operator
is close to the patient and risks receiving high doses.
Work station studies have shown that, in the mostunfavourable situations (on the liver in interventional
radiology), the doses to the hands and feet are of
the order of 250 mSv/year, or half the dose limit.
In nuclear medicine, the most critical situations
occur during the handling of fluorine 18.

CONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENTS

Geometric modelling for the calculationof effective dose.

The IRSN is frequently called on by the
medical professionals to participate inways to better understand the exposureof health personnel in normal working
conditions. The Institute’s contribution
can go from simple provision of dosimeters to a complete on-site study.
Recent changes in legislation, and inparticular laws governing operational
dosimetry, are creating growing interestin studies on workstations and zoning.

Monitoring of workers exposed
to asbestos
As part of post-professional monitoring of workers
exposed to asbestos, the IRSN was responsible forassessing the doses received during scanner examinations associated with this monitoring. A report
was sent to the ministry for Labour in October 2005.
To conduct this assessment, 187 scans were considered with an effective average dose per examination of 3.9 mSv.This dose is less than the diagnostic
scan reference level for a standard lung examination, which is of the order of 8.5 mSv.

Radiological protection inradiotherapy facilities
In 2005, the IRSN with the support of the DGSNR
launched a study to answer the concerns ofradiotherapists or radiophysicians. Indeed, theInstitute is regularly consulted for its opinion on
projects to built or renovate radiotherapy rooms.
To these requests have recently been added theconcerns of the users of linear accelerators, con-

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C O N T R AC T UA L S E RV I C E S I N E X P E RT I S E , R E S E A R C H A N D M E A S U R E M E N T S
Services not related to statutory requirements

Bunker no. 1

Waiting room 03

Waitingroom 02
Hall 02AP 1 airlock

AP 2 airlockof cases) to 30-51 mGy (5.5% of cases). 51 cases
were studied in 2004 and the doses were similarly
distributed.
In relation to international recommendations andin particular those in publication 84 of the ICRP, allthese doses are lower than the value of 100 mGy,
the limit above which there may be prejudice tothe fetus, the extent and nature of which dependon the dose and the stage in the pregnancy.

PC AP 1

Waiting room 01
Scan airlock

Dosimetric study of radiotherapy
treatment rooms.

cerning protection against neutrons produced bydevices of over 10 MV. This work is used to understand the importance of the configuration of theroom and of the type of device used in radiotherapy.

Dosimetric assessment for new
radiology technologies
In 2005, at the request of the professionals
concerned, the IRSN participated in assessing new
3D imaging techniques used in dental radiology.
The doses were compared to those of similar
examinations conducted using a scanner. For the“Newtom” system, doses to the skin and the salivary
glands are respectively lower by a factor of two
and three than those of a traditional scanner
examination.
For the “Accuitomo” system, doses to the skin andsalivary glands are comparable to those received
from a traditional scanner examination whose
acquisition parameters have been optimised.

OPERATIONAL
RADIOLOGICALPROTECTION SERVICES
The IRSN’s services in operational radiologicalprotection cover all entities possessing or using
ionising radiation sources, mainly in France but also
in other countries. Services correspond to consultancy, study, expert assessment or radiologicalanalysis (sealed or non-sealed sources, polluted
sites, equipment or installations).
Interventions may also be carried out, in particularin a degraded situation (making sources safe,
detection and measurement of radon). In 2005,
the Institute provided 112 services, of all types, topublic and private establishments and private
individuals.

Exposure of pregnant women
In response to requests from radiologists or
gynecologists, the IRSN conducted in 2005
dosimetric assessments for 54 pregnant patients
who had undergone one or more radiologicalexaminations.The corresponding examinations are
divided between traditional radiology (26 cases),scanning (26 cases), nuclear medicine (one case)and radiotherapy (one case). The estimated doses
received by the fetus range from a few mGy (24%144 ]I R S N 2005 ANNUAL REPORT

Some interventions require the use of IRSN remotetools. Here the robot Romain.

CONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENTS[FOCUS]Radiological expert assessment of adevice for import into France

The equipment assessed by the IRSN in Australia
prior to its import into France.

The import company PLCD asked the IRSN to carry out aradiological expert assessment of a device to analyse the chemicalelements in cement, manufactured in Australia and using aneutron source of californium 252 of about
1 GBq. An IRSN team went to Adelaide to the premises of the
Scantech manufacturer to conduct radioactivity measurements. It
was able to assess the risk of exposure to ionising radiation andcheck the various safety and protection systems.
The expert assessment determined the specific precautions to betaken when installing equipment in cement factories andproposed improvements to protection, safety and signalling.

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Services not related to statutory requirements

Stabilisation of the sarcophagus of
the damaged reactor at the Chernobyl
power plant

COLLABORATION WITH
EASTERN EUROPEAN
COUNTRIES
Nuclear safety in Eastern European
countries is a major target for the IRSN’s
international action in partnership withother European technical safety organisations and those of the countries
concerned.

The IRSN is continuing its activity of assistance tothe Ukrainian safety authority.

[FOCUS]

Stabilisation work on the current structures of the sarcophagus
surrounding reactor no. 4 continued and were intensified at the
Chernobyl site during 2005. Started in 2004, this work should becompleted towards the end of 2006.
In parallel, the assistance to the Ukrainian safety authority
provided by the IRSN was continued by providing support to the
Ukrainian technical support organisation (SSTC) to assess a large
number of safety dossiers sent in by the operator. These safety
dossiers concern various domains in the project: stabilisation
work, foundations, design of the new sarcophagus, integrated andautomated monitoring system, a priori assessment of exposure toradiation during the work, legislation to limit this worker
exposure, strategies for managing radioactive waste, etc.

Riskaudit
Riskaudit is a European group of economic interest (EGEI) founded
in 1992 by the IPSN and the GRS to co-ordinate joint
international projects. Since its founding, Riskaudit has managed
more than 100 projects involving its two parent establishments
and other European and American technical safety organisations,in the context of programmes to provide assistance to Eastern
European countries in nuclear safety, financed by the European
Commission and the European Bank for Reconstruction andDevelopment (EBRD).
Riskaudit has its headquarters in Châtillon (Hauts-de-Seine)and two permanent offices in Moscow (Russia) and Kiev (Ukraine).

146 ]I R S N 2005 ANNUAL REPORTCollaboration with Eastern European countries
occurs via the development of regulatory contexts,
transfer of calculation codes and training in theiruse, but above all via the conducting of safety
reviews.
These reviews concern the definition of safety
objectives or requirements, the determination ofnecessary improvements, assessment of the corresponding improvement programmes, and analysisof the detailed solutions offered by the operators.
In this context, the IRSN participated in about 40
projects in 2005, in particular in safety review
regarding RBMK reactors in Lithuania and Russia,
and VVER reactors in Ukraine.
This co-operation is mainly carried out in the context
of contracts managed by Riskaudit, a subsidiary of
the IRSN and GRS, and financed by the European
Commission (PHARE and TACIS programmes) or by
the EBRD.
Co-operation in this part of the world is seeing
new developments with the setting up in Russia
and, in the near future, in Ukraine of the “Global
Partnership Against the Spread of Weapons andMaterials of Mass Destruction” adopted by G8 in
2002.

[FOCUS]

Expert assessments as part of
the G8 global partnershipFrance is a key player in the G8 global partnership, decided during
the Kananaskis summit in 2002, in particular in the field of thefight against the spread of weapons of mass destruction andagainst terrorism.

[FOCUS]

Emergency shutdown system for thereactor no.2 in the Ignalina power plant

CONTRACTUAL SERVICES IN
EXPERTISE, RESEARCH AND MEASUREMENTS

Within this framework, in 2005 the IRSN participated in preparing
several technical support projects for the radiological protection
or safety authorities concerned:> “RTG legislation”, service to improve Russian legislation
applicable to the dismantling of radioisotope thermoelectric
generators (RTG);> “Kalinine”, assessment of the improvements planned by theoperator for protection against fire of the Kalinine power plant(Lithuania);> “AÏDA MOX”, setting up of legislation adapted to theelimination of Russian military plutonium in the form of MOX
fuel.

In 2005, the IRSN participated in a PHARE project on a safety
review of the new emergency shutdown system on reactor no. 2of the Ignalina nuclear power plant (Lithuania), assisting the
Lithuanian safety authority.
In October 2005, the operator of this nuclear facility completed
installation of this new emergency shutdown system.
It includes two independent sub-systems, each able to shut down
the reactor if necessary.

I R S N 2005 ANNUAL REPORT[ 147

Key figures 2005
Key figures 2004

132 technical reports related to the safety of defence-related installations and activities
103

13 meetings of safety commissions and small groups of experts
94 crisis exercises related to the safety of defence-related installations
3

183 inspections related to the control of nuclear materials
198

1 crisis exercise related to the security of installations
1

148 ]

I R S N 2005 ANNUAL REPORTNUCLEAR
DEFENCE
EXPERTISE
In application of the decree relating to the IRSN dated 22 February
2002, the Assistant Director General in charge of implementing theInstitute’s defence-related missions, has a specific division, the
DEND, (Division for nuclear defence expertise). It carries out expert
assessments, inspections, studies and research regarding the safety
and radiological protection of defence-related activities and instal
lations, protection and control of nuclear and sensitive materials
and protection of nuclear installations and transport of radioactive
and fissile materials against malicious acts.

Assessment of the safety of military nuclear
systems, secret basic nuclear installations
and defence-related transport

154

Protection and control of nuclear andsensitive materials

159

Protection against malicious acts

NUCLEAR DEFENCE EXPERTISE

150

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NUCLEAR DEFENCE EXPERTISE
Assessment of the safety of military nuclear systems, secret basic nuclear installations
and defence-related transport

Assessment of the safetyof military nuclear
systems, secret basic
nuclear installations
and defence-relatedtransport
TECHNIC AL SUPPORTWITH REGARD TO
NUCLEAR AND
RADIOLOGICAL RISKO P E R AT I O N A L S U P P O RT
IN CASE OF CRISIS OR
RADIOLOGICALEMERGENCY

In 2005, the IRSN examined the safety of defence-related installations and transport,
based on dossiers provided by the operators, and sent the corresponding reports to thedelegate for safety and radiological protection of nuclear defence-related installations
and activities (DSND). The installations concerned may be in the stage of design,operation, definitive shutdown or dismantling.

Activities concerning defencerelated laboratories and plants
In 2005, the IRSN examined the safety of installations operated by the CEA (Division for military
applications) or by Cogema, using procedures
required to supply and manufacture weapons andmanufacture fuel for naval propulsion nuclear
reactors.
The IRSN examined the safety of radioactive
waste management in the CEA Valduc centre

General view of Marcoule - in the centre of
the UP1 plant.

150 ]I R S N 2005 ANNUAL REPORT(Côte-d’Or) based in particular on the study of“waste” and annual “waste plans” presented by theoperator. This assessment dealt with:> “waste zoning” of installations;> operator’s waste management strategy;> perspectives for the treatment of waste fromthe Valduc centre;> changes in the types and quantities of waste
produced by the site.
The operator’s dossier and the associated IRSN
assessment report were used for the meeting of the
Safety commission in charge of waste management(CSGD) on 26 May 2005.
The IRSN monitored the Cogema establishment inMarcoule (Gard) and the installations on this site.
Within this framework, the Institute transmitted
reports on the following:> waste storage and conditioning installations, inparticular these reports dealt with versatile interim
storage, implementation of storage pits and reviewof the safety of the alpha waste storage andconditioning site (IECDA).The corresponding reports
were presented to the CSGD and to the Commission
for the safety of laboratories and plants (CSLU);> general safety provisions for secret basic nuclear
installations (INBS);

containment and without significant increase ofdose rates outside the package.The IRSN continued
its development and, in 2005, investigated thecorresponding safety dossier. In-depth technicalexchanges took place between the CEA (DAM) andthe IRSN, in particular concerning the mechanicalbehaviour of the packaging during a high-speed
impact. The IRSN’s report on the safety of thispackage was presented to the Transport safetycommission (CST).

Transport of radioactive materials
by road tanker.

> operations planned as part of continuing shutdown and dismantling of the UP1 plant and thedecanning workshop;> evacuation, after reconditioning, of rod cartridges
to Cadarache (Bouches-du-Rhône);> storage of irradiated fuel rod cartridges;> implementation of a station to measure theactivity of technological waste;> five-year extension of storage of waste fromdefinitive shutdown operations of the UP1 plant.

The IRSN monitored the Cogema establishment in
Pierrelatte (Drôme) and the installations on thissite. In this respect, the Institute transmitted reportson the following:> start of operation of the P35 storage park for
uranium-bearing materials;> dismantling operations on annexes of gaseous
diffusion plants (GDP);For the Istres airbase, and as part of the creationof a new INBS, the IRSN provided a report on thecivil engineering safety demonstration regarding
earthquakes.

In addition, a review concerning radioactive material transport legislation, takes place every two years
with proposals and modifications from the Members
States and international organisations (ISO, EEC,etc.) submitted to the IAEA. 40 proposals were
accepted by the IAEA’s legislation review committee
and sent for comments to the Member States andinternational organisations. The IRSN provided areport on 11 proposals which it judged the mostimportant for safety and presented this report to
the Transport safety commission (CST) at the requestof the DSND.
Finally, the IRSN appraised dossiers concerninginternal transfers at the Pierrelatte, Cadarache,
Marcoule and Valduc sites, and packaging dossiersfor transport on public roads.

Activities related to naval
propulsion reactors
The expert assessments conducted by the IRSN in2005 concerned the design, operation anddismantling of installations and in particular, naval
propulsion reactors.
As regards design, 2005 was marked by continuing

A new type of transport package for radioactive
waste, enabling materials of high-level activity to
be transported by air, has been under development
since 1996 by the CEA (Division for military
applications - DAM). This type of packaging mustwithstand the accident conditions representativeof air transport, without significant loss of

NUCLEAR DEFENCE EXPERTISE

Activities regarding the transportof defence-related radioactive
materials

Barracuda project: SNA model.

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NUCLEAR DEFENCE EXPERTISE
Assessment of the safety of military nuclear systems, secret basic nuclear
installations and defence-related transport

Major overhaul: 2005 was also marked by the firstexhaustive examination of the work and inspections
conducted during a major overhaul of a nuclearpowered vessel. It consists of analysing the maintenance policy and the associated organisation
implemented during such a phase, but also thesignificant safety modifications made to theinstallations, taking account of requests made by
the DSND, the scope and the results of inspections
carried out on various containment “barriers”, andthe programme and methods to requalify the
nuclear boiler room and support installations.

Saphir, a French nuclear attack submarine (SNA).

investigations into the preliminary safety report on
new-generation Barracuda nuclear attack submarines(SNA), the object of two meetings of the Reactor
safety commission. Following the investigation
which should be completed in the first half of 2006,
the DSND will decide whether or not to authorise
the first of this type of boiler.

Annual operating review: The annual examinationof the operating review of onboard nuclear boilers
includes an analysis of the incidents which occurredand significant events in terms of training, organisation, waste management and monitoring ofreactor evolution. In 2005, this examination wascompleted by an operating reliability assessmentof the electricity production equipment on SNLEssuch as Le Triomphant.
As regards dismantling, 2005 was mainly marked
by reviews regarding the definitive shutdown of
the boiler on the SNLE L’Indomptable and its support
installations, and dismantling methods.
Finally, the IRSN also analysed two especially
important safety dossiers:

As regards operations monitoring, work in 2005 inparticular dealt with the safety review of SNA, thefirst “major overhaul” of Le Triomphant, a French
nuclear-powered ballistic missile submarine (SNLE),
and the 2004 operating report for onboard nuclear
boilers.
Safety review of Rubis-type SNAs: In April 2005,
the IRSN presented the Reactor safety commission
with its report on the general approach of the Rubistype SNA safety review, and on the method to study
accident scenarios.The technical investigation into
the safety review of SNAs, the first vessel of its typewhich was launched in 1983, should be extended
until 2008. A safety review mainly consists of
examining the conformity of the installations totheir initial safety standard and the main eventsoccurred during operation, completed by a repeatof the safety demonstration taking into accountthe requirements for a new installation.This exercise
may lead to modifications being defined, which
would aim to strengthen the overall safety of theinstallations.

152 ]I R S N 2005 ANNUAL REPORTLe Triomphant, a French nuclear-poweredballistic missile submarine (SNLE).

> the scenarios proposed by the operator to draw
up the special intervention plan regarding the portof Toulon (Var);> the conditions for carrying out statutory resistancetests on the main primary circuits of onboard nuclear
boilers.

Activities related toradioactive sources

Activities regarding internal
emergency plans (PUI)
In 2005, the IRSN sent technical reports concerning
PUI reviews for installations classified as secret.
They concerned:> the operational part of the PUI of the Cogema
facility in Marcoule;> the accident situations used to draw up the PUI
for the CEA Valduc facility.
The latter expert assessment consisted of examining all accident situations chosen, then, for eachsituation, assessing detection and alert means,intervention means, discharges and the radiologicalconsequences calculated by the operator.

In general, the IRSN is finding it difficult to copewith the increasing workload resulting from updating
the PUIs of defence-related nuclear installations,as those of civilian installations.

Crisis exercises
In 2005, the IRSN participated in four national crisis
exercises concerning secret basic nuclear installations(INBS):> the CELESTIN reactors in the Cogema Marcoulefacility;> the Saint-Dizier (Haute-Marne) airbase;> a workshop at the CEA Valduc centre;> an SNLE at the Île-Longue base.
These various scenarios were used to test IRSN
relations with the safety authority (DSND) and withthe operators of the installations concerned.

NUCLEAR DEFENCE EXPERTISE

In 2005, as part of the gradual implementation of
new legislation regarding radiological protection,
the IRSN listed about 20 installations whoseradioactive sources are henceforth inspected by the
DSND. This number should change seeing as
inspection of installations authorized by the CIREA(Interministerial commission on artificial radioelements) prior to 2002 will be transferred to the
DSND. For these installations, the IRSN monitors
movements of sources by issuing the required
packages and by recording them in the national
inventory.

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NUCLEAR DEFENCE EXPERTISE
Protection and control of nuclear and sensitive materials

Protection and control
of nuclear and sensitive
materials
TECHNIC AL SUPPORTWITH REGARD TO
NUCLEAR AND
RADIOLOGICAL RISK

DEFINING AND
I M P L E M E N T I N G N AT I O N A L
A N D I N T E R N AT I O N A L
RESEARCH PROGRAMMESThere are several aspects to the protection and control of nuclear and sensitive materials:
physical protection, monitoring of and accounting for nuclear materials, tracking oftransports and applying international controls on the non-proliferation of chemical
and nuclear weapons.

PHYSICAL PROTECTION
OF NUCLEAR
MATERIALS
Expert assessment andinspection activities
The IRSN places its technical expertise at the disposalof public authorities to assess the efficiency ofphysical protection measures adopted or proposedby nuclear operators and holders of nuclear materials. In this capacity, the IRSN analyses the reports
required by legislation and organises technicalmeetings with operators as part of its investigations.

Assessments carried out
during inspections
The IRSN assesses the performance of the physicalprotection systems installed by nuclear operators
to prevent any theft or hijacking of nuclear materials.
During 2005, several sites were thus assessed, withparticular emphasis on electrical fencing.This action
will continue in 2006.Tests and assessments concern
both verification of the technical recommendationsof the equipment manufacturers and the suitabilityof this equipment to the objective sought.
Assessments concern in particular the two functions“detect” and “delay”.

In addition, on behalf of the High Civil Defence
Servant (HFD) at the ministry for Finance, some
IRSN agents carry out inspections in installations
holding nuclear materials, in order to check in situ
that protection and control provisions against
loss, theft or hijacking of nuclear materials andprotection of installations against malicious acts,
are in place and operational.

56 support missions

carried out by international
inspectors to control nuclear
and sensitive materials(32 in 2004)

42 participationsin national and international
focus groups(54 in 2004)

154 ]For this purpose, the Institute carried out 51
inspections and, during 2005, processed about
130 requests to analyse dossiers provided byoperators and holders around 100 of which gave
rise to an analysis report.
During these inspections, the Institute carried out
in situ measurements of the physical characteristics
of protection systems.

I R S N 2005 ANNUAL REPORT

Physical protection barrier.

These three steps are assessed by field tests totake account of the specificities of the installations(distances between buildings, location of the security post, surface area of the zone to be monitored, etc.). For electrical fencing, several break-in
detection systems are used, some of which require
thresholds to be set. It is essential to ensure thatthe adjustments made by the operators properly
detect a break-in attempt.
Delay
This function, for electrical fencing, is based on theassociation of a physical barrier (the fence) with
an electrical pulse signal. The high voltage of theelectrical signal, tested during on-site tests, ensures
the repel function.

MONITORING OF AND
ACCOUNTING FOR
NUCLEAR MATERIALS
Expert assessment andinspection activities
At the request of the High Civil Defence Servant(HFD) at the ministry for Finance, the IRSN examines
the provisions made by operators and holders interms of monitoring of and accounting for nuclear
materials held in installations, in particular inorder to:> have precise, quantitative and qualitative information on all the nuclear materials that enter andleave the installations;> track the materials, i.e. always know where they
are located, what they are used for and the operations they undergo (movements, transformations,etc.);> check that the actual stock of materials heldcorresponds to the accounting figures that operators
are compelled to keep updated.

The IRSN suggests any corrective measures it deems
necessary, in particular regarding risks of theft,
loss or hijacking of nuclear materials. It then ensuresthat the requests from the HFD are properly met,
and reports to him.
In addition, on behalf of the HFD, some IRSN agents
carry out inspections in installations authorised tohold nuclear materials, to ensure that applicablestandards regarding detention of these materials
are met.
For the record, legislation distinguishes between
installations subject to a prior authorisation andinstallations subject to a prior declaration, dependingon the nature and quantity of materials held.
Within this context, during 2005, the IRSN conducted:> 128 analyses of dossiers sent in by operators
which required around 40 technical meetings andproduced 113 analyses of inventory reports on
nuclear materials;> 79 inspections at operators subject to authorisation. In addition, the Institute carried out about
20 technical inspections of installations subject toa prior declaration.

Changes in accounting
The new Euratom 302/2005 rule came into force
on 20 March 2005.The IRSN, who for the HFD fixes
the rules for declaring counts of nuclear materials,
centralises the accounting data transmitted byholders and sends the declarations to the European
Commission, is directly concerned by changes
introduced by the new rule.These changes concern
the formalism of the accounting reports anddocuments sent to the Commission, and extensionof European control to nuclear industry waste which
until now, was subject to national control, and the
supply of additional information.
The IRSN’s action included monitoring of thenegotiations prior to publication of the 302/2005
rule, presentation of the text to French operators
and an impact study on the nuclear material
management in France. Following this study, two
focus groups were organised by the Institute withrepresentatives of French nuclear operators. The
first dealt with changes necessary in the short-term.
Its work led to decisions to modify the national

I R S N 2005 ANNUAL REPORTNUCLEAR DEFENCE EXPERTISE

DetectDetection leads to a yes or no answer, and if
necessary, calls in the response forces. To analyse
this function in-depth, the IRSN successively
examines the physical components of detection(with their operating principles), transmission of
information to a security post and the taking
into account of the information by the agent on
duty.

[ 155

[

NUCLEAR DEFENCE EXPERTISE
Protection and control of nuclear and sensitive materials

accounting computer system to enable operators
to meet the new obligations, regarding accounting
for waste, from July 2006.
The second focus group dealt with content changes
to be implemented before March 2008. It aims toharmonize the modes of application of national andEuropean rules, and plans a significant change inoperators’ accounting systems. This change also
concerns the formalism of the national accounting
declarations, which include the additional information required by the 302/2005 rule. This focus
group’s decisions will enable specifications to be
drawn up, required to implement modifications to
the French accounting system and the national
accounting computer system planned for 20062007. The statutory standard codifying national
accounting declarations also needs to be updated
and this will be done in 2006.
Container of experimental irradiated fuelelements.

TRANSPORT OF
NUCLEAR MATERIALS
Within the IRSN, the Operational transport section(EOT), on behalf of the HFD from the ministry for
Finance, carries out operational missions in the fieldof protection and control of nuclear materials duringtransport. The road transport means used for thesetransports are subject to an approval procedurefrom the Minefi, in which the IRSN participates byassessing the design dossiers, monitoring production
and conducting periodic inspections.
Thus, the EOT managed and monitored 1,558
transports in 2005.
Among these should be mentioned a particularly
sensitive international transport the first phase ofwhich started in 2004: transport of nuclear materials
for manufacture in France of MOX fuel for a reactor
in the United States (EUROFAB project). The EOT
investigated dossiers describing physical protective
measures for nuclear materials during their transferfrom the Cadarache (Bouches-du-Rhône) plutonium
technology workshop (ATPu) to the MELOX facility,
then from there to the La Hague facility (Manche),and finally, during loading onto the ship for transport
to the United States.
The EOT also carried out real-time satellite monitoring of all these movements 24 hours a day, until
the ship left the French territorial waters (see
Focus opposite).

156 ]I R S N 2005 ANNUAL REPORTINTERNATIONALCONTROLS ON
NON-PROLIFERATION
Some international treaties to fight proliferationof nuclear and chemical weapons of mass
destruction, implement inspection systems. In France,
the IRSN provides assistance and technical support
to authorities in charge of monitoring these
inspections.
The inspection systems implemented by the Treatyof Non-Proliferation, the Treaty of Rome or theChemical Weapons Convention may be different
but they all involve international officers checking,in declared facilities, the information transmitted
by States to international inspection bodies (IAEA,
Euratom, OPCW).
Within this framework, the IRSN acts on behalf ofFrench authorities, collecting and preparing the
French declarations to inspection bodies.
The Institute is also in charge of ensuring the smoothrunning of international inspections in French nuclear
or chemical facilities. For this purpose, it prepares
the inspections, accompanies the inspection teamas the representative of the French authorities andensures the practical arrangements of the inspection
are followed.

Protection and control of nuclear
materials during the EUROFAB operation[FOCUS]

In its capacity as technical support, the IRSN analyses
the technical documentation to be submitted bythose being inspected, before it is sent to theinspection body. It assists French authorities byanalysing and keeping up with changes to national
or international regulations relating to the fightagainst proliferation. When necessary, it takes partin interministerial work and joins groups ofinternational experts set up by the Organisation for
the Prohibition of Chemical Weapons (OPCW) or
IAEA.

Chemistry

Nuclear
In 2005, the IRSN prepared and transmitted to theEuropean Commission:> more than 160,000 lines of operations declaration
on nuclear materials;> more than 500,000 lines of physical stock
declarations;> more than 650 reports prior to import or export.

Sea transport of nuclear materials.

Manufacture by Cogema of four MOX assemblies withplutonium for use in American power generating reactors (EUROFAB
operation) involved the IRSN on several levels.
During 2004 and 2005, the Institute was called upon to:> check authorisations and approvals of transport equipment,
approve transport plans and monitor land and sea transports,
including the highly publicized one in October 2004 between La
Hague and Cadarache, mentioned previously;> assess and inspect physical protection and detection systems
for nuclear materials;> in terms of monitoring of and accounting for nuclear
materials, analyse the adequacy of the preparatory campaign torestart the ATPu manufacturing line in Cadarache, the relevanceof reception checks of foreign plutonium and in-process controls,
and the validity of material analysis methods used;> study the behaviour of the FS47 package in the event of amalicious act.

NUCLEAR DEFENCE EXPERTISE

During the past year, the IRSN prepared and sent
to the ministry for Foreign affairs, for the OPCW:> the declaration of 2004 activities on the 144
French chemical facilities listed;> the declaration of the activities planned onthese sites in 2006.
The IRSN accompanies the eight inspections that
the OPCW ordered in chemical facilities in the French
civilian sector. None of these inspections required
any follow-up by the OPCW.
The Institute also participated in all the projects of
the OPCW expert groups aiming to propose practicalmethods of inspecting civilian installations aroundthe world.

Samples for the Euratom inspection.

I R S N 2005 ANNUAL REPORT

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NUCLEAR DEFENCE EXPERTISE
Protection and control of nuclear and sensitive materials> the monthly and six-monthly accounting reports
related to the international transfers of crudematerials and ores;> draft annual declaration of France on its researchand development and co-operation activities with
States not equipped with nuclear weapons (as partof application of the additional protocol to safeguard
agreements);> draft quarterly declarations of France to the IAEA,
regarding export of equipment or non-nuclear
materials (within the same context).

Preparation of the annual declaration as partof application of the additional French
protocol.

The Institute prepared and sent to the Euratom
technical committee:> provisional programme of activities for declared
French nuclear facilities;> the list of some 250 French holders of low
quantities of nuclear materials (and the conditionof their stocks). It also prepared and sent to the
French governor to the IAEA:> monthly and six-monthly accounts of stocks ofnuclear materials to be sent to the IAEA;

158 ]I R S N 2005 ANNUAL REPORTThe Institute accompanied 48 inspections by theEuropean Commission as part of inventory controls(35) and checks of dossiers known as “basic
technical characteristics” of installations (13).
The IRSN’s activities in 2005 were considerably
influenced by the review of the Euratom 302/2005
rule and by the European Commission‘s decision
to significantly modify its way of inspecting
installations.The review of the Euratom rule requiresthat inspections be extended to waste.The decisionaims to increase the qualitative dimension of theinspection, in particular by means of audits of theoperators’ management systems for nuclear
materials.
In this context, the IRSN participated in many
discussions with the services of the European
Commission and with French nuclear operators.

Protection against
malicious acts
The arrangements chosen internationally to fight against terrorist or malicious acts
strengthened the need, already identified nationally, to improve legislation regarding
the protection of nuclear installations, radioactive sources or transport of nuclear
materials against malicious acts.

Improving regulatory texts
In 2005, the IRSN participated in work undertaken
to strengthen and harmonize defence code legislation regarding the protection of nuclear materials
against the risks of theft or hijacking and thatregarding the protection of nuclear materials andinstallations against the risks of sabotage. Thus,
the IRSN participated in writing up the draft
decree to apply articles L.1333-1 and following of
the defence code.The Institute also helped to develop
a new set of reference threats designed to size andverify the suitability of physical protection systems
for nuclear installations. Finally, the IRSN was
involved in work conducted by the General secretariat
for national defence (SGDN) regarding changes inlegislation on materials governed by nuclear
dissuasion.

The work carried out in 2005 mainly concerned
sealed radioactive sources.

TECHNIC AL SUPPORTWITH REGARD TO NUCLEAR
AND RADIOLOGICAL RISK

DEFINING AND
I M P L E M E N T I N G N AT I O N A L
A N D I N T E R N AT I O N A L
RESEARCH PROGRAMMESStudying and developing
assessment tools
During 2005, the IRSN continued developing tools
to assess the consequences of malicious acts against
transport of nuclear materials. These are tools
used to assess not only the resistance of packaging
to a set of reference threats, but also radioactive
discharges which may result from damage caused
to containers. In the case of transport of irradiatedfuels, it is important to know precisely the behaviourof the material in the event a high-speed projectile
reached it. The aim is to specify the characteristicsof the fragments produced and the dispersible
fraction of these fragments.

In 2005, the IRSN launched a programme tostrengthen security of radioactive sources against
malicious acts. The general aim of this programmeis to better understand the risks of malicious useof radioactive sources and to draft proposals oftechnical or statutory measures to reduce theserisks.
In 2005, an initial study was conducted to identify
the types of sources and situations presenting thegreatest risks.The study comprised three main stages:> inventory of radioactive sources and classificationaccording to different types or families;> assessment of their sensitivity, i.e. the possible
consequences of a malicious act on man or theenvironment;> assessment of their vulnerability, i.e. the possibilityof success of a malicious act, for the families ofradioactive sources with the highest risks.

NUCLEAR DEFENCE EXPERTISE

Security of radioactive sources

Exchange between experts during a meeting
within the Division for nuclear defence
expertise.

I R S N 2005 ANNUAL REPORT

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NUCLEAR DEFENCE EXPERTISE
Protection against malicious acts

[FOCUS]In this context, an international focus group was
set up in 2000 including the Gesellschaft für Anlagen
und Reaktorsicherheit (GRS) for Germany, theDepartment of Energy (DOE), the National
Regulatory Commission (NRC) and Sandia National
Laboratories for the United States, the IRSN for
France and the Office for Civil Nuclear Safety(OCNS) for the United Kingdom.The group defined
an experimental work programme to study thedamage affecting a fuel rod in the event of aggression
from a “high-density energy” device, typically, aperforating device. One of the major objectives of
the tests is to determine the characteristics of theaerosols produced. Tests are planned in 2007 in
Albuquerque (New Mexico), on the site of Sandia
National Laboratories.
Prior to this, a significant experimental campaign
has started to develop the system and select theirradiated fuel substitute to be used for the experiments.At the same time as its participation in thisexperimental programme, the IRSN developed
several models in 2005 to calculate the damage.

The convention on physical protection
The review of the agreement on physical protection of nuclear
materials and installations significantly extends the scope of the
1979 international agreement and strengthens its effectiveness.
This new text owes a lot to France and, in particular,
the role played by the director of the Institute who chaired theinternational group of experts in charge of drawing up thetechnical and legal changes to the document.
In particular, the Institute was involved in defining the physicalprotection principles retained in the new agreement, which now
covers domestic use of nuclear materials and protection ofmaterials and installations against sabotage. These principles
highlight the primary responsibility of the States, who must
implement a physical protection system based on the existenceof a legal and statutory framework and on the designation of acompetent authority. The agreement also introduces a reference
to new misdemeanours, in order to ensure better legal protectionof materials and installations against the risks of theft andsabotage.
The final act of the review conference was signed on 8 July 2005
at the IAEA headquarters in Vienna. The amendment to theagreement will enter into force when two thirds of theparticipating States have ratified it.

160 ]I R S N 2005 ANNUAL REPORT

Crisis exercise involving the inventory of
nuclear materials.

Today it would appear possible to predict the damage
caused to the rods and the quantities of fragments
produced using digital simulation. Such models
are necessary to be able to extrapolate the results
obtained in a specific experimental configuration
to a set of cases representative of real transport.

Installation protection exercises
At the request of the HFD, the IRSN organised safety
exercises in the field of installation protection
with a view to testing decision-making chains andcoordination of those involved (operators, publicauthorities). It also pilots focus groups in charge ofpreparing the exercises and learning the lessons
from them.
Hence in 2005, a national security exercise, thesecond of its type, took place during the night of 9
to 10 September 2005 at the Cogema La Hague
facility (Manche). 150 people took part. The IRSN
participated in defining the scenario with thecollaboration of Cogema and the national police,
and drew up the exercise protocol. Led by the MINEFI(HFD) representative, the exercise was conducted
and observed by agents from the Institute.The IRSN
has been asked to participate in assessing thisexercise.

The training was tested in the Czech Republic in
2005. The method was then proposed to the IAEA.
It will be used as the basis of a publication in the
Agency’s “Tecdoc” documents. In 2005, the IRSN

The nuclear safety culture

also participated in several IAEA focus groups todraw up “Tecdocs” dealing with subjects such as
definition of reference threats, identification of vitalzones in nuclear installations or transport security.
As regards bilateral relations with the United States,
Institute agents were part of the French delegation
invited by the US DOE and the US NRC to attend
security exercises called “force on force” in an
American nuclear power plant.
As regards multilateral relations, the IRSN, involvedin the ENSRA, met with its counterparts several
times during 2005 for informal exchanges on topicalsubjects regarding nuclear safety.

Within the spirit of the final act of the agreement on thephysical protection of nuclear materials and installations,signed on 8 July 2005, the IRSN has worked on drawing up
two doctrine documents stating the basic principles of a
nuclear safety culture.
The first text is a document which may be published by
the IAEA to meet the demands of the member States. The
second, available on the IRSN website under the title
Culture de sécurité dans le domaine nucléaire is adapted to
the French context. This second document specifies thenotion of the nuclear safety culture and clarifies the roles
and responsibilities of each of the various stakeholders.
The goal is to increase awareness, in all actors concerns, ofthe possible consequences of a lack of attention in termsof safety of nuclear materials and installations.

NUCLEAR DEFENCE EXPERTISE

In 2005, the IRSN participated, as trainer or speaker,
in international courses organised by the IAEA,
regarding reference threats (in Serbia) and theprinciples of physical protection of nuclear materials
and installations (in Iran and India). Moreover, in
co-operation with the United States Departmentof Energy (US DOE), the IRSN developed an assessment method and training course on internal threats.

[FOCUS]International activities

I R S N 2005 ANNUAL REPORT[ 161

GlossaryA
ACQUISITION 4
Version 4 of the software used to collect theparameters from a supposedly EDF damaged
reactor. ACQUISITION 4 is the first element in
the SESAME system, IT tool used by the Technicalcrisis centre (CTC) to evaluate radioactive
releases in the event of an accident affecting an
EDF nuclear reactor

AECL

ANCLI
Association Nationale des Commissions Localesd'Information - French association of local
information commissions

ANDRA
Agence Nationale pour la gestion des Déchets
RAdioactifs - National agency for radioactive
waste management

Atomic Energy of Canada Limited - Canadian
research organisation

ANL

AES 92ANTARES

3rd-generation reactor developed by
Atomstroyexport

Very-high temperature reactor project,graphitemoderated and helium-cooled

AFA 3GLr AA

AP-1000

Advanced Fuel Assembly (2nd generationassembly) - Name given to a certain type of fuelassembly

3rd-generation reactor developed
byWestinghouse (USA)

AFAQ

Arrest or insufficiency in the development of
a tissue or organ

French Quality Assurance Association

AFNOR

Argone National Laboratory (USA)Aplasia

APOLLO 2

Association Française de NORmalisation - French
standardisation association

Neutron calculation code used to calculate
the conditions governing the nuclear reaction
in a fissile medium

AFSSET

AREVA

Agence Française de Sécurité Sanitaire del'Environnement et du Travail - French agency forenvironmental and occupational health safety

Industrial group including the companies Areva
T and D, Cogema, Framatome, FBFC, Cogema
logistics, Framatome ANP,Technicatome and FCI

ALCADE

ASTEC

Name of a fuel management method used in
French power plants

Accident Source Term Evaluation Code -Scientificsoftware system used to simulate the train of
events in a core meltdown accident in a water
reactor, from the initiating event to the releaseof radioactive products outside the containment.
It is developed jointly by the IRSN and GRS

Alpha (α symbol)
Radiation composed of helium nuclei, highly
ionising but not very penetrating. A sheet ofpaper is sufficient to stop alpha radiation

ALPHA-RISK
Quantification of cancer and non-cancer risks
associated with multiple chronic radiation andexposures: epidemiologicals studies, organ dose
calculation and risk assessment - European
project to assess chronic risks due to radiation on
man

162 ]

Externe - Accelerator for metrology andneutronics applications for external dosimetry(Cadarache)

ASTRAL
ASsistance Technique en Radioprotection
postAccidenteLle - Calculation code of the IRSN
that enables the transfer of radioactive elements
into the agricultural sector to be quantified

ATPu
Atelier de Technologie du Plutonium - Plutonium
technology workshop (Cogema)

AMANDE

AVN

Accélérateur pour la Métrologie etles Applications NEutroniques en Dosimétrie

Association Vinçotte Nucleaire - Vinçotte nuclear
association (Belgium)

I R S N 2005 ANNUAL REPORT

B

Burnup fraction

B4C

Thermal energy produced by the nuclear fissions
in a fuel mass unit. It is measured inmegawattsday per ton (MWj/t)Boron carbide used as a neutron absorberin some control rods

BWR
Boiling Water Reactor

BACCARACalibration and test bench of devices for themeasurement of radon and its decay products(Saclay)

BANCO
BANc d’étude du COlmatage des filtres - Filter
clogging test bench (Saclay)

BARC
Bhabha Atomic Research Centre (India)

BARRACUDA
Programme dedicated to the next generation of
French nuclear attack submarines

BECARRE
Essais de dégradation de Barres En CArbure deboRe et RElâchements associés - Tests on the
degradation of boron carbide control rods andassociated releases

Becquerel (Bq)
Official international unit for radioactivity
measurement. The becquerel is equal to one
disintegration per second

BEMUSEBest Estimate Methods Uncertainty andSensitivity Evaluation - OECD programme

Beta (β symbol)
Radiation composed of electrons of negative or
positive charge. A few-millimetre air screen ora simple sheet of aluminium can stop this typeof radiationC
CABRI
Test reactor for fuel safety used by the IRSN(CEA)CABRI-CIPCABRI International Program - Cabriinternational programme with a pressurised
water loop

Caesium (Cs, atomic number 55)
Noble metal for which biokinetics is very similar tothat of potassium released in large amounts
during nuclear reactor accidents

Callovo-Oxfordian
Layer of sedimentary rock from the Jurassic
period (160 million years) which is the layer
studied in the Bure laboratory

CAMARI
Certificat d’Aptitude à Manipuler des Appareils deRadiographie ou de radioscopie Industrielle Certificate attesting the ability to handle
radioscopy and industrial radiography equipment

CANDU
CANada Deuterium Uranium - Canadian designof heavy-water reactor

CaPhé-InE

Biokinetics

Caractérisation des Phénomènes de transfert enzone Insaturée d’Éléments traces potentiellement
toxiques - Characterisation of transfer
phenomena of potentially toxic trace elements
into a non-saturated area

Refers to all the accumulation and excretion
kinetics of an element in an organism

CAPITOUL

BfS
Bundesamt für Strahlenschutz - German federal
office for radiological protection

Boiling Liquid Expanding Vapour Explosion

Canopy and Aerosol Particles Interactions in
TOulouse Urban Layer - Measurement campaign
to study urban meteorology in Toulouse

BNI

CARINEA

Basic Nuclear Installation

Dispositif expérimental pour la CARactérisation
pour l’INcendie d’Échantillons Analytiques Experimental device used to characterise the fireof analytical samples

BLEVE

BRGM
Bureau de Recherches Géologiques et Minières Bureau of geological and mining research(France)

BSR
Basic Safety Rule

CATFISH
Caractérisation AnalyTique de la FIltration Sous
Humidité - Test bench (Saclay)

I R S N 2005 ANNUAL REPORT[ 163

CATHARE

CNNC

Advanced thermal-hydraulic calculation codeused to study the behaviour of pressurised water
reactors in accident situations.

China National Nuclear Corporation (China)

CCAP
Commission Centrale des Appareils à Pression Central committee for pressure vessels,
consultative organisation in place under the
Minister for Industry bringing together
representatives from various occupations andexperts of techniques used in the construction
and monitoring of pressure vessels. Any matter as
regards the implementation of laws andregulations concerning pressure vessels, may be
forwarded to the CCAP

CDI

Centre Nucléaire de Production d’Électricité Nuclear power generation site

CNRS
Centre National de la Recherche Scientifique French national organisation for scientificresearch

COFRAC
COmité FRançais d’Accréditation - Frenchaccreditation committee

COGEMA

CEA

COmpagnie GEnérale des MAtières nucléaires French general company for nuclear materials,
member of the Areva group and recently
renamed Areva NC

Commissariat à l’Énergie Atomique - French
Atomic Energy Commission

Containment building

Contrat à Durée Indéterminée - Open-ended
contract

CEFR
China Experimental Fast Reactor (China)

CERN

Leaktight concrete reactor building housing
the reactor pressure vessel, primary system,
steam generators and main auxiliaries ensuring
the safety of a pressurised water reactor

Centre Européen pour la Recherche Nucléaire European organisation for nuclear research(Switzerland)

Corium

CFX-5

COXST

Three-dimensional fluid mechanics calculation
software program

CHIP
Experimental programme on “Iodine chemistry in
the primary system” of a pressurised water
reactor during a core meltdown accident

CHSCT
Comité d’Hygiène de Sécurité et des Conditions deTravail - Health, safety and working conditionscommittee

CIREA

Molten nuclear reactor core (fuel and structural
materials)
COmité dédié à l’eXcellence Scientifique etTechnique - Committee dedicated to scientificand technical excellence (IRSN)

CPDP
Commission Particulière du Débat Public - Special
public debate commission

CPHR
Centro de Protección e Higiene de las Radiaciones Scientific and technical unit of the Nuclear
Energy Agency (Cuba)

Commission Interministérielle des RadioÉléments
Artificiels - Interministerial commission for
artificial radioelements

CRIS

CIVA

CRISTAL

Software plateform for modelling ultrasonic andeddy current examinsation

Centre de Ressources en Information Scientifique Scientific information resources centre

Commission Locale d’Information - Local
information commission

French criticality package developed as part ofa joint project between the IRSN, CEA and
Cogema. It aims at assessing the criticality riskin all nuclear fuel cycle installations and fissile
material transport packages.

CMS

Criticality (risks)

CLI

164 ]

CNPE

Cote Majorée de Sécurité - Maximum design
flood level

Risk associated with uncontrolled fission
phenomena in fissile materials

CNAM-TS

Criticality accident

Caisse Nationale d’Assurance Maladie, Travailleurs
Salariés - French employee’s national healthinsurance fundUncontrolled chain fission reaction triggered in
an environment containing fissile materials suchas uranium-235 or plutonium-239

I R S N 2005 ANNUAL REPORTCSGDCommission de Sûreté chargée de la Gestion
des Déchets - French waste management safetycommission

CSLU
Commission de Sûreté des Laboratoires et Usines French laboratories and factories safetycommission

CST
Commission de Sûreté des Transports - Frenchtransport safety commission

CTC
Centre Technique de Crise - Technical crisis
centreCTHEN
Centre Technique d’Homologation desÉquipements Nucléaires - Technical centre fornuclear equipment approval

CTHIR
Centre Technique d’Homologation del’Instrumentation de Radioprotection Technical centre for the radiologicalinstrumentation approval

D
DAM
Direction des Applications Militaires - Military
applications division (CEA)DATARAD
Database of radioactivity measurements

DDASS
Direction Départementale des Affaires Sanitaireset Sociales - French departmental administration
for health and social affairs

DDE
Direction Départementale de l’Équipement French departmental administration for public
engineering

DECOVALEX
DEvelopment of COupled models and their
VALidation against EXperiments in the nuclear
waste field

DEND
Direction de l’Expertise Nucléaire de Défense -Radioprotection - General department for
nuclear safety and radiological protection

DISCO
German experimental programme on direct
heating of the reactor containment when corium
is ejected out of the vessel

DISCO
Banc d’essais de DISpersion de COntamination Contamination dispersion test bench (Saclay)

DISPRO
DISpersion en champ PROche - Near-field
dispersion

DIVA
Dispositif pour l’étude de l’Incendie,la Ventilation
et l’Aérocontamination - System for the study offire, ventilation and air contamination (Cadarache)

DOE
Department Of Energy (USA) - Ministry for
EnergyDosimetry
Detection, by assessment or measurement, ofthe dose of radiation (radioactivity) absorbed bya substance or a person

DPPR
Direction de la Prévention des Pollutions et desRisques - Division for prevention of pollutions
and risks (IRSN)DRACCAR
Deformation and reflooding of a fuel rod
assembly during a loss of coolant accident,
computation software program used to predict
the behaviour of a fuel rod assembly

DRASS
Direction Départementale des Affaires Sanitaireset Sociales - French regional administration for
health and social affairs

DRIRE
Direction Régionale de l’Industrie, de la Recherche
et de l’Environnement - French regional
directorate for industry, research andthe environment

DRT

Division for nuclear defence expertise

Direction des Relations du Travail - Staff relations
department (IRSN)

DGA

DSND

Délégation Générale pour l’Armement - French
general delegation for armaments

Délégué à la Sûreté Nucléaire et à laradioprotection pour les activités et les
installations intéressant la Défense - Nuclear
safety and radiological protection representative
for activities and facilities relating to defence

DGSNR
Direction Générale de la Sûreté Nucléaire et de la

I R S N 2005 ANNUAL REPORT

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E

EPR

EBMT

ERICA

European cooperative group for Blood andMarrow Transplantation

EBRD
European Bank for Reconstruction andDevelopment

ECC

Environmental Risk from Ionising Contaminants:
Assessment and management

ERMSAR
European Review Meeting on Severe Accident
Research

EURANOS

European Community Commission

European approach to nuclear and radiologicalemergency management

ECCR

EURATOM

European Committe on Radiation Risk (CERI in
French)EURopean ATOMic energy community

EDEN

EUROpean uranium enrichment by gaseous
DIFfusion plant (Pierrelatte)

Elementary Dose Evaluation for Natural
Environment

EDF
Électricité De France - French national electricutility

EDZ
Excavation Disturbed Zone

EMRAS
Environment Modelling for Radiation Safety Environmental modelling programme forradiological protection

ENSRA
European Nuclear Security Regulators
Association

ENVIRHOM

EURODIFEUROFAB
FABrication en EUROpe, project which is part ofthe programme for disposal of Russian andAmerican military plutonium exceeding defence
requirements

EURSAFE
European project of the 5th FPRD on research
priorities in the field of severe accidents

EXTREME
Research programme aimed at studying theconsequences of extreme climatic events on thetransfers of radioactivity between thecompartments of the environmentF

Research programme aimed at studying theradionuclide accumulation processes and thebiological effects, during this accumulation,induced in the living organisms of plants, animals
and humans subjected to chronic exposure

FASSET

EOT

FBFC

Échelon Opérationnel des Transports Operational transport section (IRSN)

Société Franco-Belge de Fabrication de
Combustibles - Franco-Belgian fuel manufacturer

EPIC

FGI

Experimental Platform In Chernobyl

Franco-German Initiative for Chernobyl

EPICE

FIRST

Évaluation des Pathologies Induites parles contaminations chroniques en CÉsium Assessment of the pathologies induced bychronic contamination by caesium

Further Improvement of Radiotherapy of cancer
through side effect reduction by innovative application of adult Stem cells transplantation forprevention and Treatment of deterministic radiation
effects - Research programme of the 6th FPRDEPICUR
Cobalt-60 irradiator used to study the behaviourof iodine under radiation (Cadarache)

EPR
European Pressurised water Reactor

166 ]Electronic Paramagnetic ResonanceI R S N 2005 ANNUAL REPORT

Framework for ASSessment of Environmental
impacT

FLAMME_S
Software that simulates in a simple manner theevolution of carbonated product fires ininstallations comprising mechanically ventilated,confined premises

FLAMME_S/SIMEVENTGPD

FLAMME_S software combined with SIMEVENT
software that simulates a fire in a group ofpremises connected by a ventilation system anddoors

Standing advisory group of experts for waste

Foundation raft
Reactor foundations in a nuclear power plant

FPRD
Framework Programme for Research andDevelopment (European Union)

FPRTD
Framework Programme for Research andTechnological Development (European Union)

FPT-3
PHEBUS FP test dedicated to studying the effectsof B4C on the degradation of a reactor core andon the release of fission products

FRED
Fasset Radiation Effects Database - Databasecreated during the European FASSET programme(5th FPRD)

Fuel assembly
Cluster of fuel rods, connected with a metallic
structure, used in nuclear reactors

FUTURAEA Future for Radioecology in Europe

FzK
Forschungszentrum Karlsruhe - German research
centreGPR
Standing advisory group of experts for nuclear
reactors

GPU
Standing advisory group of experts for plants

GRNC
Groupe Radioécologie Nord-Cotentin - NordCotentin Radioecology Group (France)

GRS
Gesellschaft für Anlagen- und Reaktorsicherheit(Germany) - German IRSN counterpart

GWj/t
Fuel burnup rate. Giga Watt Days per tonne offuel, customary unit for measuring fuel assembly
irradiation, expressed as the energy extracted
from the assembly in the reactor per tonne ofinitial uranium

H
Hatch
Device for large equipment access in the reactor
building

HDR
Eligibility to supervise research

Hematopoietic cells
Cells from which the various blood cells areformed (red cells, white cells, platelets)

G
Gamma (γ symbol)
Highly penetrating but not very ionising
electromagnetic radiation, emitted during thedisintegration of radionuclides. Shielding of
concrete or lead is necessary to protect persons

GAMA
OECD focus group on severe accidents in nuclear
reactors

GATeL
Génération Automatique de Tests à partir d’une
description Lustre - Automatic generation of tests
from a Lustre description

GDP
Gaseous Diffusion Plants (Areva NC)

HFD
Haut Fonctionnaire de Défense du ministère del’Économie, des Finances et de l’Industrie - FrenchHigh Civil Defence Servant of the Ministry for
Economy, Finance and Industry

HLLL
High-Level and Long-Lived

HRD
Human Resources Division

HTR/VHTRHigh Temperature Reactor/Very High Temperature
Reactor

I

GOR

IAEA

General Operating Rules

International Atomic Energy Agency

GP

ICARE

Standing advisory group

Interprétation des Cœurs Accidentés pour les

I R S N 2005 ANNUAL REPORT[ 167

Réacteurs à Eau, code de calcul simulant ladégradation d’un cœur de réacteur à eau durant
un accident grave - Interpretation of damaged
cores for water reactors, computer code
simulating the degradation of a water reactor
core during a severe accident

InVS

ICARE-CATHARE

IPSN

Scientific computation software that accurately
describes the reactor core degradation up until
tank rupture during a core meltdown accident

ICPE
Installation Classée pour la Protection del’Environnement - Classified installation forthe protection of the environment

ICRP
International Commission on RadiologicalProtection

ICSBEPInternational Criticality Safety Benchmark
Evaluation Project

ICST
Ingénierie de la Connaissance Scientifique etTechnique - Scientific and technical knowledge
engineeringIEC

Institut de veille sanitaire - French national
institute of public health surveillance

IPPE
Institute of Physics and Power Engineering (Russia)
Institut de Protection et de Sûreté Nucléaire Institute for nuclear safety and protection

IRIS TÜM
Irradiation device for fuel plates of research
reactors

IRMA
IRradiation MAterial - Cobalt-60 irradiation cell,
test facility intended to study the response todose and/or dose rate exposure (Saclay)

IRS
Incident Reporting System. This is the onlyinternational report system at the disposal ofsafety authorities and government organisations.
It provides an evaluation of the most important
events for safety occuring in nuclear plants, aswell as detailed information on the analyses ofprimary causes and the lessons learnt in terms ofsafety. The IRS is managed by a joint secretariat
formed by the NEA and IAEA

International Electrotechnical Commission

IRSN

IGR
Gustave Roussy Institute (France)

Institut de Radioprotection et de Sûreté Nucléaire French institute for radiological protection andnuclear safety

IGS

ISIS

Institute of Geological Sciences (Ukraine)

Calculation software that precisely simulates the
progress of a fire, gas, smoke and structures in
confined spaces with mechanical ventilation

INBS
Secret basic nuclear installationISO
INERISInternational Standard Organisation

Institut National de l’Environnement industriel etdes RISques - French national institute for theindustrial environment and hazards

ISO 9001

INEX 3INternational EXercise (3rd of this type) International emergency exercise in case of
nuclear accident

Isotopes

Institut National de la Propriété Industrielle French national institute of industrial property

Elements whose atoms have the same number ofelectrons and protons, but a different number ofneutrons: they have the same name and thesame chemical properties. Around 325 natural
isotopes and 1,200 artificially-created isotopes
are currently listed

INRETS

ISTC

Institut National de REcherche sur les Transports
et leur Sécurité - French national institute fortransport and safety researchInternational Science and Technology Center Russian institute conducting civilian research
programmes in laboratories previously engaged
in military activities

INPI

INRS
Institut National de Recherche et de Sécurité French national research and safety institute168 ]European standard for quality-based
management systems

I R S N 2005 ANNUAL REPORT

IURInternational Union of Radioecology

J
JAEA
Japan Atomic Energy Agency

K
KAERI

program which calculates the corium-waterinteraction or vapour explosion

MEDD
Ministère de l’Écologie et du Développement
Durable - French Ministry for Ecology andSustainable Development

MEDEC
French health exhibition

MELODIE

KINS

Modèle d’Evaluation à LOng terme des Déchets
Irradiants Enterrés - Model for the long-term
assessment of buried radioactive waste

Korea Institute of Nuclear Safety

Mesenchymal

KROTOS

Relating to embryonic connective tissue

Facility intended to study the corium-waterinteraction, and more specifically the vapour
explosion resulting from a rapid energy transferfrom corium to water (CEA)mGy

Korea Atomic Energy Research InstitutekV
kiloVolt

L
L3-COM-MAPPS
Industrialist (Canada)

LECI
Laboratoire d’Examen de Combustibles Irradiés Laboratory for Study of Irradiated Components
(CEA)

LMDN
Laboratoire de Métrologie et de Dosimétrie desNeutrons - Laboratory of metroloy and neutron
dosimetry (Cadarache)

LOCA
Loss Of Coolant Accident of a PWR

LOLF
Institutional act on the finance law

LPG
Liquified Petroleum Gas

M
M5
Type of pressurised water fuel cladding

Masurca
Breeder model - Research reactor (CEA)

MC3D
Multi Composants 3 Dimensions - Software

Milligray - Unit of absorbed radiation dose of
the international system of units

MICADO
Model uncertainty for the mechanism of
dissolution of spent fuel in nuclear waste
repository - European project of the 6th FPRD
on the influence of uncertainties regarding therelease of spent fuel radionuclides on the overall
safety of a geological disposal

MIMAUSA
Mémoire et Impact des Mines Anciennes
d’Uranium : Synthèse et Archivage - Memory andimpact of uranium mines: summary and archives

MINEFI
Ministère de l’Économie, des Finances etde l’Industrie - French Ministry for Economy,
Finance and Industry

MLLL
Medium-Level and Long-LivedMONTE CARLO
Design method based on random draws

MORET
Monte Carlo code for simulation of neutrontransport (multi-group approximation) to
calculate the effective multiplication factor (keff)of three-dimensional complex systems.

MOX
Fuel of uranium (natural or depleted) andplutonium oxides

MOZART
Analytic tests to study the oxidation kinetics ofclads under air

MSC
Mesenchymal Stem Cells

mSv
Millisievert - Unit derived from dose equivalentof the international system of unitsI R S N 2005 ANNUAL REPORT

[ 169

MWe

NurethMegaWatt electric

Congress attended by specialists in nuclear
reactor thermal-hydraulics

N
N4
N4 series, series of 1,450 MWe pressurised water
reactors operated by EDF

OCNS

NAGRA

OECD

Nationale Genossenschaft für die Lagerung
radioaktiver Abfälle (Switzerland) - National
cooperative for radioactive waste storage,organisation in charge of the radioactive waste
disposal

OECD/NEA:

NEA
Nuclear Energy Agency of the Organisation for
Economic Co-operation and Development(OECD)NF-PRO

Office for Civil Nuclear Security
Organisation for Economic Co-operation andDevelopment (European Union)
OECD Nuclear Energy Agency

OJ
Official Journal

OPCW
Organisation for the Prohibition of Chemical
Weapons

Near Field PROcesses

OPERA

NNSA
National Nuclear Safety Administration (China)

Observatoire PErmanent de la RAdioactivité dansl’environnement - Permanent Environmental
Radioactivity Observatory

NRC

OPRI

NSRR

Office de Protection contre les Rayonnements
Ionisants - French Office for Protection against
Ionising Radiation

Nuclear Safety Research Reactor (Japan)

OSIRIS

Nuclear fuelExperimental reactor (CEA)

Nuclear Regulatory Commission (USA)Fissile material (capable of undergoing fission
reactions) used in a reactor to develop a nuclear
chain reaction. After being used in a nuclear
reactor, this is referred to as irradiated fuelP

Nuclear island

P’4

Assembly comprising the nuclear boiler, theinstallations relating to the fuel and theequipment needed to operate and ensure thesecurity of this assembly

Plant series comprising twelve more recent
1,300 MWe water-pressurised reactors

Nuclear materials
Materials which could be used to manufacture anuclear explosive device. They are definedaccording to their fissile (for a fission device),fusible (for a thermonuclear bomb), or fertile(capacity to produce fissile or fusible materials)
characteristics. French legislation covers 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 of design,
construction, operation and decommissioning of
the nuclear installations to prevent accidents andlimit their effects

170 ]

O

I R S N 2005 ANNUAL REPORT

P4
Plant series comprising eight 1,300 MWewater-pressurised reactors at Paluel, Flamanvilleand Saint-Alban

PACA
Provence-Alpes-Côte-d’Azur region (France)

PAMINA
Performance Assessment Methodologies IN
Application to guide the development of the safetycase - European project of the 6th FPRD on thecontribution of modelling carried out as part ofthe performance assessments of geologicaldisposals, to draw up the safety dossier

PASEPRI
Plan d’Actions pour la Surveillance de l’Exposition
des Patients aux Rayonnements Ionisants - Action

plans for the monitoring of patient exposure toionising radiation

PCO
Poste de Commandement Opérationnel Operational control centre

PHARE
Poland-Hungary Assistance for Reconstruction of
the Economy

PSA2
Level 1 probabilistic safety assessment
quantifying the probabilities of fission productreleases in case of severe accident

PUI
Plan d’Urgence Interne - Internal emergency plan

PWR
Pressurised Water Reactor

PHEBUS-FP
Experimental programme on the degradation ofa nuclear reactor core and the release of fission
products (FP)R

PHEBUS FPT3

R&D

Test of the PHEBUS FP programme

Research and Development

PHENIXRadioactivity

250 MWe fast neutron reactor (CEA)

Property of certain chemical elements whose
nuclei spontaneously disintegrate into otherelements emitting ionising radiation

PIC
Programme d’Intérêt Commun - Common interest
programme

PICSEL

Radioelement
Natural or artificial radioactive element

Propagation de l’Incendie de Combustibles Solides
dans un Environnement Laboratoires et usines Propagation of solid fuel fire in a laboratory andplant environment (IRSN/Areva programme)Radiological protection

Plutonium (Pu, atomic number 94)

Radionuclide

Transuranic chemical element. The isotope 239
has a half life of 24,110 years

POLLUTEC
International trade fair for environment-related
equipment, technologies and services forindustryPrimary system
Reactor coolant system operating in a closed
loop, comprising a series of components that
ensures the circulation of water used to extract
the heat given off by the reactor core

PRISME
PRopagation d’un Incendie pour les Scénarios
Multi-locaux Élémentaires - Propagation of a firefor elementary, multi-premises scenarios (OECDprogramme)

PROTECT
Protection of the environment from ionisingradiation in a regulatory context

PSA
Probabilistic Safety Assessment

PSA1
Level 1 probabilistic safety assessment
quantifying the risks of core meltdown

Set of measures intended to ensure protection of
the population and workers against ionisingradiation sources
Radioactive isotope of an element

RAPHAEL
ReActor for Process heat, Hydrogen And
ELectricity generation

REBUS
REactivity tests for a direct evaluation of the BUrnup
credit on Selected irradiated LWR fuel bundles

RECI
RECombiner of Iodine - experimental systemused to assess the influence of recombiners on
the chemistry of iodine in the containment(Saclay)

REP-NaExperimental programme in the sodium loop of
the CABRI reactor aimed at studying the
behaviour of fuel during a power transient

RHF
Laüe Langevin Institute’s high-flux reactor(Grenoble)

RIA
Reactivity Insertion Accident

ROSATOM
Russian federal agency for atomic energy

I R S N 2005 ANNUAL REPORT

[ 171

S
SAPIDE/LUDD
Documentary database collecting the incidents
and events related to nuclear installations otherthan reactors (laboratories and plants)

SARNET
Severe Accident Research NETworkof excellence - European network of excellenceon core meltdown accidents in water reactors(6th FPRTD)

SATURNE
Experimental installation with an extractor hood
aimed at studying the progress of a fire (Cadarache)

SCANAIR
Software used to calculate an RIA-type transientPressurised water reactor accident simulator
developed and used by the IRSN

SISERI
Système d’Information de la Surveillance del’Exposition aux Rayonnements Ionisants Ionising radiation exposure monitoring
information system

Site effect
Modification of the characteristics of seismic
movements resulting from the mechanicalproperties of soils or topography. It may increase
the devastating effect of an earthquake

SNA
Nuclear attack submarine

SCPRI

SNG

Service Central de Protection contre lesRayonnements Ionisants - French central service
for protection against ionising radiation

SNLE

SDIS

New generation submarine
Nuclear-powered ballistic missile submarine

Service Départemental d’Incendie et de Secours French departmental fire and rescue service

SNM

SENSIBSPNSENSIBilité radioécologique, projet de recherche Radioecological sensitivity, research project

SERENA
Steam Explosion REsolution for Nuclear
Applications (OECD programme)

SESAME
Schéma d’Évolution des Situations Accidentelles etMéthodes d’Évaluation - Accident progression
analysis and assessment methods

SEVESO
Accident happened in Italy in 1976 which gave
its name to a European directive on industrial
accident risks

SGDN
Secrétariat Général de la Défense Nationale French General Secretariat for National Defence

SIEVERT

Military nuclear system
Permanent nuclear section of the Central
committee for pressure vessels

SSI
StatensSträlskyddsinstitut (Sweden) - Radiologicalprotection authority

SSTC
State Scientific and Technical Center on nuclear
and radiation safety (Ukraine)

STARMANIA
Station for the study of airborne contaminationtransfer and mechanical strength under incident
and accident conditions (Saclay)

STEME
Environmental Sample Processing and Metrology
Department

Information and assessment system of the
exposure to cosmic radiation during flights

STI

SIGIS

STUK

Système d’Information et de Gestion de l’Inventaire
national des Sources de rayonnements ionisants Information and management system for thenational inventory of ionising radiation sources

Stäteilyturvakeskus (Finland) - Safety authority

SIMEVENT
Software simulating aeraulics in a ventilation
system developed as part of a joint project
between the IRSN, SGN and Cogema

172 ]

SIPA

I R S N 2005 ANNUAL REPORT

Scientific and Technical InformationSYLVIA
Software system of the IRSN used to study
ventilation, fire and air contamination

SYMBIOSE
Systemic approach for modelling the fate ofchemicals in biosphere and ecosystems

T

UPRES

TACIS

Unité Propre de Recherche de l’Enseignement
Supérieur - Specific research unit for higher
education

Technical Assistance for Commonwealth of
Independent States

USDOE

TID

US Department Of Energy (USA) - Ministry for
Energy of the United States

Total Indicative DoseTONUS
Code developed by the CEA on behalf of the
IRSN using models that govern the distributionof hydrogen in the containmentTOSQAN
TonuS Qualification ANalytique - Experimental
containment used to reproduce a small-scale
accident scenario enacting a hydrogen risk in a
nuclear reactor containment (Saclay)

TROI
Test for Real cOrium Interaction - Experimental
Installation designed to study the corium-waterinteraction (Korea)

USNRC
US Nuclear Regulatory Commission (USA)V
VD3 900
Third 10-yearly outage programmes of 900 MWe
reactors

VDEW
Verbandes der Elektrizitätswirtschaft (Germany) Electricity group

VHE
Very High Efficiency

U

VHTR

UF6

Voxel

Uranium hexafluoride

UIAR
Ukrainian Institute of Agricultural Radioecology(Ukraine)

UNSCEAR
United Nations Scientific Committee on the
Effects of Atomic Radiations

Very High Temperature Reactor
Elementary volume in a digital, threedimensional framework

VVER or WWER
Vodo Vodiannoï Energititschesky Reactor or
Water Water Energetic Reactor - Russiandesigned reactors, whose operating principle
is similar to that of western pressurised water
reactors

UO2
Uranium oxides

W

UP1
Biggest plant for the reprocessing of spent
nuclear fuels with a view to them being recycled
in France (Areva NC)

WHO
World Health Organization

UP2-400
Irradiated nuclear fuel reprocessing plant,
definitely shutdown, located at the La Hague site
(Areva NC)

UP2-800
Irradiated nuclear fuel reprocessing plant, locatedat the La Hague site (Areva NC)

UP3-A
Irradiated nuclear fuel reprocessing plant, locatedat the La Hague site (Areva NC)

I R S N 2005 ANNUAL REPORT[ 173

Contents
1 Current events, strategy and organisation
Foreword by J.-F.LACRONIQUE and J.REPUSSARD . . . . . . . . . . . . 04
Foreword by M. BRIÈRE . . . . . . . . . . . . . . . . . . . . . . . . . . . 06
About the IRSN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 07
The IRSN in 2005: report and prospects . . . . . . . . . . . . . . . . . 08
[ The Governmant-IRSN objectives agreement 2006-2009 ] . . . . . . 09
[ Agreements signed by the IRSN in 2005 ] . . . . . . . . . . . . . . . 09
The IRSN in 2005, a few figures . . . . . . . . . . . . . . . . . . . . . . 11

Key events 2005 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
IRSN missions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
Sites: activities and staff . . . . . . . . . . . . . . . . . . . . . . . . . . 15
The Board of Directors . . . . . . . . . . . . . . . . . . . . . . . . . . . 16
The Scientific Board . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17
Organisation chart . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18

2 Management and support
Scientific and technical excellence . . . . . . . . . . . . . . . 23
[ Agreements signed in 2005 between the IRSN anduniversities, engineering schools or the CNRS ] . . . . . . . . . . . . . 25

Health and safety at work . . . . . . . . . . . . . . . . . . . . . 30
[ The IRSN's regulated facilities and activities ] . . . . . . . . . . . . . 32

IRSN communication . . . . . . . . . . . . . . . . . . . . . . . . 33

[ Training through research: encouraging results ] . . . . . . . . . . . . 26

[ Two questions to the Communications Division ] . . . . . . . . . . . 35

Quality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28

Human resources serving development
at the IRSN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36

[ Policy to achieve approval to become an “organiser ofinterlaboratory comparisons” ] . . . . . . . . . . . . . . . . . . . . . 29

3 IRSN activities
Programmes to achieve its missions . . . . . . . . . . . . . . 42
Research and public service missions . . . . . . . . . . . . . . 48
Defining and implementing national and international
research programmes . . . . . . . . . . . . . . . . . . . . . . . . . 50
Research work supporting the safety analysisof reactors in operation . . . . . . . . . . . . . . . . . . . . . . . . 50
[ Renovation of the SIPA 2 simulator ] . . . . . . . . . . . . . . . . . 51
Research on PWR ageing . . . . . . . . . . . . . . . . . . . . . . . . 51
[ International seminar on the impact of ageing on reliability ] . . . . . 52
Research work on human and organisational reliability . . . . . . . 51
Fuel and its management in normal and accident
operating conditions . . . . . . . . . . . . . . . . . . . . . . . . . . 52
[ Loss of coolant accident (LOCA) ] . . . . . . . . . . . . . . . . . . . 53
[ Spent fuel pit drainage accident ] . . . . . . . . . . . . . . . . . . . 54
Modification work on the CABRI installation . . . . . . . . . . . . . 55
Research work on severe accidents with core meltdown
in a PWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56
[ ASTEC, backbone of the SARNET network ] . . . . . . . . . . . . . . 56
[ Start-up of the SOURCE TERM programme ] . . . . . . . . . . . . . 57
[ PHEBUS programme: first results of the FPT3 test ] . . . . . . . . . . 58

174 ]I R S N 2005 ANNUAL REPORT[ Summary of the RECI programme ] . . . . . . . . . . . . . . . . . . 59
[ Review and prospects of the SERENA programme of OECD/NEA ] . . . 59
Safety of laboratories, plants, transport and dismantling . . . . . . 60
[ Experimental criticality programmes 2005-2008 ] . . . . . . . . . . . 61
Research work in the field of waste . . . . . . . . . . . . . . . . . . 62
[ Characterisation of disturbances caused by rock excavation ] . . . . . 63
Research work in the field of fire and air dispersion . . . . . . . . . 65
[ Continuing the Common interest programme (PIC) on fires ] . . . . . 64
[ Setting up the PRISME experimental programme ] . . . . . . . . . . . 65
[ Development of the ISIS software ] . . . . . . . . . . . . . . . . . . 66
[ Simplifying the modelling of ventilation systems
in case of fire ] . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67

Research on naturally-occurring hazards:
earthquakes and floods . . . . . . . . . . . . . . . . . . . . . . . . 68
[ Agreement on co-operation with the Universityof Chile on seismic hazards ] . . . . . . . . . . . . . . . . . . . . . . 68

Radioecology research . . . . . . . . . . . . . . . . . . . . . . . . . 69
[ Radioactive deposits linked with Saharan dust
falling in France ]. . . . . . . . . . . . . . . . . . . . . . . . . . . 70

[ Participation of the IRSN in European radioecology projects ] . . . . . 71

Research on metrology for radionuclides
in the environment . . . . . . . . . . . . . . . . . . . . . . . . . . . 72
Chronic risks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72
[ Presentation of the ENVIRHOM programme
to the scientific committee ] . . . . . . . . . . . . . . . . . . . . . 73
Research work on radon . . . . . . . . . . . . . . . . . . . . . . . . 75
Epidemiology of nuclear workers . . . . . . . . . . . . . . . . . . . . 76
[ Quantification of cancer risks ] . . . . . . . . . . . . . . . . . . . . 76
Improvements in radiological protection . . . . . . . . . . . . . . . 77
The AMANDE installation . . . . . . . . . . . . . . . . . . . . . . . . 79
Radiological protection in the medical field . . . . . . . . . . . . . 79
[ Work will continue at UPRES EA 27-10 ] . . . . . . . . . . . . . . . 79
Irradiation and contamination accidents . . . . . . . . . . . . . . . 80
[ Bio-indicator of damage to bone marrow ] . . . . . . . . . . . . . . 80
[ Completion of the contract with DGA on molecular therapeutics ] . . . 82
Management of post-accident situations . . . . . . . . . . . . . . . 82
[ Analysis and quantification of atmospheric fallout
in France following the Chernobyl accident ] . . . . . . . . . . . . . . 83

International programmes and agreements . . . . . . . . . . . . . . 83
[ Tripartite co-operation in case of radiological accident ] . . . . . . . . 84
[ Franco-Russian co-operation ] . . . . . . . . . . . . . . . . . . . . 84
[ Studies of pathologies in children in Bryansk oblast ] . . . . . . . . . 85
Radiological protection : strengthening Frenchpresence internationally . . . . . . . . . . . . . . . . . . . . . . . . 86
[ The IRSN defines its position on environmental
radiological protection ] . . . . . . . . . . . . . . . . . . . . . . . . 86
[ Controversy over the effects of internal contamination ] . . . . . . . . 87

Contributing to training in radiological protection . . . . . . . . . 88
Support for the prevention of radiological risks
and to limit their consequences . . . . . . . . . . . . . . . . . . . . 88
[Setting up of a training course on the radioactivity ofwater for engineers and technicians from Ddass and Drass ] . . . . . . 88
[ Training sessions provided in 2005 ] . . . . . . . . . . . . . . . . . . 89
[ Professional training programmes offered ]. . . . . . . . . . . . . . 90

Permanent monitoring in the field of radiological protection . . 91
Radiological monitoring of the environment . . . . . . . . . . . . . 91
[ Examining the objectives of environmental monitoring ] . . . . . . . . 92
Permanent monitoring in matters of radiological protection . . . . 92
Contributing to public information and transparency . . . . . . . 94
Public information . . . . . . . . . . . . . . . . . . . . . . . . . . . 94
Opening up expertise for society . . . . . . . . . . . . . . . . . . . 96
[ Pilot project with CLIs concerning radioactivity
in the environment in the Loire basin ]. . . . . . . . . . . . . . . . 96

[ The IRSN's participation in the public debate
on the first-off EPR project in Flamanville ]. . . . . . . . . . . . . . 97

Technical support and assistancefor public authorities . . . . . . . . . . . . . . . . . . . . . . . . 98
Technical support with regard to nuclear andradiological risk . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100
Safety analysis of nuclear reactor . . . . . . . . . . . . . . . . . . 100[ Safety review associated with the third 10-yearly
outage programmes of 900 MWe reactors ] . . . . . . . . . . . . . . 101[ Risk of spent fuel pit drainage ] . . . . . . . . . . . . . . . . . . . 102[ Incident in Nogent-sur-Seine ] . . . . . . . . . . . . . . . . . . . . 103[ Seminar in China on the EPR reactor project ] . . . . . . . . . . . . 104[ Standing advisory group for nuclear reactors ] . . . . . . . . . . . . 105
Support for the safety analysis of reactors in operation . . . . . . 106[ Radiological consequences of accidents ] . . . . . . . . . . . . . . 107
Ageing of pressurised water reactors (PWR) . . . . . . . . . . . . . 108
Human and organisational reliability . . . . . . . . . . . . . . . . . 108
Fuel behaviour in normal and accident
operating conditions . . . . . . . . . . . . . . . . . . . . . . . . . 109
Examination of risks associated with severe reactor
core meltdown accidents . . . . . . . . . . . . . . . . . . . . . . . 109[ “Severe accidents” standard ] . . . . . . . . . . . . . . . . . . . . 110[ Using the level 2 PSA in safety analysis ] . . . . . . . . . . . . . . . 111
Fourth generation reactors . . . . . . . . . . . . . . . . . . . . . . 110
Safety of plants, transport and dismantling . . . . . . . . . . . . . 111[ Use of feedback of incidents ] . . . . . . . . . . . . . . . . . . . . 113
Radioactive waste management safety . . . . . . . . . . . . . . . 114[ Key figures of the Dossier 2005 Argile ] . . . . . . . . . . . . . . . 114[ Assessment of the dossier regarding the mine site
at Les Bois Noirs ] . . . . . . . . . . . . . . . . . . . . . . . . . . 116
Protection of installations against fire and explosion . . . . . . . . 117[ Guide to assess the risks of explosion ] . . . . . . . . . . . . . . . 117
Risks associated with external hazards . . . . . . . . . . . . . . . . 117
Population exposure to fallout from nuclear weapons . . . . . . . 118
Environmental monitoring . . . . . . . . . . . . . . . . . . . . . . 119[ Health impact of medical-origin effluents ] . . . . . . . . . . . . . 119[ Increase in participation in cross-comparison exercises ] . . . . . . . 120
Technical support in the field of radon . . . . . . . . . . . . . . . . 120[ Radon measurement in spas ] . . . . . . . . . . . . . . . . . . . . 121
Radiological protection response and assistance . . . . . . . . . . 121
Radiological protection of workers . . . . . . . . . . . . . . . . . . 122[ Reconstitution of a dose after a radiologicalprotection incident ] . . . . . . . . . . . . . . . . . . . . . . . . . 122
Radiological protection in the medical field . . . . . . . . . . . . . 123[ Study of the doses received by premature babies ] . . . . . . . . . . 124
Multilateral scientific co-operation:
strengthening the IRSN's contribution to IAEA andOECD/NEA work . . . . . . . . . . . . . . . . . . . . . . . . . . . . 125[ Strengthening of co-operation with China ] . . . . . . . . . . . . . 125[ EUROSAFE 2005 ] . . . . . . . . . . . . . . . . . . . . . . . . . 125

I R S N 2005 ANNUAL REPORT[ 175

Operational support in the event of a crisis
or radiological emergency . . . . . . . . . . . . . . . . . . . . . . 126
Crisis management . . . . . . . . . . . . . . . . . . . . . . . . . . 126[ Real actions of the IRSN's CTC for real situations ] . . . . . . . . . . 127[ Use of pectin to decorporate caesium 137 ] . . . . . . . . . . . . . 128[ Gammagraphy source accident in Chile ] . . . . . . . . . . . . . . 129
Support in managing post-accident situations . . . . . . . . . . . 130[ Post-accident crisis exercise ] . . . . . . . . . . . . . . . . . . . . 130[ IRSN mobile intervention means ] . . . . . . . . . . . . . . . . . . 131

Dosimetric services . . . . . . . . . . . . . . . . . . . . . . . . . . 142
Radiological protection in the medical field . . . . . . . . . . . . . 143
Operational radiological protection services . . . . . . . . . . . . . 144[ Radiological expert assessment of a device
for import into France ] . . . . . . . . . . . . . . . . . . . . . . . . 145

Collaboration with Eastern European countries . . . . . . . . . . . 146[ Stabilisation of the sarcophagus of the damaged reactor
at the Chernobyl power plant ] . . . . . . . . . . . . . . . . . . . . 146[ Riskaudit ]. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 146[ Expert assessments as part of the G8 global partnership ] . . . . . . 147

Contractual services in expertise, research
and measurements . . . . . . . . . . . . . . . . . . . . . . . . . 132
Services related to statutory requirements . . . . . . . . . . . . 134
Radiological testing of water intended
for human consumption . . . . . . . . . . . . . . . . . . . . . . . 134
Radon detection . . . . . . . . . . . . . . . . . . . . . . . . . . . . 134
Radiological protection of workers . . . . . . . . . . . . . . . . . . 135[ Changes in external exposure monitoring ] . . . . . . . . . . . . . . 135
Conformity of materials and equipment . . . . . . . . . . . . . . . 136[ Cross-comparison of operational dosimeters ] . . . . . . . . . . . . 136
Statutory inspections in radiological protection . . . . . . . . . . . 136
Non nuclear services . . . . . . . . . . . . . . . . . . . . . . . . . 137
Services not related to statutory requirements . . . . . . . . . 138
Study of the radioactivity of effluentsfrom the Tours treatment plant . . . . . . . . . . . . . . . . . . . . 138[ Sale of low-activity standard sources ] . . . . . . . . . . . . . . . . 138
Safety of plants, transport and dismantling . . . . . . . . . . . . . 138[ Support services for the users of the CRISTAL package ] . . . . . . . 139
Studies regarding Nigerian Areva mining sites . . . . . . . . . . . . 139
Radioecology services . . . . . . . . . . . . . . . . . . . . . . . . . 140
Services concerning radon . . . . . . . . . . . . . . . . . . . . . . 141
Modelling of facility ventilation . . . . . . . . . . . . . . . . . . . 141[ Ventilation performance - transfer of pollutants ] . . . . . . . . . . 142

176 ]I R S N 2005 ANNUAL REPORT[ Emergency shutdown system for the reactor no. 2
in the Ignalina power plant ] . . . . . . . . . . . . . . . . . . . . . 147

Nuclear defence expertise . . . . . . . . . . . . . . . . . . . . 148
Assessment of the safety of military nuclear systems,
secret basic nuclear installations anddefence-related transport . . . . . . . . . . . . . . . . . . . . . . 150
Protection and control of nuclear and sensitive materials . . . . 154
Physical protection of nuclear materials . . . . . . . . . . . . . . . 154
Monitoring of and accounting for nuclear materials . . . . . . . . 155
Transport of nuclear materials . . . . . . . . . . . . . . . . . . . . 156
International controls on non-proliferation . . . . . . . . . . . . . 156[ Protection and control of nuclear materials
during the EUROFAB operation ] . . . . . . . . . . . . . . . . . . . 157

Protection against malicious acts . . . . . . . . . . . . . . . . . . 159[ The convention on physical protection ] . . . . . . . . . . . . . . . 160[ The nuclear safety culture ] . . . . . . . . . . . . . . . . . . . . . 161

Glossary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 162

Finance Ledger ofthe Annual Report

2005Didier DEMEILLERS,
Director in charge of Financial Affairs

Contents
04

Management report10

Profit & Loss account

12

Balance sheet

14

Intermediate management balances

15

Forecast and completion reconciliation

14

Self-financing capacity

15

Variation in liquid funds

[

FINANCIAL LEDGER
OF THE 2005 ANNUAL REPORT]Management report
1. OVERALL OUTLOOKThe year 2005 has seen the implementation of a

€ 10 million of appropriations (that is, 3% of therevised tax system, excluding from liability to VAT the

IRSN’s budget) between operational activities andgrant for the operation of the Institute provided byinvestment has been effected in order to undertake

the State via the Ministry for Ecology and Sustainable

these operations, within the framework of the budgetary

Development (MEDD). This modification of the tax

interchangeability from which the Institute benefits.

system, extended to the grant provided by the

In accordance with the directives in the matter, this

Ministry of Defence has, for the first time in 2005,

amendment did not require the approval of the Board

enabled the presentation of a balanced statement ofof Directors, inasmuch as it did not affect the overall

receipt and expenditure forecasts (EPRD).The budgetbalance of the budget nor impair the result. These

deficit, recurring since the creation of the IRSN, hasoperations, launched in the second half of 2005, aredisappeared. However, this balance will automa-

not completed at the end of the financial year, thustically disappear as from 2006, because of theinvolving a carry-over of appropriations of € 12.2

implementation of payroll tax. It will be definitively

million in working capital, for re-application in 2006.

restored if the fiscal legislation department (DLF)
confirms the alignment of the business and corporation taxes with the limitation of the principle ofprofitability, which governs the new VAT system for
the Institute. Furthermore, amending decision
no.1-2005 (DM1-2005), presented to the Board of
Directors in June 2005, incorporated the carrying

Budgetary balance
F/year(in € million)

2003

2004

2005

Variation
2005/2004

Total resources

242.9

247.2

287.7

+16.4%

Total expenditures

246.1

258.0

268.2

+4.0%

Balance

-3.2

-10.8

19.5

NB

forward of investments not terminated in the 2004
financial year, i.e. € 2.2 million, paid into working
capital at closure 2004. Almost all these operations
were balanced in the financial year.

prospectively overvalued by the carrying forward ofinvestments of € 12.2 million.

The implementation of the 2005 budget had as its

Over 2005, the modification of the tax system (pro-main objective the effective recovery of balances, inrata VAT system) generated additional receipts ofconformity with the EPRD, and the resumption of€ 33 million and additional expenditure of approxi-

investment, whose level had been significantly reduced

mately € 23 million, corresponding to the VAT which

during previous financial years, while essentiallyhas become irrecoverable. The difference, approxi-

achieving the scientific and technical goals pursued.

mately € 10 million, has enabled absorption of the

A number of new urgent matters having appearedbudget deficit resulting from the underestimation ofwith regard to investment during this financial year.

the tax provision allowed for on creation of the IRSN

It was considered preferable to redeploy, in favour

in 2002.

of these programmes, the resources allocated to

All in all, the financial year 2005 is therefore marked

operational activities, rather than revising the invest-

by:ment plan initially envisaged. The most significantof these operations relates to the modernization of

4]

The 2005 operation shows a budgetary balance

the observance of the EPRD 2005 balances
approved by the Board of Directors;

the IRSN offer as regards dosimetry (dosage measure-a rate of budget realization of 95.7% (againstment) in respect of the workers, the replacement of

97.5% in 2004), a variation of €13 million with thesilver film by digital technology being imposed de

EPRD, corresponding to € 12.2 million throughfacto in the short term by the market. A transfer ofirregular realization of certain investments.

I R S N 2005 ANNUAL REPORT

2. INCOME STATEMENT ANALYSIS
2.1.2.

2.1. Income

Financial income, amounting to € 1.2 million, is lower
F/year(in € million)

2003

2004

2005

Variation
2005/2004

Turnover

36.6

35.2

36.1

+2.6%

Grants

198.1

206.7

240.2

+16.2%

Other operating
income

1.8

3.7

2.2

-40.5%

Financial income

1.0

1.4

1.2

-14.3%

than in the preceding year (- € 0.2 million, i.e.-14%)
by reason of a more even spread of the Institute’s
operating expenditure throughout the financial
year, in particular with its principal supplier, the CEA

Extraordinary
income

25.2

6.7

4.2

-37.3%

Total

262.7

253.7

283.9

+11.9%

2.1.1.
Increased by € 32.9 million in comparison with
2004 (+13.4%), operating income amounts to€278.5 million, including:€236.8 million for the grant from MEDD, an increaseof € 34.9 million, because of non-subjection to VAT,
due to modification of the tax system.

€2.9 million under the agreement with the Ministryof Defence, being a slight increase ( € 0.2 million)
due to modification of the VAT system, adjusted tothat applicable to the grant from MEDD.

€ 0.5 million in respect of other grants, in particularfrom local authorities, as against € 2 million in the(expenses of centres, scientific subcontracting, BNI,etc.).

2.1.3.
Extraordinary income is lower at € 4.2 million. It
essentially consists of the share of investment
grants inherited from the CEA, a share transferred tothe income statement (€ 3.8 million). These accounting operations, not affecting the balance of thebudget, will continue to decrease gradually until
they disappear completely.
Total income for the 2005 financial year amounts to€ 283.9 million as against € 253.8 million in 2004and € 261.7 million in 2003.

2.2. Expenditureprevious year.

€ 36.1 million of own resources (as against€35.2 million in 2004) from the expert activity of theF/year(in € million)

2003

2004

2005

Variation
2005/2004

Purchases

124.9

118.0

128.7

+9.1%

IRSN, other service provision or co-financing of

Personnel

103.3

107.7

109.2

+1.4%

research programmes. These resources are fairly

Taxes and dues

1.4

1,3

1.2

-7.7%

stable in comparison with the preceding financial

Depreciation

25.0

13.6

13.4

-1.5%

year, the increase of 2.6% enabling compensation for

Provisions

3.4

4.2

8.3

+97.6%

inflation. This stability masks a loss of market share

Other

3.0

1.2

2.1

-75.0%

in dosimetric activity, compensated overall by the

S/T Operation

261.0

246.0

262.9

+6.9%

increase in turnover in other fields.

Financialexpenditure

NB

NB

0.1

NB

for the preceding year.This income includes royalties

Extraordinary
expenditure

0.3

13.8

0.4

NB

related to industrial property (€0.1 million, stable),

Total

261.3

259.8

263.4

+1.4%

€2.2 million of sundry income as against €3.8 million

sundry current management income (€0.4 million,
stable), write-backs on depreciation and provisions(€0.5 million, increasing) and finally €1.2 million ofcancellation of accruals in respect of previous financial
years, as against €3.3 million in 2004.

I R S N 2005 ANNUAL REPORT[5

[

FINANCIAL LEDGER
OF THE 2005 ANNUAL REPORT]

2.2.1.

assessed at €19 million (16.6%, i.e. 85% of 19.6%)

Operating expenditure for 2005, amounting toin respect of irrecoverable VAT. Other charges of€ 262.9 million, is appreciably higher (by € 16.9

€2.1 million, as against €1.2 million in 2004. They

million, i.e. +6.9%) in comparison with 2004. This

represent cancellations of receipts issued in previous

increase is due to the modification of the Institute’s

financial years for €0.5 million and royalties paid fortax system, with the arrival of an irrecoverable VAT

use of patents and software of €1.4 million.

charge, representing 85% of the VAT paid to suppliers.
The operating expenditure breaks down as follows:

F/year(in € million)

2003

2004

2005

Variation
2005/2004

Total personnel charges, including the employees

60 - Purchases

43.3

58.3

69.1

+18.5%

provided by the CEA (+ €3.5 million, as compared61 - External
services

63.6

42.3

41.1

-2.8%

on remuneration (+€2.1 million): €109.2 million in

62 - Other external
services

18.0

17.4

18.4

+5.7%

2005, as against €107.7 million in 2004 and a forecast

Total

124.9

118.0

128.6

+9.1%

with the accounts closed by the accountant) and tax

in the DM1-2005 of €110 million. This reduction of€0.8 million is explained by variations occurring in

The reading of this table shows:

the realization of the Institute’s recruitment plans.

the stability of item 60 - purchases, the variation

Taxes and dues: €1.2 million (i.e. €3.3 million -of 18.5% resulting from the combined impact of€2.1 million, reprocessed above in personnel charges)

irrecoverable VAT (16.6%) and inflation (1.9%);

as against €1.3 million in 2004.This posting is broadly

a drop in item 61 - external services, resulting inless than the forecast in DM1-2005, by an amountparticular from the reduction in subcontracting at theof €5.4 million, but a provision for contingencies

heart of the business, attributable to the increase in

and charges is allowed for in the sum of €4.7 million,

capacity of the Institute’s workforce;in respect of the taxes for 2005, unknown on closurea relative drop, taking into account the irrecoverableof the accounts. This provision is constituted in

VAT effect, in item 62 - other external services, aparticular for business tax, the assessment of which

reduction attributable to better control by the Instituteis effected according to the recommendation of theof its activities and costs.

DLF, by way of precaution, by limiting added value inrespect of the business as a whole.

Financial expenditure of €0.1 million comes prima-

relation to the previous year (€13.6 million), but inrily from the interest on the loan contracted for theslight decline in comparison with the DM1-2005

financing of the purchase of the UIS building at(€14 million).Allocation to provisions is €8.3million,

Fontenay-aux-Roses.The charge corresponding to theincluding €4.7 million for taxation (see above) andflat-rate annual tax (corporation tax scheme) is cited€3.6 million for commitments in respect of earlyby way of reminder.

retirement (Capron agreement).

The extraordinary expenditure of € 0.4 million as

Purchases of goods and services of €128.7 million,

6]

2.2.2.

Depreciation in the sum of €13.4 million, stable inagainst € 13.8 million in 2004 will henceforth beas against €118 million in 2004.

insignificant. The total of expenditure for the finan-This increase in fact masks a reduction in volume ofcial year is €263.4 million, as against €259.8 million

about €8 million, compensated by the tax impact

in 2004 and €261.3 million in 2003.

I R S N 2005 ANNUAL REPORT

3. RESULT AND FINANCING
F/year(in € million)

2003

2004

2005

Variation
2005/2004

Result

0.4

-6.0

20.4

NB

SFC

10.3

5.1

37.8

+641.2%

Variation ofworking capital

-3.2

-10.8

19.5

NB

to provisions (taxation and pensions), provided forin the EPRD in the form of charges and not provisions.
The IRSN’s self-financing capacity is therefore
increased to €37.8 million to ensure the financing
of its investments. Total projects launched in 2005

3.1.
The financial year shows a profit of €20.4 million as
against a loss of €6 million in 2004 and a profit of€0.4 million in 2003.
Moreover, the amending decision of the EPRD forecast
a profit of €8.5 million for 2005. The variation of€11.9 million (i.e. €20.4 million - €8.5 million) incomparison with the DM1-2005 is explained by:a reduction in operating expenditure in consequenceof the need for redeploying the Institute’s budgets
in order to effect certain investments, for an overall
total of €10 million, not provided for in the DM12005;
an increase of €0.1 million in the financial income

or deferred from 2004 amount to €38.6 million, theexecution of which has been effected up to€26.4 million, which results in the carrying forward
to 2006 of a total amount of € 12.2 million, thebalance of these operating commitments. Significant
in amount, this carrying forward is explained both by
the delay involved in certain operations and thelaunching during the year of certain projects notinitially provided for. This €12.2 million, included inworking capital in respect of 2005, shall be the subjectof a withdrawal from working capital in respect of2006, in accordance with the instructions from the
Budget department (circular 4BCJS-05-3152 of
1 August 2005).

of the Institute;
extraordinary income of €0.3 million;
cancellation of accruals, issued in previous financial
years, of €1.2 million;
reduction of depreciation expenditure of€0.6 million;on the other hand, a reduction in the share ofinvestment grant transferred to the income statement,
which reduces this profit by €0.3 million.

3.2.
The Institute’s self-financing capacity (SFC), initially
fixed at €17.6 million in the EPRD, is automaticallyadjusted to a higher level, due to the improvementin the result of €11.9 million and also increased by€8.3 million, due to reincorporation of the allocation

I R S N 2005 ANNUAL REPORT[7

[FINANCIAL LEDGER
OF THE 2005 ANNUAL REPORT]

4. BALANCE SHEET ANALYSIS
4.1. Liabilities

4.2. Assets

F/year(in € million)

2003

2004

2005

Variation
2005/2004

F/year(in € million)

2003

2004

2005

Variation
2005/2004

Net assets

40.6

34.6

55.0

+58.9%

Capital assets

47.9

50.1

62.5

+24.8%

Advances & deposits

7.8

9.8

0.1

-99.0%

Investment
grants

18.9

12.3

8.5

-30.9%

S/T Shareholders’equity

59.5

46.9

63.5

+35.4%

Provisions

8.4

12.4

20.3

+63.7%

S/T Invested
capital

67.9

59.3

83.8

+41.3%

Financial debts

0.1

-

7.3

NB

Advances & deposits

2.4

2.4

2.5

+4.2%

Capital assets have appreciably increased (bySupplier debts

84.4

40.6

40.7

+0.2%

Tax and social
debts

24.8%) with a net value of €62.5 million, as against

11.4

16.7

20.5

+22.8%€ 50.1 million the previous year. After several

Other debts

41.8

2.9

1.7

-41.4%

financial years where this item remained stable andShort- andmedium-term
S/T debts

140.1

62.6

72.7

+16.1%

Total

208.0

121.9

156.5

+28.4%

Operatingreceivables

108.3

48.5

26.7

-44.9%

Treasury

44.1

13.5

67.2

+397.8%

Total

208.1

121.9

156.5

+28.4%

4.2.1.

represented the ageing of the IRSN installations, thetendency is reversed and should continue in 2006.

4.2.2.
4.1.1.

Current assets have increased to €94.1 million, as

Taking account of a profit of €20.4 million, long-term

against €71.8 million in 2004. They breaks down

capital comprises:

into:

net assets of €55 million;€26.7 million of operating receivables;€8.5 million of investment grants;€67.2 million of treasury.

€20.3 million of provisions;i.e. a total of €83.8 million, as against €59.3 million
in 2004 and €67.9 million in 2003.

The strong growth in treasury noted at the close of
the financial year 2005 corresponds to:
the delay (see above) in the investment plan(€12.2 million);

4.1.2.
Short- and medium-term debts amount to€ 72.7 million, as against € 62.6 million for thethe strong reduction in operating receivablesprevious year. This increase is explained primarily(- €21.6 million).

by the taking out of a loan for €7.2 million, intended

The financial year 2005 finishes with working

to finance the purchase of a building, and by thecapital increasing by €19.5 million, within which

adjustment (in the sum of €3.6 million) of the social€12.2 million of investments carried forward will

liabilities in respect of holiday pay. These short- andbe taken up in amending decision no. 1 of the 2006

medium-term debts break down as follows:

financial year.

€7.3 million of financial debts;€2.4 million of advances on pending orders;€40.8 million of supplier debts;€20.5 million of tax or social liabilities;€1.7 million of sundry debts.

8]

the provisions allowed for in the financial year(€8.3 million);I R S N 2005 ANNUAL REPORTCONCLUSION
The 2005 budget was carried out in accordance

respect of 2006. The IRSN has requested thewith the budgetary commitments undertaken by

perpetuation of this measure as from 2007, to enable

the Board of Directors.

it in particular to cope with this future expenditure.
The disappearance of the Institute’s budget deficit,

The accounts do not take into consideration thein consequence of the revision of its tax system,

future expenditure on dismantling, the procedures

enables it to present a healthier financial situationin respect of which were not completely clarified atin respect of its current operations.

31 December 2005.

With the effective subjection of the IRSN to theThis provisioning, estimated at €31 million, has been

payroll tax as from 2006, this improvement may only

incorporated in amending decision no. 1 of 2006,

be maintained, insofar as the tax system adopted

thanks to the direct allocation to the IRSN of afor VAT is extended to corporation tax and businessportion of the income from the tax on the BNIs intax.

I R S N 2005 ANNUAL REPORT[9

Profit & Loss account
INCOMEIn euros excluding tax

2005

2004

2003

278,533,129.53

245,598,908.63

235,482,280.96

36,082,032.27

35,164,526.17

35,590,211.96

240,153,038.38

206,681,399.76

198,098,871.94

Write-backs on depreciation and provisions

522,051.53

80,417.64

20,504.32

Transfers of charges

54,410.88

36,839.37

25,349.47

Other income

1,721,596.47

3,635,725.69

1,747,343.27

Financial income

1,190,690.45

1,446,579.93

1,018,763.58

Operating income
Net total turnover
Operating subsidies(1)

From holdings

104,780.21

Other interest and equivalent income

19,690.46

8,710.77

Positive exchange differences

4,800.05

19,953.00

38,568.13

Net income on sale of negotiable investment securities

1,061,419.73

1,417,916.16

980,195.45

Extraordinary income

4,146,552.62

6,721,564.71

25,211,622.50

6,554,482.13

18,742,326.22

Income from asset transfers

20,516.72

Investment subsidies transferred to the year’s Profit & Loss Account3,791,414.60

Non-staggered investment grants

265,856.15

Management operations

68,765.15

167,082.58

6,469,296.28

283,870,372.60

253,767,053.27

261,712,667.04

TOTAL INCOME
Debit balance = loss

6,045,350.60

OVERALL TOTAL

283,870,372.60

259,812,403.87

261,712,667.04(1) As from 1 January 2005, the operating grants paid by the Ministry for Ecology and Sustainable Development (MEDD) and the Ministry of Defence (MINDEF) are exempt from VAT.

Operating income (in € million)
236,8

Detailed income (in € million)
278,5

MEDD subsidy

201,9
2,9

245,6
1,2

MINDEF subsidy

2,7
0,5

4,2

2005
Miscellaneous

3,8

2005

10 ]

10

100

Own resources

2,2

10

Extraordinary income

6,7
0

36,1
35,3

0

Financial income

1,4

Other subsidies

2

100

1000

2004

I R S N 2005 ANNUAL REPORT

Operating income

2004

1000

[

FINANCIAL LEDGER
OF THE 2005 ANNUAL REPORTEXPENDITURE
In euros excluding tax
Operating expenditure
Third-party consumption for financial year

(1)

2005

2004

2003

262,953,012.10

245,997,066.23

261,015,076.71

132,158,168.96

158,454,902.47

182,831,266.23

Tax, rates and equivalent payments

3,302,586.05

2,776,145.74

1,381,124.89(2)

103,617,061.44

65,805,418.98

45,440,248.53

Depreciation and provision allowances

21,734,857.59

17,771,491.98

28,404,363.46

Other charges

2,140,338.06

1,189,107.06

2,958,073.60

99,153.11

33,456.39

21,155.29

Interest and equivalent charges

88,837.44

9,805.48

1,881.88

Negative exchange differences

10,315.67

13,650.91

19,199.31

10,000.00

74.10

Personnel charges

Financial expenditure
Depreciation and provision allowances

Net charges on sale of negotiable investment securities
Extraordinary expenditure

375,520.45

13,763,131.25

260,535.00

Management operations

292,742.13

13,763,131.25

35.00

Capital operations

82,778.32

500.00Depreciation and provision allowances

260,000.00

Tax on profit

18,750.00

18,750.00

Fixed annual taxation

18,750.00

18,750.00

TOTAL EXPENDITURES

263,446,435.66

259,812,403.87

Credit balance = profit

20,423,936.94

OVERALL TOTAL

283,870,372.60

261,296,767.00
415,900.04

259,812,403.87

261,712,667.04(1) Since 1 January 2005, VAT on purchases has become irrecoverable in proportion to the activity not subject to VAT.
(2) The personnel charges increase with the arrival of the CEA employees opting for the IRSN. This increase is compensated for by a decrease in third-party consumption.

Detailed expenditure (in € million)
262,9

0,5

2005

100

Personnel

107,7
1,2

Other charges

13,8
10

109,2

Operating expenditure

246

0Operating expenditure (in € million)

Taxes

1,3

1000

21,7

Depreciation-provisions

17,8

2004

130,8

Purchases of goods-services

119,2
0

10

2005

100

1000

2004

I R S N 2005 ANNUAL REPORT

[ 11

]

Balance sheet
ASSETSIn euros

2005

2004

2003

Gross

Depreciationand provisions

Net

Net

Net

Intangible fixed assets

8,368,894.53

6,771,569.16

1,597,325.37

1,742,147.10

1,845,335.08

Tangible fixed assets

104,762,296.29

45,204,104.93

59,558,191.36

47,190,404.05

45,435,018.48

Financial fixed assets

1,314,180.01

1,314,180.01

1,196,078.27

635,212.81

62,469,696.74

50,128,629.42

47,915,566.37

Fixed assets

114,445,370.83

51,975,674.09

Stocks and work-in-progress

34,943.08

Advances and deposits
paid on orders

140,499.71

140,499.71

9,824,069.06

7,758,726.96

24,984,581.97

29,826,904.94

28,178,006.45

1,731,507.74

18,533,312.85

79,899,947.86

26,716,089.71

48,360,217.79

108,077,954.31

1,069.28

1,069.28

Operational receivables
Client receivables

25,116,260.99

Other receivables

1,731,507.74
26,847,768.73

131,679.02

131,679.02

Sundry receivables
Negotiable investment securities

65,313,646.29

65,313,646.29

10,938,217.44

33,680,806.20

Liquid assets

1,905,219.84

1,905,219.84

2,565,411.71

10,370,525.94

72,469.00

241,517.33

Prepayments
Current assets

94,207,134.57

131,679.02

94,075,455.55

71,761,454.28

160,165,543.10

OVERALL TOTAL

208,652,505.40

52,107,353.11

156,545,152.29

121,890,083.70

208,081,109.47

Detailed assets

40

Current assets

71

60

27

2

Treasury €67.2 million (71%)
Advances €0.1 million (0%)

12 ]Capital assets €62.5 million (40%)

Client receivables €25 million (27%)

Current assets €94 million (60%)

Sundry receivables €1.7 million (2%)

I R S N 2005 ANNUAL REPORT[FINANCIAL LEDGER
OF THE 2005 ANNUAL REPORT

LIABILITIESIn euros

2005

2004

2003

Allocation

8,782,859.59

8,782,859.59

8,782,859.59

Reserves

31,844,160.61

31,844,160.61

31,428,260.57

Carried forward-6,045,350.60

Financial year result (profit or loss)

20,423,936.94-6,045,350.60

415,900.04

Net assets

55,005,606.54

34,581,669.60

40,627,020.20

Investment subsidies

8,505,605.26

12,297,019.86

18,851,501.99

Shareholders’ equity

63,511,211.80

46,878,689.46

59,478,522.19

Risk provision

1,278,000.00

1,260,000.00

260,000.00

Taxation provision

9,250,369.57

1,300,000.00

Provision for charges

9,806,000.00

9,882,369.57

8,150,000.00

Contingent liability provision

20,334,369.57

12,442,369.57

8,410,000.00

Loans & debts from credit houses

7,283,771.11

Sundry financial loans & debts

136,224.68

190.50312.42

312.42

Advances and deposits received on current orders

2,468,724.45

2,426,504.71

2,426,504.71

Supplier debts and connected accounts

31,459,617.08

33,998,794.86

79,002,887.85

Tax and social debts

20,529,969.47

16,649,279.72

11,409,966.28

Other operational debts

39,514,301.48

Debts on fixed assets and related accounts

9,306,807.42

6,583,920.72

5,386,816.45

Other debts

1,650,490.89

2,792,448.24

2,197,809.41

117,764.00

117,764.00

Prepayments and accrued income
Debts

72,699,570.92

62,569,024.67

140,192,587.28

OVERALL TOTAL

156,545,152.29

121,890,083.70

208,081,109.47

Debt analysis

28

56

16
Tax and fiscal debts €20.5 million (28%)
Supplier debts €40.7 million (56%)
Other debts €11.5 million (16%)

I R S N 2005 ANNUAL REPORT

[ 13

]

Intermediate managementbalances
HEADINGS

31/12/05%

31/12/04

31/12/03

Turnover36 082 032.27

13.06%

35,164,526.17

35,590,211.96+ Operating subsidies

240,153,038.38

86.94%

206,681,399.76

198,098,871.94

FINANCIAL YEAR PRODUCTION

276,235,070.65

100%

241,845,925.93

233,689,083.90- Third-party consumption

132,158,168.96

47.84%

158,454,902.47

182,831,266.23

ADDED VALUE

144,076,901.69

52.16%

83,391,023.46

50,857,817.67- Taxes and rates

3,302,586.05

1.20%

2,776,145.74

1,381,124.89- Personnel charges

103,617,061.44

37.51%

65,805,418.98

45,440,248.53

GROSS OPERATING SURPLUS

37,157,254.20

13.45%

14,809,458.74

4,036,444.25

576,462.41

0.21%

117,257.01

45,853.79+ Other income

1,721,596.47

0.62%

3,635,725.69

1,747,343.27- Depreciation and provision allowances

21,734,857.59

7.87%

17,771,491.98

28,404,363.46+ Write back on equipment subsidies

4,057,270.75

1.47%

6,554,482.13

18,742,326.22- Other charges

2,140,338.06

0.77%

1,189,107.06

2,958,073.60

OPERATING RESULT

19,637,388.18

7.11%

6,156,324.53-6,790,469.53+ Investment income

1,190,690.45

0.43%

1,446,579.93

1,018,763.58- Financial charges

99,153.11

0.04%

33,456.39

21,155.29

20,728,925.52

7.50%

7,569,448.07-5,792,861.24+ Extraordinary income

89,281.87

0.03%

167,082.58

6,469,296.28- Extraordinary expenditure

375,520.45

0.14%

13,763,131.25

260,535.00

EXTRAORDINARY RESULT-286,238.58-0.10%-13,596,048.67

6,208,761.28

18,750.00

0.01%

18,750.00

20,423,936.94

7.39%-6,045,350.60+ Write backs, transfers of charges

CURRENT PRE-TAX RESULT- Tax on profit
FINANCIAL YEAR RESULT14 ]I R S N 2005 ANNUAL REPORT

415,900.04

[

FINANCIAL LEDGER
OF THE 2005 ANNUAL REPORTForecast and completion
reconciliation
PROFIT & LOSS ACCOUNT in euros

2005 budget

2005 actual

Sale of services

37,865,760.00

36,082,032.27

Public subsidies

239,703,400.00

240,153,038.38

Other operating income

1,154,780.00

3,301,319.10

Internal transactions

4,893,000.00

4,333,982.85

283,616,940.00

283,870,372.60

Personnel charges

110,073,780.00

103,617,061.44

Other operating costs

151,060,960.00

138,089,268.20

Internal transactions

14,000,000.00

21,740,106.02

TOTAL CHARGES

275,134,740.00

263,446,435.66

RESULT (PROFIT)

8,482,200.00

20,423,936.94

TOTAL PROFIT & LOSS ACCOUNT BALANCE

283,616,940.00

283,870,372.60

TRANSFER OF RESULT TO SFC TABLE in euros

2005 budget

2005 actual

RESULT

8,482,200.00

20,423,936.94

INCOMETOTAL INCOME
CHARGESRESULT (LOSS)+ Accounting value of asset items sold+ Allowances for depreciation and provisions

5,248.43
14,000,000.00

21,734,857.59- Income from asset transfers

20,516.72- Share of investment subsidies transferred to profit & loss account- Write-back on depreciation and provisions

3,791,414.60
4,893,000.00

522,051.53

17,589,200.00

37,830,060.11

2005 budget

2005 actual

SELF-FINANCING CAPACITY

17,589,200.00

37,830,060.11

Acquisitions of tangible and intangible assets

27,028,360.00

25,560,548.88

780,000.00

876,486.61

SELF-FINANCING CAPACITY (SFC)

SUMMARY FINANCING TABLE in euros

Financial fixed assets
Financial debt repayment
TOTAL APPROPRIATIONS

121.9227,808,360.00

26,437,157.41

Other resources (excluding internal transactions)

8,009,160.00

8,062,672.70

TOTAL RESOURCES

8,009,160.00

8,062,672.70

CONTRIBUTIONS TO WORKING CAPITAL-2,210,000.00

19,455,575.40

Public investment subsidies

I R S N 2005 ANNUAL REPORT

[ 15

]

Telephone+ 33 (0)1 58 35 88 88
Postal address
B.P. 17 - 92262 Fontenay-aux-Roses Cedex - France
IRSN website
www.irsn.org© Mickaël Lefontan / Olivier Seignette

Head office
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92140 Clamart - France
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EDITORIAL COORDINATION
Department for Strategy, Development and External Relations
EDITORIAL COMMITTEE
Bernard ADROGUER
Jocelyne AIGUEPERSE
Françoise BRETHEAU
Nathalie CHAPTAL-GRADOZ
Stéphanie CLAVELLE
Patrick COUSINOU
Didier DEMEILLERS
Agnès DUMAS

Huguette FABRE
Dominique FRANQUARDMarie-Line de HEAULMEJean JALOUNEIX
Pascale MONTIEmmanuelle MUR
Jean-Louis ROY

AUTHORSIRSN with the assistance of Camille JAUNET (La Clé des mots) and Jean-Christophe HEDOUIN (HIME)PRODUCTION COORDINATION
Communications Division
GRAPHIC DESIGN AND COORDINATIONPRODUCTION ASSISTANCELAO Conseil, ré(craie)action, summer time

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