2002€¦ · organisation draft for the new Institute was is underway. Nevertheless, the implementation of the organisation had to be deferred in the absence of a Board of Directors;

IRSN ACTIVITY REPORT

20

02

Institut de radioprotection et de sûreté nucléaire

IRSNHead office: 77-83, avenue du Général-de-Gaulle – 92140 Clamart

Phone: +33 (1) 58 35 88 88Postal address: B.P. 17 – 92262 Fontenay-aux-Roses Cedex

Web site: www.irsn.org

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[ I R S N A C T I V I T Y R E P O R T 2 0 0 2 ]

PART I : MISSIONS AND ORGANISATION

EditorialPresentation of IRSN2002 : results of the first year of IRSNBoard of Directors and organisation chart of IRSN

PART II : ACTIVITIES

Protecting human beings and environment

. Networks for detecting and measuring radioactivity in the environment

. Consequences of the Chernobyl accident fallout in France

. A new organisation for IRSN crisis management

. IRSN involvement in environment radiation protection

. IRSN research programmes in marine radio-ecology

. Radiation protection of populations and professionals

. IRSN participation in ICRP work

. Expertise and research in neutron dosimetry

. Management of accidental exposures

. Understanding the ionizing radiation effects

Contributing to the safety of nuclear facilities and transports

. Phenix safety review

. Studying the safety of PWR fuels

. Safety review of nuclear power plants

. Research on the PWR core meltdown accidents

. Ensuring waste management safety

. Expertise used for industrial risk control

. Controlling criticality risk

. Assessing transport safety

. Reinforcing fire protection

Contents

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Ensuring non-proliferation and protection against malevolent actions

. Non-proliferation of chemical weapons

. Protection against malevolent actions

Promoting international relations

. An Internationally-oriented Institute

. Close co-operation between France and Germany

Supporting information and training

. Communication based on transparency and education

. Training

PART III : QUALITY AND DEVELOPMENT MEANS

Proceeding with quality objectives

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

IRSN 2002 budget

ANNEXES

IRSN sites

Glossary

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

Jean-François LacroniquePresident of the Board of Directors

Jacques RepussardDirector General

Editorial

MISSIONS AND ORGANISATION

Jacques RepussardDirector General

Jean-François LacroniquePresident of the Board of Directors

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The Nuclear Safety and Radioprotection Institute is apublic scientific and technical expert organisation,

specialising in the assessment of risks due to ionisingradiation, particularly in nuclear facilities and duringtransport of nuclear materials.Both main missions of IRSN are complementary: researchenhances knowledge and expertise provides technicaladvice; research represents the basis of a qualityassessment of the most complex issues.More specifically, the main areas of activity of theInstitute cover the safety of nuclear facilities andtransport of nuclear and fissile matter, the protection ofhuman health and the environment against ionisingradiation, protection and control of nuclear matter,protection against malevolent actions and crisismanagement.IRSN maintains partnerships with nearly 30 countries andtakes part in large-scale research programmes. It takespart in the development of international scientific and technical consensus and in the development ofinternational recommendations.

IRSN is a public establishment of an industrial andcommercial nature created by the law of May 9th, 2001.Its missions and operations are defined in a decree ofFebruary 22nd, 2002.

The creation of IRSN is part of the reform regarding thecontrol of nuclear safety and radiation protection inFrance, which follows the general pattern of the creationof health security agencies and clarifies the roles of thedifferent actors by separating the implementation andthe promotion of nuclear power programmes, controlauthority functions and technical assessment functions.

Technical assessment functions are entrusted to IRSN,control authority functions for facilities and civiltransport being ensured by the General Management ofthe nuclear safety and radiation protection under theauspices of the Ministries of Industry, Environment andHealth. IRSN is in charge of technical activities previouslycarried out by IPSN (Institute for Nuclear Protection andSafety) and OPRI (Office for Protection against IonisingRadiation). It is placed under the joint guardianship of the Ministries of Environment, Industry, Research, Healthand Defence.

With a budget of about 250 million Euros, IRSN employs1,500 experts and researchers, covering various disciplinesfrom life sciences to physics of nuclear reactors.In 2002, IRSN had a provisional organisation, with themembers of the Board of Directors being appointed at the beginning of 2003, as were the President of the Boardand the Director General.

Presentation of IRSN

> Preventing nuclear and radiobiological risks


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Daniel QuéniartDirector Advisor

From the end of February 2002 to the appointment of the Director General in March 2003, I ensured the functions of theIRSN provisional administrator, born of the meeting of the technical teams of IPSN — now separated from CEA — and OPRI.

During this transition period, it was essential to carry on ensuring correctly all the research and expertise technicalmissions, previously conducted by IPSN and OPRI, and especially the technical support of the various administrationsconcerned. The 2002 activity report seems to testify that a good technical vitality brought by the new Institute, ismaintained.

Building its operation by joining teams from two organisations with different modes of thought and management, thusensuring for the former OPRI and the former permanent secretary of the Inter-ministerial commission for artificial radio-elements (CIREA), a clear separation between expertise functions and authority functions (now assumed by the DGSNR),managing relations with CEA with a very large part of the personnel made available by the CEA and which can adopt for three years their maintenance in the CEA staff, represented new and formidable challenges, even if the long lead timeof IRSN had allowed deep-rooted preparatory work conducted by the IPSN and OPRI directors.

After one year of existence, IRSN has a large part of the units and texts required for its operation:– The members of the Board of Directors, except for personnel representatives, have been appointed, by decree dated

January 3rd, 2003; the Chairman of the Board was appointed by decree dated January 21st, 2003;

– Upon the suggestion of the latter, the Director General was appointed by decree dated March 17th, 2003;

– The work committee held its first meeting on February 25th, 2003 and the negotiations concerning the company agree-ment have progressed (agreement signed by the Director General and four labour organisations on May 26th, 2003);

– With the exception of the convention related to the use by IRSN of the CABRI and PHEBUS reactors, whoseimplementation was difficult and which was signed on June 20th, 2003, the texts governing the daily relations betweenCEA and IRSN regarding safety, personnel, premises and technical support were, with a single exception, signedbetween September 2002 and February 2003; the convention regarding the transfer of means, rights and obligationshas not been yet finalised, but is now well in progress.

– A decision from the Prime Minister’s office established at 58 the number of ex-OPRI and ex-permanent secretary ofCIREA positions deployed to authority missions previously exercised by these units; for obvious reasons concerningpersonnel management, this decision can only be implemented gradually, as the effective personnel movementsdepend on voluntary agreements;

– The income tax system of IRSN was set by the fiscal legislation branch in August 2002 and January 2003.

However, the scientific committee remains to be created and the orientation committee related to defence-relatedactivities has not yet met.

Above all, the pooling of cultures and the synergy of the teams remain to be improved. First steps were made in thisdirection. Common values — competence, independence, transparency, responsiveness, creativity — were defined and anorganisation draft for the new Institute was is underway. Nevertheless, the implementation of the organisation had to be deferred in the absence of a Board of Directors; the related work have since resumed by the new management teamto give IRSN and its personnel renewed confidence after years of uncertainty.

2002: results of the first year of IRSN

Daniel QuéniartDirector Advisor

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ChairmanJean-François LACRONIQUEPresident of the Board of Directors

State representativesEmmanuel DUVALArmament inspection manager, representing theMinister of Defence

Marie-Claude DUPUISDirector of the industrial environment depart-ment, Department for the Prevention ofPollution and Hazards, representing the Ministerof the Environnement

Thierry MICHELONDeputy Director of environment risk manage-ment, General Directorate for Health (DGS),representing the Minister for Health

Stéphane GRITBranch manager of nuclear industry, GeneralDirectorate for Energy and Raw Materials(DGMF), representing the Minister for Industry

Bernard FROISDirector of the “Power, transport, environment,natural resources department”, TechnologyDepartment, representing the Minister forResearch

Philippe SIMÉON-DREVONManager of the national mission supportingnuclear risk management, representing theMinister for Civil Security

Jean-Denis COMBREXELLEDirector of the Labour Relations, representingthe Minister for Employment

Nicolas VANNIEUWENHUYZEOffice manager, Budget Department, represen-ting the Minister for the Budget

André-Claude LACOSTEDirector of Nuclear Safety and RadiationProtection

René PELLATDelegate for nuclear safety and radiation pro-tection for activities and installations concer-ned by national defence provision

Qualified personalitiesJean RANNOUAir Force general

Jacques VERNIERDouai Mayor

Maurice LAURENTFormer Department Manager of the NationalAssembly

Dominique GOUTTEDirector of the major heavy ion accelerator

Claude BIRRAUXMember of Parliament

Personnel RepresentativesThe election of the personnel representativeswill be held on September 9th, 2003.

Government commissionerPhilippe VESSERONDirector for the Prevention of Pollution andHazards

State controllerDaniel RACINET

Board of Directors of IRSN

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


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IRSN management

Director General: Jacques REPUSSARD ● General Deputy Director: Michel BRIÈRE ●

Director Advisor: Daniel QUÉNIART ● Assistant Director for Protection: Annie SUGIER ●

Assistant Director for Waste Safety: Michèle VIALA ● Assistant Director to the Director inCharge of Programmes: Catherine LECOMTE ● Assistant Director to the Director in Chargeof International Relations: Jean-Bernard CHÉRIÉ ● Secretary General: Jean-BaptistePINTON ● Deputy Director in Charge of Human Resources and Administrative Affairs:Louis CROUX ● Assistant Director for Communication: Marie-Pierre BIGOT ● Head ofQuality, Safety, Security and Environment Division: Alain BARDOT ● Advisor for RadiationProtection: Philippe HUBERT ● Official representative for crisis organisation: BrunoDUFER ● Internal auditor: Jean-Claude SAEY.

Director of Vésinet site: Philippe JAMET ● Deputy Director: Jean-Luc PASQUIER ●

Director of the Safety Assessment Department: Jean-Christophe NIEL ● Director of theDepartment for the Prevention and Study of Accidents: Michel POURPRIX, interim ●

Director of the Department for Human Health Protection and Dosimetry: PatrickGOURMELON ● Director of the Department for the Protection of the Environment: Jean-Claude BARESCUT ● Director of the Security Research Department: Joseph LEWI ●

Director of the Department for the Security of Radioactive Materials: Denis FLORY.

Delegate Treasurer

Jean-Claude DALE

Organisation chart on July 10th, 2003

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Contributing to the protection of the environ-ment and human health, being able to answerprecisely the authorities and public inquiries on

the impacts of ionising radiation sources on theenvironment and health, are the main objectives ofIRSN. To meet efficiently those objectives, the Instituteperforms measurements and conducts studies and alsodevelops research programmes to improve the state ofknowledge.

The areas covered are very wide. Concerning theenvironment, the objective is to measure and study the consequences of human activities on natural envi-ronments: measurement and observation networks,radio-ecology works in terrestrial and marine environ-ments, study on radionuclide bio-accumulation in theenvironment, research on “natural” radioactivity…

Concerning human health, radiation protectioninvolves populations in general, but also workers andpatients more specifically exposed to ionisingradiation. The objective is to assess the exposure ofdifferent populations in various conditions, as forexample, by chronic incorporation of radionuclidesand the resulting risks, but also to deepen the know-ledge of the physical and biological effects induced byirradiation in ordrer to develop appropriate therapeu-tic responses. In case of accident or incident, theInstitute uses its competencies to assess it and makessuggestions regarding the measures to be taken inorder to minimize its consequences. A crisis centre ispermanently on duty to respond to such situations.


IRSNProtecting human beings and environment

The most recent OPERA1 station wasimplemented in Arles in March 2002.

260,000The SISERI databaseimplemented by IRSN lists260,000 workers exposed toionising radiation.

1.9 million1.9 million of dosimetersoperated by IRSN in 2002.

32,000For the monitoring of workershandling radio-elements orexposed to such radio-elements,IRSN performed 32,000 radio-toxicological analyses onbiological samples in 2002.

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ACTIVITIES [ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]

IRSN ensures nationwide permanent monitoring ofambient radioactivity levels in various environ-

ments (air, water, soil, food…) which people may bein contact with. Merging IPSN (Institute forProtection and Nuclear Safety) and OPRI (IonisingRadiation Protection Agency) into a single organisa-tion allows IRSN to have a complete and consistentset of measurement networks. Those networks coveralerts (detection of an incident or an accident, loca-tion of anomalies), the monitoring of industrialinstallations and the understanding of transfers tothe environment (phenomena modelling). This moni-toring contributes to the appraisal of the dosesreceived by populations and to the assessment of theimpact of human, industrial or medical activities onthe environment.

Today, IRSN is based on three complementary networks:

– Fully automated alert stations (Téléray, Hydrotéléray,Téléhydro and Sara) providing a real-time alert in case ofabnormal increase of radioactivity or ambient radiation;

– 300 sampling stations, located in the environment,generally near nuclear sites and around former miningor industrial sites. This network measures natural andartificial radioactivity in the air, atmospheric dust, waterand soils. Foodstuffs and drinking water are monitoredas well as are fauna and flora. The network contributesto check that operators observe their requirementsregarding radioactive effluent releases;

– Observatories: This network, which includes 34 stations,is called OPERA1 ; it is used to measure radioactivity, up to the level of traces, in samples collected in theenvironment. The purpose is to understand the proces-ses controlling distribution, in time and space, of theradionuclides of natural and artificial origin comingfrom various environments, including the food chain. The knowledge of radioactivity levels is necessary formodelling the transfer processes of radionuclides in theenvironment. This network is also used to developmeasurement databases essential for the scientificstudies on the variability of the observed radioactivitylevels.

Today, all networks cover the entire territory of France.Every year, more than 36,000 samples are taken from thevarious compartments of the environment, includingagricultural foodstuffs. They are subject to more than100,000 laboratory analyses, focusing on the differentalpha, beta and gamma emitters. Moreover, there arethousands of results permanently produced by conti-nuous measurement systems (alert stations) of radioacti-vity in the air, atmospheric aerosols and water from themain rivers.

> Networks for detecting and measuringradioactivity in the environment


ALERT STATIONS

Téléray: National network measuring continuouslymonitors ambient gamma radiation. In 2002, a newradiation probe was installed in the Château deVincennes, in the Paris region, bringing the number ofstations to 180. Technical improvements in electronics(modem, transmission speed…) will allow to acomplete modernisation of the network as of 2003. A direct link was installed at the beginning of 2002between technical the crisis centre of IRSN inFontenay-aux-Roses (Hauts-de-Seine) and the controlcentre for intervention resources located in Le Vésinet(Yvelines).

Téléhydro: Network continuously monitoring theradioactivity of wastewater in big cities. The instal-lation in 2002 of 4 new radiation probes in Lyon(Rhône), Rouen (Seine-Maritime), Strasbourg (Bas-Rhin) and Nantes (Loire-Atlantique) brings the numberof operational stations to 8.Moreover, an autonomous and remote access mobiledevice, used for punctual measurements, was producedand has been available since the end of 2002.

Hydrotéléray: Network continuously measuringradioactivity of water from big rivers. This networknow comprises 6 stations, including the Agen (Lot-et-Garonne) radiation probe installed on the Garonneriver under the Layrac bridge.

Sara: Network measuring the alpha, beta and gammaactivities of aerosols. In 2002, 5 new radiation probeswere installed in Biarritz (Pyrénées-Atlantiques),Montélimar (Drôme), Strasbourg (Bas-Rhin), Lille (Nord)and Brest (Finistère), bringing the number of equipmentimplemented in the airport meteorological stations to 11.

1. OPERA : Observatoire PErmanent de la RAdioactivité.

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ACTIVITIES

T he Chernobyl (Ukraine) accident fallout is stillsubject to studies and working groups on the

assessment of the catastrophe’s impact on the envi-ronment and health, and on the lessons to be drawnfor crisis management. The Institute has, for a longtime, implemented an organisation, reinforced sincethe creation of IRSN, intended to bring technicalsupport to the authorities in case of nuclear accident.

Research to reinforce expertiseTo improve its expertise capacities in the radioecologicalarea, IRSN develops scientific programmes. The purposeof the CAROL (CAmargue RhÔne Languedoc) programmewas thus to determine the origin of the radionuclidespresent in measurable quantities in the lower Rhônevalley and to foresee their medium and long-termdevelopment. This project covered all environments:atmospheric, terrestrial, aquatic, continental and marine,and was used to respond to many inquiries. As an example,the study of the origin of the 137Cs present in soil wasused to quantify the relation between the deposits resultingfrom the Chernobyl accident and the rains of the firstweek in May 1986, period during which contaminated airmasses passed over France; it led to modelling a map of137Cs deposits in France due to the accident. This map canbe superimposed to the map displaying the fallout of theatmospheric tests of nuclear weapons, reproduced frommeasures performed by OPRI since 1961. It is thereforepossible to provide data on the level and origin of thecurrent 137Cs activities in French soil.

Another application of IRSN research involves the studyof the Chernobyl accident fallout in Corsica. Upon therequest of the public authorities, three sampling andmeasurement campaigns were performed in Corsica byOPRI and IPSN in 2001. Their purpose was to check theassessments of deposits, reproduce as far as possible foodchain contamination in 1986 using the measurementsperformed at this time, and determine current foodcontamination levels. The thyroid doses likely to havebeen received by children having lived in the most conta-minated areas were assessed. The study was the subjectof publications and a public introduction in Ajaccio(Corsica) in January 2002.

Lastly, within the framework of a “workshop area” ofabout 1,000 m2 located in the Mercantour region (South-East mountain range), a study focused on theorigin and localisation of radioactivity concentrationpoints in high altitudes and on food chain contamination

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

> Consequences of the Chernobyl accident fallout in France

STUDY GROUPS

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

Soil sampling in Corsica to measure the quantity of Cesium-137 currently present.


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In case of a nuclear or radiological accident, IRSNdeploys an organisation and resources to advise

public authorities. It is in particular able to rapidlyprovide information to nuclear safety authorities(DGSNR, DSND) including technical informationabout the nature and severity of an accidentalsituation affecting a nuclear facility as well as itspossible development and the consequenceswhich might result for the population and theenvironment. In addition, it suggests appropriateprotective actions to be implemented in the field.In case of effective release of radioelements, theInstitute collects and processes all measurementresults of performed to distinguish the contami-nated area and suggests appropriate measures torestore the environment.

An appropriate organisation for the situationTo respond efficiently to its missions, the Institute has anorganisation enabling it to provide a diagnosis of thesituation and a forecast on its development:

– An on-call team, comprising 14 agents, able to react inless than one hour on a 24/7 basis;

– A technical crisis centre (CTC) in Fontenay-aux-Roses(Hauts-de-Seine), available on a 24/7 basis. In case ofcrisis, it can gather a team of 20 to 25 persons,equipped with specific means: telecommunications,documentation, computer systems and databases,including mappings. This team transmits technicaladvice and information to public authorities in order toensure the protection of the population;

– A mobile unit responsible for locally coordinating mea-surements, transmitting these to the CTC for all thenecessary technical elements needed to carry out its

expertise and performancesand, if necessary, health controlof the populations. It has mobilemeasuring equipment, emer-gency vehicles and specialisedvehicles that can be useddepending on the severity of theevent (seven lorries, two trailertrucks and one rail vehicle). This

is deployed by the control centre of the interventionresources in Le Vésinet (Yvelines), in permanent contactwith the CTC.

Merging IPSN and OPRI technical activities allows IRSN tonow dispose of a wide range of technical resources. In2002, coordination of those various means was implemen-ted, allowing their complementarities to be used to impro-ve the Institute’s expertise in case of crisis: joining on-callteams, centralising information towards the CTC ofFontenay-aux-Roses (Hauts-de-Seine), implementing themobile unit… This synergy results in more direct and rapidexchange between the CTC expert team and the mobileunit in the field. Twelve crisis exercises were performed in2002: eight concerned EDF installations, one concerned theLa Hague (Cotentin) plant, one concerned Laue-Langevin(Grenoble in Isère) institute, one concerned CEA installa-tions in Cadarache (Bouches-du-Rhône) and one concer-ned a transport of nuclear materials. In addition to IRSNstaff, each of those exercises mobilizes public authorities as well as operators locally and nationally. Those exercisesare used in particular to assess the exchange between the various actors. Furthermore, computer tools developedby IRSN to assess the possible development of an accidentand the possible consequences on the environment and onthe populations of a release of radioactive materials aretested under these circumstances.

A CD-ROM ON NUCLEAR RISK FORLOCAL DECISION-MAKERS

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

The crisis technicalcentre in operation.

> A new organisation for IRSN crisis management

250IRSN experts areavailable to bemobilised at thetechnical crisiscentre.

[ PROTECTION OF HUMAN BEINGS AND THE ENVIRONMENT ]


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ACTIVITIES

> IRSN involvement in environment radiation protection

With the increase in environmental concerns, aninternational consensus was established on the

need to implement, beyond the protection of humanbeings, a system intended to protect the environmentagainst the ionising radiation effects. The assessmentof the risk associated with the presence of radionuclidesin the environment implies the development of newresearch orientations in radioecology (study of thechronic accumulation of low-dose radionuclides, consi-deration of the multipollution phenomena (metals andradionuclides)… Within this framework, IRSN launchedtwo new research programmes to acquire knowledgeand develop indispensable tools for the implementa-tion of a method to assess radioecological risks.

The ENVIRHOM programmeStarted in 2001, the purpose of the ENVIRHOMprogramme is to assess the effects of chronic exposuresto very low levels by associating experts specialising inthe protection of human beings and the environment.The attempt is to study radionuclide accumulationphenomena in ecosystems and people in a multipollutionenvironment. The knowledge bases obtained willsignificantly contribute to the implementation of asystem intended to protect the environment.

Another purpose of the ENVIRHOM programme is toassess the radionuclide transport from radioactivity tankcompartments that are water, soil and sediments,towards the living environment. Furthermore, withinecosystems, the wide diversity of those transports isassociated to the complexity of the chemical andbiological recycling mechanisms of the radionuclides and to the food patterns of the organisms present inthose environments. The programme in particular studiesthe biological changes produced in the long term.ENVIRHOM will be used to develop dose-effect relationsbetween concentrations of chemical species present inthe environment and the ecological consequencesaffecting individuals and the population (chemical andradiological toxicities).

The first experiences focussed on uranium andhighlighted and quantified uranium bioaccumulationprocesses as well as the mechanisms implementedaccording to the environment and uranium chemicalforms, for phytoplankton and invertebrates.

Other studies highlighted bioaccumulation processes andcapacities of transfer to consumers. Lastly, somebiological effects (death rate, impact on growth…) couldbe associated with the exposure modalities and thereforewere used to draw dose-effect relation curves.

The SYMBIOSE programme: towards an integrated assessment-support platformStarted in 2002, the purpose of the SYMBIOSEprogramme is to develop a set of coordinated computertools intended to support the assessment andmanagement of the risk of radioactive contamination inthe environment. The objective is to process the impacton both human beings and the environment from thescale of an individual to the scale of a whole population.

Depending on the situations studied, the programme canuse more or less complex and detailed models. Thus, inpreliminary forecast studies, some phenomena can betreated using simplified descriptions whereas theinterpretation of delicate real cases may require moresophisticated models. The aim of the approach used is toprocess a wide range of situations. It should allow thedynamic modelling of radionuclide transport within andbetween the different environments forming thecontinental biosphere on time scales ranging from oneday to several dozens of years. This approach will beapplied to the waste storage, basic nuclear installations(BNI) in normal or accidental operations.

The work in 2002 focussed on restructuring existingmodels and integrating them into a modular set used to assess the dosimetric impact on human beings, linkedto an ingestion of contaminated food from a simplifiedcontinental biosphere.


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

A STRONG INVOLVEMENT IN INTERNATIONAL PARTNERSHIP NETWORKS

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

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

The sources of uncertainty aretaken into account for each step.

Characterisationof the releases.

Quantification of the impacton health or ecological risk.

Analysis of target population exposures to substances.

BREAKDOWN OF THE ASSESSMENT AND RISK MANAGEMENT CYCLE

Identification of actions to achievean acceptable detriment level.Uncertainty 4

Actions

3Risk

2Exposure

1Source

The uranium bioaccumulation is studied in bivalves and crayfish.



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ACTIVITIES

IRSN expertise regarding the assessment of theimpact of radioelements present in the environ-

ment, on human beings and ecosystems, implies inparticular the understanding and quantification ofthe transfer mechanisms of the natural and artificialradioactive substances in the marine environment.For more than twenty years, the Institute has beenconducting marine radioecology studies, bringingtogether specialists in chemistry, biology, geoche-mistry, sedimentology… Relations were establishedwith French and foreign research and expertiseorganisations (participation in working groups,signature of collaboration agreements.

62 days of campaign at sea in 2002The data obtained during sampling campaigns in sea andin the estuaries are used to design and validate transfermodels. The purpose of those models is to assess the dispersion in the marine environment — seawater,sediment, biota — of the radioactive substances ofnatural or artificial origin.

These campaigns use IFREMER and CNRS/INSU (InstitutNational des Sciences de l’Univers) resources. IRSN’saccess to oceanographic ships and their equipmentdepends on the assessment conducted by an appropriatescientific committee for both institutes in researchprojects involved. The requests submitted in 2001 by IRSNled to the scheduling of six campaigns in 2002, for aduration of 62 days at sea.

These campaigns contributed to:

– Understanding and quantifying transfer mechanismsbetween the sea, the atmosphere, 14C and tritium soil(TRANSAT1 campaign);

– Developing a model of dispersion at sea for contami-nants, in the near field of an emission source (DISPRO2

campaign) ;– Understanding and quantifying the fixation and

remobilisation mechanisms of radioelements insediments (DIAPLU3 campaign) ;

– Studying the distribution of natural and artificialradioelements contributed by the Rhône River to theMediterranean (REMORA4 campaign).

Improve the knowledge concerning transfersbetween the sea, the atmosphere and the soilThe work of the Nord-Cotentin Radioecology Group (GRNC)showed how important it was to deepen knowledge inthe area of transfers between the sea, the atmosphereand the soil. This led IRSN to conduct research on theunderstanding and quantification of transfers betweenthose three compartments. The purpose of both TRANSATcampaigns carried out in February and August 2002 wasto quantify the transports of 14C and tritium in gaseousform between the water, the earth and the atmosphere,in the ecosystems of the central Manche and the Seineriver estuary. Moreover, the results obtained on 14C duringthese campaigns will contribute to the more generalstudy of the CO2 cycle within the framework of the workon climate change. The equipment and specifictechniques developed during these campaigns are usedto measure very low levels of 14C and tritium in the air.

These campaigns were conducted in collaboration withthe Laboratory of Science of Climate and theEnvironment (LSCE, CEA/CNRS mixed unit) and the Groupof atomic studies (GEA) of the National Navy.

Towards the modelling of contaminantdispersion in the English Channel.The purpose of both DISPRO campaigns carried out inNovember 2002 was to determine the short and medium-term dispersion parameters of soluble releases in the seathrough tides using the tritium controlled releases of theLa Hague power plant in the North-West of the Cotentinregion. They will allow the dispersion variations to bebetter assessed, depending on hydrodynamic conditions(release time, tidal currents, meteorological forcing). The results obtained on the tritium used as a tracer willbe used to validate a high-resolution two-dimensionaldispersion model (110 metres), developed in collaborationwith IFREMER. 4,000 seawater samples have beencollected, as well as data on sea currents and depths. The first results show that tritium concentrationsmeasured in seawater correspond to those provided bythe model.

> IRSN research programmes in marine radio-ecology

1. TRANSAT : TRANSfert eau ATmosphère.2. DISPRO : DISpersion en champ PROche.3. DIAPLU : comportement du PLUtonium dans la DIAgenèse

des sédiments marins.4. REMORA : REMObilisation des RAdionucléides

dans le pro-delta du Rhône.

DIAPLU mission: the Flucha core sampler takes samplings for analyzing sediment.


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

In fact, sediments constitute a deferred and non-pointplutonium source that will be taken into account toassess the plutonium part linked to a release and theplutonium part coming from the remobilization of pluto-nium contained in sediments. Plutonium concentrationsfound in Irish Sea sediments marked by releases from theSellafield reprocessing plant enable the plutoniumdissolved in interstitial waters of sediments to bemeasured. Sampling of sediment cores and extraction ofinterstitial waters were performed in conditions keepingthe physical and chemical characteristics of the studiedenvironments.

The analyses of the 230 samples were used to determinetheir sedimentological and geochemical characteristics aswell as the characteristics of the interstitial waters (pHvalue, redox potential…). The association modes of pluto-nium with the solid and reactive phases of sedimentswere determined and the concentration of plutoniumdissolved in interstitial waters was assessed.

This campaign was performed within the framework ofthe REMOTRANS programme of the European commis-sion, with the collaboration of the CEFAS (The Centre forEnvironment Fisheries and Aquaculture Science, UK) and the University College of Dublin (Department ofExperimental Physics, Ireland).

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

The REMORA 3 campaign, conducted from October 12th

to November 5th, 2002, completes the campaigns perfor-med in 2001 in the area under direct influence of theRhône River inputs (European REMOTRANS programme).Almost 2,400 sediment samples were collected during the three REMORA campaigns.

The REMORA 3 campaign was carried out within theframework of the EUROSTRATAFORM (EUROpean marginSTRATA FORMation), ORME (Environment RegionalMediterranean Observatory, CNRS) and PNEC (NationalCoastal Environment Programme) programmes.

Extraction of interstitialwater of sediments sampled in sea.

REMORA mission: localization map

of samples.



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ACTIVITIES

IRSN is the main French technical organisationaiming at informing citizens, increasing professionals’

awareness and advising public authorities on ionisingradiation-related risks. Its experience in the area ofworkers’ radiation protection allows it to provide tech-nical advice on draft regulations and take part in thework of various national or international organisations.

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

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

> Radiation protection of populations and professionals

SISERI

To record, check and report the doses received by wor-kers exposed to ionising radiation are the main objec-tives of the SISERI database. Developed by theInstitute since 2000, it is intended for use by variousradiation protection actors (occupational health phy-sicians, “certified” persons in companies…). Ultimately,current developments will allow remote access todata, via a secure Internet network.

Medecine 110,000

Nuclear industry 84,000

Miscellaneous5,000

Research personnel 7,500

Classical industry 24,000

Veterinarians4,000

Dentists 25,000

Distribution of the 260,000 workers subject to a monitoring of their exposureto ionising radiation.


IRSN ensures the dosimetricmonitoring of workers exposedto ionising radiation.

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Patients’ radiation protectionIRSN takes part in the development of future regulationrelated to the protection of patients, based upon thereduction of exposures at an optimal level, while ensuringthe quality of the diagnostic images and the achievementof the therapeutic objectives. Its expertise focuses on thejustification of actions, protection optimisation, equip-ment quality control, medical screening campaigns andtraining of professionals. Within this framework, theInstitute took part in the preparation of a report on the procedures and reference doses of radiological exa-minations. This system of reference aims at reducing thedosimetric differences noted for the same examination.

Furthermore, in radiotherapy, IRSN conducts research onbiological indicators which will enable the assessment ofthe radiosensitivity of each patient in order to adjusttherapeutic protocols. Studies on mechanisms of induc-tion of side effects have also been conducted in order tosuggest appropriate treatments.

Exposure to cosmic radiation

To implement the 96/29 directive, the SIEVERT systemwas developed by IRSN, and its partners, the GeneralDirectorate of Civil Aviation (DGAC), the Meudon (Hauts-de-Seine) Observatory and airline companies, to providenecessary information about cosmic radiation exposurein planes and assess radiation doses received during a

flight. SIEVERT has been opened to French airlines since August 2001 for the regulatory dosimetry of theirstaff. To date, more than twenty airlines have used thissystem and the doses have been calculated for almost 1 million flights. This service was also opened to thepublic in March 2002 and it is available on Internet(www.sievert-system.org).

Control of radon in homesRadon is a natural radioactive gas which is classifiedamong the carcinogenic substances for lungs. For morethan 25 years, it has been studied by IRSN which hasprovided elements to public authorities in order todevelop a prevention policy of the related risk. Thus, theInstitute produced a map of radon concentrations,published in 2000, after performing more than 12,000radon measurements in French homes, in collaborationwith departments of the Ministry of Health. To enrich thismap, complementary measurements were performed in2002 in eight departments and the analysis of thoseresults is currently in progress. Furthermore, a crossanalysis of the measurements with INSEE data (popu-lation density, types of homes, seasonal behaviour…) was carried out in 2002 and it will be used to assess theradon exposure of the French population in terms ofconcentration measurements.

IRSN brings its expertise to patients’ radiation protection.



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ACTIVITIES

The modelling work intended to distinguish radon from a mining site from radon of natural origin.By reducing the threshold of public exposure to radiationgenerated by industrial practices, French regulation basedon the 96/29 European directive posed the problem of thedistinction between radon of natural origin and radonoriginating from residue storage of uranium mines.

IRSN performed several measurements of radon and itsdaughters, mainly bismuth 214 (214Bi), as part of aresearch programme conducted in the Bessines-sur-Gartempe (Haute-Vienne) mining site and its surroundings.The bismuth/radon ratio proves to be far lower in theimmediate site surroundings than in the outlyingenvironment. This phenomenon is mainly linked toatmospheric dispersion, for which we have workingmodels which schematically predict that the bismuthmeasured in the surrounding site is representative of theradon of natural origin only. From the measurement oftotal radon, the part of radon of anthropogenic originemitted by the mining site may therefore be deduced.

In 2002, the method was improved, the physicalhypotheses and simplifications of the models used weresubjected to a critical analysis. The uncertainties relatedto these hypotheses were assessed. Nowadays, IRSN usesa method applicable to similar sites whose characteristicscorrespond to the validity area of the method.

Measurements of radon and free fraction of its daughtersPure metrology work on radon gas is intended to providereference values and ensure proper traceability of the gasduring the calibration of equipment. Within this frame-work, IRSN participated in an international intercomparison,concerning the calibration procedures, launched in 2002.Measuring equipment, called Alphaguard, circulated in 9European laboratories which performed its calibration.This exercise showed good consistency in the resultsobtained by the different laboratories.

The radon gas metrology is specifically completed withthe measurement of the free fraction of its daughters,small aerosols (about one nanometre) contributing to thehealth risk. In 2001, the Institute launched a partnershipwith the University of Catalonia (Spain) and theUniversity of Brest (Finistère) for the development oforiginal measuring equipment, intended for thecharacterisation (measurement of particle size) of radondaughters and particularly polonium 218. In 2002, thetwo organisms carried out an intercomparison of twomeasuring systems of the free fraction of radon daugh-ters. The resulting analysis is currently in progress and thefirst elements analysed show satisfactory consistency,with some points to be improved, in particular data pro-cessing algorithms.


Radon 1.3 mSv Medical exposure 1 mSv

Others (nucleartests, industries)0.1 mSv

Water and food 0.2 mSv

Cosmic radiation 0.4 mSv

Soil radiation 0.5 mSv AVERAGE EXPOSURE OF THE FRENCH POPULATIONIRSN Source

IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 20

IRSN experts participate actively in the work of theInternational Commission on Radiological Protection

(ICRP) at a crucial moment in the action of this organisa-tion, aiming to simplify and clarify the radiation protectionsystem in order to make it more comprehensible and moreefficient. The recommendations from this work willcomplete publication 60 dated 1990 which is used as areference for basic international standards of theInternational Atomic Energy Agency (IAEA) and for the European directive of 1996 on radiation protection ofworkers and the public.

The ICRP, which was created in 1928 as a nongovernmental organisation, plays a crucial role in thedevelopment and transmission of the protectionprinciples against ionising radiation. The Commissionclosely work with the International Commission onRadiological Units and Measurements (ICRU) and keepsrelations with many other international organisations,including the United Nations Scientific Committee on theEffects of Atomic Radiation (UNSCEAR).

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

> IRSN participation in ICRP work

ICRP members during themeeting held in September

2001 at La Haye.



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ACTIVITIES

With time, IRSN has developed a significant andrecognized activity of research and expertises

in the area of neutron dosimetry. Equipped withmetrology and test installations, some being uniquein the world, the Institute has a reference positionboth at national and international levels.

Research and study activitiesMeasurements and characterisation of radiation fields in work placesThe purpose of the measurements is to assess workers’exposure to neutrons, in order to improve their radiationprotection, suggesting practices and instruments moreappropriate to their irradiation conditions. IRSN hasconducted many measurement campaigns in France(nuclear industry, army, transports of nuclear materials,radiotherapy, air transports …), and in foreign countries(Spain, Germany, Belgium). Among recent operations, a measuring campaign of neutron dosimetry wasconducted in 2002 in an industrial production facility ofMOX fuels operated by COGEMA (ATPu work area).

Assessment of personal dosimeters The behaviour of the personal dosimeters varies depen-ding on the various characteristics of the neutron radia-tion field and environmental factors (temperature…).Within this scope, IRSN is involved in two Europeanprogrammes. The first programme, called EVIDOS, focuseson the assessment of various available or in-studymethods for ensuring the personal dosimetry of workers,in the real exposure conditions found in work stations ;

from October 14th to 18th, 2002,the EVIDOS programme partici-pants were gathered around theCEZANE and SIGMA facilities inorder to calibrate the equipmentused for this programme. Thesecond programme, conductedwithin the framework of EURADOS(European Radiation DosimetryGroup), aims at harmonizing thedosimetric practices in Europe;IRSN is responsible for conducting

a state of the art study of the development and use ofpersonal electronic dosimeters.

Calibration of dosimeters with reference radiation sourcesThe calibration of dosimeters is performed by the IRSNlaboratory certified by the COFRAC (French Committeefor Accreditation) and concerns photons and neutrons. As a laboratory associated with the National metrologybureau (BNM), IRSN plays the role of national referencefor neutron dosimetry. It is part of the cooperativeorganisation between the national metrology institutes,EUROMET, and is recognized at the international level by the International Bureau of Weights and Measures(BIPM). As such, IRSN organizes comparisons with otherlaboratories at the national and international levels.

Research and development of new measuringinstruments and methods. The purpose of research and development actions is toimprove the monitoring of workers’ exposure.

The research of new measuring methods is conductedwith scientific software used to simulate the experimentalconditions studied.

Models and laboratory prototypes are then made andtested on reference installations. Having neutron, but alsophoton, references is crucial for IRSN to conduct researchand perform expertise as neutron fields are alwaysassociated with photon fields in work places. In June2002, a French industrial company marketed the firstelectronic dosimeter called “Saphydose-n” for measuringneutron radiation. This has put into effect the success ofa study and a technology transfer conducted by IRSN,following previous work carried out in its laboratories. Thisdosimeter, whose first industrial prototype was validatedduring the measuring campaign conducted by IRSN in the EDF power plant of Dampierre-en-Burly (Loiret), was certified in January 2002 by the CTHIR (TechnicalCentre for the Approval of Radiological ProtectionInstrumentation).

> Expertise and research in neutron dosimetry

First EVIDOS campaign on CANEL: Saphydose-n.

10Years of research were required to develop the first electronic dosimeter for neutrons meeting the international standards requirements.


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Participation in national and international normative bodiesIRSN experts participates in national (StandardizationBureau for Nuclear Equipment (BNEN)) and internationalbodies, such as the International Organisation forStandardization (ISO) and the International ElectrotechnicalCommission (IEC) working groups. For ISO, the activity in2002 focused on the creation of a new standardconcerning the calibration in neutron radiation fields with“realistic” spectrums. The IEC committee on radiationprotection instrumentation, managed by IRSN, met inBeijing (China). One of the working groups in which IRSN participated actively examined personal and areaelectronic dosimeters.

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

Moreover, the CEZANE facility houses two electrostaticaccelerators coupled to a moderator device called CANEL.This equipment is used experimentally to produceneutron radiation whose energy distribution is said to be“realistic”, i.e. representative of the conditions observed inwork stations. They are used to assess the performancesof dosimeters and detectors in various configurations.Within the framework of a EUROMET (EuropeanMetrology) collaboration between IRSN, the German(PTB) and English (NPL) primary laboratories and theUniversity of Barcelona (Spain) (UAB), the characteristicsof the radiation field produced by a new configuration ofthe CANEL device were determined in 2002. This device,unique in the world, is also intended to become areference as an international standard project on theproduction and use of “realistic” spectrums, currentlybeing assessed by ISO.

A NEW INSTALLATION DEDICATED TOMONOENERGETIC NEUTRONS

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

Installation of neutronmeasuring equipment

on a Van-Gogh calibration system.

IRSN has unique tools in France for neutrondosimetry such as theCANEL moderator device shown here.



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ACTIVITIES

During irradiation or contamination accidents orincidents, IRSN may have to contribute its

expertise to assess doses received by irradiatedpersons and to assist medical teams in charge oftheir treatment. Concurrently, the Institute conti-nues its research to improve diagnostic indicators — especially by developing new techniques for doseassessment — and to optimise treatment of irradiatedpersons.

Complementary missionsIn case of accidents, the assessment of the dose receivedby an irradiated person is an important element to choosethe appropriate therapeutic strategy. This expertise workis based on several complementary approaches, but it isessential to collect the maximum information about thecircumstances of the accident and the exposure condi-tions of the victims. Biological dosimetry is used to assessthe average dose received by an irradiated person fromthe scoring of unstable chromosome anomalies in thecirculating blood lymphocytes, by a cytogenetic techniquerefered as conventional. Physical dosimetry is used toassess the distribution of doses in the organism fromexperimental reconstructions or by modelling of theirradiation conditions. The dose received can also beassessed with measurements by paramagnetic electronicresonance on bone fragments. In case of contamination,the incorporated activity, and therefore the dose, may beassessed, depending on the radionuclides, from theanthropogammametry or measurement performed onurine and stools.

In addition to work aiming at improving the previouslymentioned measuring and assessment techniques, themain purpose of research conducted by the Institute inthe management of the accidental exposures is to suggesttreatment appropriate to each situation encountered, bytaking into account the radiosensitivity of each individualand the heterogeneous characteristic of the irradiationaccidents.

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

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

Ladoux (Puy-de-Dôme)IRSN took part in the technical analysis of the irradiationaccident which occurred in the Michelin plant at Ladoux(Puy-de-Dôme) in June 2002, when three workersentered a bunker dedicated to an industrial electronaccelerator for a maintenance operation. The equipmentoperator accidentally activated the electron beam, whichgenerated the production of bremsstrahlung X-rays.Moreover, IRSN conducted a biological dosimetry expertisestudy which did not reveal any significant exposure of theworkers concerned.

> Management of accidental exposures

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


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International incidents GeorgiaIn December 2001, three Georgians handled strontiumelectricity generators. Suffering from severe burns and acollapse of their bloodlines, they were hospitalised inTbilisi (Georgia) three weeks later. One of them had verysevere injuries in his back.

IRSN intervened upon the request of IAEA and recom-mended the transfer of the most injured patient to France.He arrived in Paris in February 2002, 88 days after theaccident. He was taken in charge at the Army Hospital ofPercy (Hauts-de-Seine), where he underwent severaltransplants. The improvement of his health conditionpermitted him to return to Georgia in April 2003.

IRSN provided its support to hospital teams, particularlyin performing dosimetric assessments. Two biologicaldosimetry methods were used. The assessment of theaverage dose by the conventional cytogenetic techniquewas completed by the evaluation of the dose received atskin level, a technique applied for the first time in anaccident. This second dosimetry was performed by scoringthe stable translocations using the FISH (Fluorescence InSitu Hybridization) method. The dose estimates are inagreement with the clinical data. Lastly, a dose calculation,using a modelling of the source and the patient, confir-med the consistency of the various analyses.

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

Collaboration with the Saint-Antoine hospital on the research of therapeutics in haematology.In 1999, IRSN created, with the Saint-Antoine universityhospital centre (Paris-VI University), a common laboratorycalled Laboratoire de Thérapie Cellulaire et de Radio-protection Accidentelle (LTCRA). Its goal is to performexperimental research in order to improve the treatmentof bone marrow failures, due either to accidental irradia-tion or not, using cell therapy. This therapy consists inmultiplying the cells of a patient taken from his ownorganism and then re-injecting them when he or sheneeds them. This technique, applied to haematopoieticstem cells sampled after an accidental irradiation in amedullar area more or lessprotected from irradiation, hasshown very promising results in the treatment of radiation-induced aplasia. This techniqueis being applied for other celltypes, and especially formesenchymal stem cells which,after re-injection, are able toacquire the functionality of theorgan or tissue they colonize.An aplasia patient was treated with this technique in2002. This works was published in international reviews.

Mobilization of IRSN agents to treat a great number

of blood samples.

International intercomparisonof dosimetry on the Silène

reactor: positioning of bloodsamples.

20IRSN performed 20expertise studies usingbiological dosimetry for accident suspicions in 2002.



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ACTIVITIES

The work conducted on health effects of ionisingradiation is crucial to achieve the radiation

protection missions of the Institute. It will improvethe knowledge on issues where uncertainties remain.

Analytic epidemiological studiesThe purpose of these studies, concerning workers andpopulations exposed to ionising radiation, is to betterquantify the risk of developing cancer depending on thedose received. Two methods are used: prospective surveysare used to follow over time the evolution of the diseaserate within a group of exposed persons, while the case-control studies are used to establish a comparisonbetween the exposure of individuals suffering from apathology and the exposure of a “control group” notsuffering from this pathology. IRSN is currently pursuingstudies with these methods:– Monitoring of the cohort of workers from the CEA-COGEMA

group within the framework of an international studyconducted by the IARC (International Agency forResearch on Cancer);

– Monitoring of the cohort of 5,098 French uraniumminers exposed to radon, completed by a case-controlstudy within this cohort to study the joint effect ofradon and tobacco;

– Case control study on lung cancer within populationsexposed to domestic radon including 1,655 individuals(552 cases and 1,103 controls) in 4 French regions;

– Study of the health consequences of the Chernobylaccident, in particular within the framework of theFrench-German initiative, and case-control study of the risk of leukaemia within populations living incontaminated territories on the banks of the Techa

River (Urals).

Concurrently, IRSN takes part in the RIMED project(Ionising radiation in medicalenvironment): epidemio-logical monitoring of thedeath rate among health careprofessionals exposed toionising radiation in France.Started in 2002, the feasibilitystudy, coordinated by InVs,

will concern 6 hospital institutions. IRSN brings to this projectits experience in the epidemiological monitoring of an activepopulation and the management of professional anddosimetric databases.

Lastly, with the intent to develop epidemiological studieson patients exposed to ionising radiation for medicalpurposes, IRSN started a pilot study in 2002 on 100premature infants subject to repeated examinationsduring the neonatal period. The purpose of this work,conducted with the Trousseau Hospital, is to determinehow accurate the doses received by those infants may beevaluated, and to assess the relevancy and feasibility of epidemiological monitoring of the related population.

Effects of chronic radionuclide ingestionIn order to improve the assessment of the risks linked tothe chronic low level incorporation of radionuclides, IRSNlaunched the ENVIRHOM programme in 2000, focusingon both biological components of the environment andhuman beings. The “human” part of this programme isconducted along four lines:– Researching the phenomena of chronic accumulation

of the radionuclides;– Understanding of the biological mechanisms leading to

the phenomena observed;– Analysis of the biological effects on the immune system,

the digestive system, the central nervous system andthe reproduction system;

– Implementation of new biokinetic and dosimetricsoftware and models in order to assess the uncertain-ties on the doses received and better take into accountthe cellular distribution of the radionuclides.

In 2002, work was focused on the first two areas and apart of the third area, the study of the biological effectson the digestive and central nervous systems, with uraniumas radionuclide using the rat as the animal model. Thestudy of the consequences resulting from uranium chronicaccumulation on the fertility and embryonic develop-ment of rodents, as well as on the organism’s capacity torespond efficiently to situations frequently encounteredin public health (bacterial infections, alimentary antigens,etc.) will be performed in 2003.

> Understanding the ionising radiation effects

Heterogeneous distribution of uranium in a kidney proximal tubular cell.

17,500Number of analysesperformed within theframework of the ENVIRHOMresearch programme intendedto assess the risks ofradionuclide bioaccumulation.


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Effects of acute irradiationsThe work performed in this area concerns both the severeeffects caused by an accidental exposure, and the long-term deleterious effects resulting from therapeuticexposures. Historically, the studies performed by IRSNfocused on the development and operational applicationof biological dosimetry using classical cytogenetics (doseassessment from the scoring of chromosome aberrations)on the one hand, and on the other hand, the study of theradiation induced dysfunctions of the physiologicalsystems involved in the vital prognosis of the irradiatedperson: haematopoietic system, digestive system andcentral nervous system. These studies took into accountsignificant scientific advances which occurred in biologyin recent years. Today, considering these studies and thelessons drawn from the severe irradiation accidentshaving occurred around the world, IRSN research activi-ties gradually evolved towards the following topics:– Operational application of new biological dosimetry

methods to assess the dose received whatever theirradiation typology. Within this framework, dosimetricassessments were performed on skin pieces sampledduring surgery on a Georgian patient and on a Polishpatient severely irradiated, treated in the BurnTreatment Centre (Percy Hospital) and in the CurieInstitute. The results have proven to be particularlypromising for characterizing the extent of injuries incase of localised irradiation;

– Physiopathology of the effects caused by an accidentalirradiation or by the irradiation of healthy tissuesduring medical examinations or treatments. The purposeis to identify biological indicators of diagnosis andprognosis of the radiation induced pathologies and to

determine possible therapeutic actions. The tissuesstudied are mainly the vascular endothelium, theintestinal barrier and the skin, given their possible rolein the multi-organ failures observed;

– Development of strategies for treating radiationinduced pathologies filling the cellular deficits usingcellular therapy. This work enables IRSN to bringexpertise to the medical teams treating accidentallyirradiated persons or treating patients using radiationtherapy.

All this research on health effects of ionising radiationconducted by IRSN do not cover all the inquiries relatedto this subject, in particular those related to carcinogene-sis. However, they provide IRSN with a privileged positionto develop cooperative research at national and inter-national levels.

Scoring of chromosome aberrations with microscope.

Biological dosimetry: mapping of the dose received atskin level for one of the patientsirradiated during the accident in Georgia.

LIMITING THE SIDE EFFECTS OF A RADIOTHERAPY

Radiation therapy treatments generally deliver highdoses necessary for the tumour monitoring, but alsoirradiate healthy tissue contiguous to the canceroustissue. They may cause very disabling side effects forpatients. On this topic, still poorly appraised, IRSNpursues research, especially in the laboratory operatedin collaboration with the Gustave-Roussy Institute, inorder to better understand the mechanisms implied inthe initiation, development and persistency of thoseside effects. The objective is to suggest preventive orcurative therapeutic strategies. The work initiated in2002 focuses on chronic radiation enteritis.



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Helping to prevent accidents in nuclear facilitiesor during transport and limiting the consequen-ces of accidents which might nevertheless occur

is a major concern for IRSN.

Assessing the safety of nuclear facilities andtransports requires at all times technical knowledge,given the evolution of facilities and the safetyapproach: aging of equipment, evolution of fuels,severe accidents, waste management, prevention ofcriticality risks, fire protection… For these technicallycomplex issues, the Institute develops and uses itscompetencies in the areas of studies, expertise andresearch. Researchers and experts have the sameglobal objective: assessing the risks to better controlthem and prevent their consequences.

The whole approach implies safety assessments andstudies used to identify issues insufficiently known aswell as research intended to increase the knowledge.Within this framework, the Institute has for manyyears developed probabilistic safety analyses (PSA)applied to the PWRs, which are used to assess theprobability of an important event for safety and itsconsequences.

The research studies have in particular resulted in aninteraction between the development of analyticmodels, the development of software and the carryingout of experiments in realistic conditions.

The competencies acquired by the IRSN in the areas ofexpertise and research are also used for non nuclearfacilities. The Institute makes available to the industryimprovements of its competencies.


IRSNContributing to the safety of nuclear facilities

and transports

750Technical notices transmittedby IRSN to safety authoritiesin 2002.

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

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

Paluel unit for nuclear electricity production.

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ACTIVITIES [ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]

Put into service in 1974, the Phénix reactor is a fast neutron reactor, with sodium cooling

systems. Owing to the age of the facility and CEA(Atomic Energy Commission) wishes to continue touse it for several years, since 1997 the licensee hasbegun a renovation programme including significantimprovements in the resistance to earthquakes andsodium fires.

Significant workThe core internal structures, sodium circuits, emergencyequipment were controlled, and, in some cases, repairedon the basis of a general assessment of the equipmentaging. The requirements regarding the resistance ofnuclear facilities to earthquakes, were also redefined andthe buildings were thus reinforced, involving a significantbuilding project.

Risk analysisIn view of a possible restart of the reactor in 2002, IRSNstudied CEA proposals regarding methods intended tocontrol and analyze failures as well as repairs of thesteam generator modules affected by a cracking pheno-menon specific to the stainless steel used for their cons-truction. Concerning the safety of steam generators, thelicensee’s justifications were studied according to anapproach which identified the existing in-depth lines foreach important safety event.

Other issues were studied, in particular those concerningthe risks in case of sodium fire and the in-servicemonitoring of the upper part of the reactor vessel. Thestructure supporting the control rods (plug-cover-core)was particularly studied, as well as the consequences of

an accident of instantaneous plugging of a fuel assemblywhich is a possible initiating event of partial coremeltdown.

IRSN submitted the results of its analyses to the FrenchAdvisory group of Experts for nuclear reactors in October2002. This meeting was the last of a series of eightmeetings held since 1996 within the framework of thesafety review of the nuclear facility.

Among other issues studied in 2002, the Institutehighlighted the need for the licensee to have moreefficient procedures and tools for the management ofcrisis situations.

Another important issue in 2002 was the study of the fireaction plans for each building. In fact, these plans werecompletely revised by the licensee,taking into account the renovationwork performed. Several failurecommon modes of materialsimportant for safety were thusidentified and processed by thelicensee. These actions have beencontinued in expectation of apower increase of the reactor.

It is important to recall that theresidual operating time of thePhénix reactor is a maximum of sixoperating cycles during which theCEA (Atomic Energy Commission)planned to perform various irradia-tion experiences, within the framework of partitioning-transmutation work, under the law of December 30th,1991 regarding the management of high activity andlong-life radioactive waste.

> Phenix safety review


Phénix in Marcoule.

Saint-Alban unit for nuclear electricity

production.

7In 2002, IRSN transmitted 7 technicalnotices concerning the safety of the Phénixfast neutron reactor and wrote a report for the French Advisory group of Experts for nuclear reactors.

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ACTIVITIES

IRSN provides technical notices on new develop-ments in fuel management requested by Electricité

de France in order to reduce production costs. The Institute has to carry out studies and researchprogrammes to assess the impact of fuel evolutionon safety.

Technical stress related to economic issuesEconomic considerations lead most of the electricians inthe world to strive for an increase of the burn upfractions of the nuclear fuel they use in their facilities.

In this framework, EDF was allowed in 1998 to use theuranium oxide (U02) based fuel to a burn-up a fraction of 52,000 MWj/t on average per assembly (instead of47,000 MWj/t previously). For the future, it forecastsmaximum burn up fractions that could reach, or evenexceed, 60,000 MWj/t.

Some electrical utilities companies, such as EDF, have forover 10 years, also used MOX type fuel (mixture of uraniumoxide U02 and plutonium oxide Pu02). The average burnup fraction of MOX fuel is today, in practice, limited to45,000 MWj/t according to its use instructions.

The increase of the MOX burn upfraction is also an industrial objec-tive for EDF.

These evolutions led the Instituteto organize, at the beginning of the1990s, a revision of the availableknowledge on fuel behaviouraround the world. This highlightedthe lack of knowledge concerningthe behaviour of fuels with highburn up fractions (exceeding theauthorised value set to 47,000MWj/t) and the need to study the

validity of the safety criteria in case of postulatedaccidents, such as the loss of coolant accidents andreactivity accidents in control rod ejection.

Increasing needs in terms of analysisAnother consequence of the increase of the fuel use rateis to stagger the maintenance shutdowns of the reactors,adjusted on the fuel use cycles. This requires studying theconsequences of the new practices from the safetyviewpoint. IRSN in 2002 undertook to analyse a feasibilitycase concerning the “parity” use of U02 and MOX fuels,implying a rise of the burn-up rate of MOX fuel up to52,000 MWj/t.The analysis focuses on the fuel evolutions likely to havean effect on its behaviour in operation: evolution of theassembly design, use of new structural or claddingmaterials. In 2002, in the framework of its expertise, IRSNspecifically studied a proposal related to the reinforcedstructure assembly, intended to compensate a failure dueto the cladding perforation by “fretting”, detected duringthe cycle No 8 of the Cattenom 3 unit. The claddingcorrosion phenomena are also monitored and analysed by EDF .Assessing the safety of these technological evolutions, in particular the available safety margins, implies developing increasingly sophisticated assessmentmethods, in particular including three-dimensionalthermo-hydraulic or neutron software.

> Studying the safety of PWR fuels

Test device in the water loop.

13IRSN performed 13 expertise studiesrelated to the development of new fuel on behalf of safetyauthorities.


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Research programmesResearch programmes conducted by IRSN study fuelbehaviour during postulated accidents: the accident ofaccidental reactivity injection, with the programmesconducted on the CABRI reactor, and the loss of coolantaccident, with a study programme on the irradiatedcladding behaviour.

CABRI programmes The first CABRI programme concerning PWR fuel wasinitiated in 1993 in the sodium-cooled CABRI reactor loop,in collaboration with EDF and with the support of theNRC (safety authority of the United States). The purposewas to study the behaviour of uranium oxide (U02) basedand fuels and MOX fuels in a situation of reactivity acci-dent for high burn up fractions. 12 tests, called “REP-Na”,were performed in the CABRI reactor, including eight onthe UO2 fuel and four on the MOX fuel. The “in-pile” testswere completed by tests referred to as “separate effecttests” related in particular to the mechanical properties ofthe irradiated clads and by the development of softwareknown as SCANAIR, used both for the interpretation oftest results and their transposition to reactor conditions.The lessons drawn from this programme were used withinthe framework of the expertise of the files concerning theuse of U02 fuel to a 52,000 MWj/t burn up fraction.

In order to determine the behaviour of even higher burnup fraction-fuels, IRSN in 2000 launched a new inter-national programme called CABRI-Water Loop, mainlyconducted within the framework of the AEN of the OECD.

The tests in the CABRI reactor will be performed in a“water loop” under pressure, more representative of thethermohydraulic conditions characterizing the PWRs that the sodium loop which has equipped this reactoruntil now.

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

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

View of the CABRI pooland core (CEA facility).

CABRI RESEARCH REACTOR

The CABRI research reactor is a unique installation inthe world, used to simulate the conditions of areactivity accident in a PWR. Operational since 1978, itwas initially intended to safety studies of fast neutronreactors (with a loop cooled by liquid sodium). Fourprogrammes were conducted on it, including the lastone called CABRI-RAFT, carried out in partnership withthe Japanese JNC organisation, ended in 2001. Its usefor the CABRI-Water loop programme requires, on the one hand, an upgrading regarding safety given the evolution of the practices, especially regarding fireprotection risks and seismic risks and, on the otherhand, the replacement of the sodium loop by a water loop.

[ SAFETY OF NUCLEAR FACILITIES AND TRANSPORTS ]


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ACTIVITIES

The purpose of the safety review is to check, everyten years, the safety level of nuclear facilities,

taking into account evolutions in safety practices(resistance to earthquakes…). 2002 was a pivotalyear, with the end of the safety review linked to thesecond decennial outage programmes and thebeginning of the safety review for the third decen-nial outage programmes of 900 MWe power plants.As for the 1,300 MWe power plants, the safetyreview began in 1997 for the second decennialoutage programmes scheduled from 2005 on.

In practice, the safety review process for 900 MWeand 1,300 MWe power plants is based on two mainparts: the check of the reactor’s conformityregarding its initial safety baseline and the review ofsafety requirements. The studies initiated from thenew safety requirements may lead to the implemen-tation of modifications intended to improve safetyduring the next ten-yearly outages.

Safety review of the 900 MWe nuclear powerplants for the second ten-yearly outagesThe 900 MWe power plants using pressurized waterreactors (PWR) are the oldest of the French nuclear powerplants. They were put in service between 1977 and 1987.The safety review approach of these power plants hasbeen initiated from 1987 for the oldest of these. Thisapproach for all 900 MWe power plants will be completed

as second ten-yearly outages ofthese plants go along, i.e. after 20 years of production.

The French Standing group ofExperts for nuclear reactors wasregularly consulted throughoutthe various steps of the processwhich took place over more than10 years.

In order to close this approach onall the 900 MWe power plants,

the DGSNR (Nuclear safety Authority) requested thetechnical notices of the French Standing group of Expertsrelated to the consideration of the safety requirementsresulting from the safety review of the power plants aftertheir second ten-yearly outage.

IRSN established an overall assessment of the approachconducted by the licensee and submitted its conclusionsto the French Standing group of Experts on February 28th

and March 14th, 2002. At this level, it did not discusselements which could raise the question concerning thecontinuation of the 900 MWe plant operations until thethird ten-yearly outages which will occur 2008 to 2015.However, EDF still has a significant amount of work tocarry out to finalise this study. In fact, the complianceprojects initiated and the modifications planned willcompletely help to improve the safety level of thesepower plants only at the date of their second ten-yearlyoutages.

Third ten-yearly outage programmesThe safety review associated with the second ten-yearlyoutage programmes has been particularly long. Thus,IRSN highlighted the need to rapidly identify the contentof the phases of the safety review linked to the third ten-yearly outages: content definition of the safetyreview and associated baseline, actual studies, controlsand implementation of the modifications. Furthermore,this process will be properly developed to meet the studydeadlines of the modifications in order to implementthem during ten-yearly outages. As the third ten-yearlyoutages of 900 MWe power plants are scheduled fromthe end of 2008, the definition of this safety review waslaunched asof 2002. This step is the first of a processwhich will set, by 2007, the requirements in which the900 MWe power plants will be authorised to be still beoperated after 30 years in service.

> Safety review of nuclear power plants

Reactor building (EDF installation).

130IRSN monitors 130 basic nuclearinstallations (pressurized waterreactors, fuel cycleplants…) in France.


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Safety review of 1,300 MWe nuclear powerplantsOn March 28th, April 4th and December 19th, 2002, IRSNsubmitted to the French Standing group of Experts fornuclear reactors its assessment of the safety requirementbaseline and the EDF approaches concerning thecompliance and reassessment studies for the 1,300 MWepower plants.

It emerged that there is a need for EDF to specify somepoints, such as the functional capacity of certainmaterials used in accidental situations out of postulatedand takes into account new requirements resulting fromthe classification of the materials and systems requiredfor safety.

Furthermore, the resistance to earthquakes of the buildingsand equipment will be reassessed, taking into account theevolution of technical rules related to seismic risk, andthe risks of explosion inside buildings shall be subjectedto a safety review for all the power plants.

The next step will consist in assessing the detailedprogramme of the modifications and the results from thecompliance examination of the reactors implemented bythe licensee.

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

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

REMOVAL OF THE RESIDUAL POWERFROM THE USED FUEL ASSEMBLIESSTORED IN THE SPENT FUEL POOLS OF THE PWR (PRESSURIZED WATERREACTOR)

To reduce the shutdown periods of the reactors in orderto increase their availability, EDF reduced the timebetween reactor shutdown and the end of fuelunloading. This leads to an increase in the residualpower which shall be removed from the spent fuel poolduring refuelling shutdown.Therefore, the facilities participating in the safety of theirradiated assembly storage have been operated todaybeyond the conditions defined in the safety reports.This situation has been highlighted by the feedback ofexperience and the safety review performed for the900 MWe power plants. It is processed through theimplementation of transitory operation stresses towhich final improvements are added. Within thisframework, IRSN analysed EDF proposals in order toimprove the safety of spent fuel storage and removethe current stresses involved in the operation of spentfuel pools of 900 MWe power plants.The Institute analysed the material and documentarymodifications proposed by EDF in order to strengthenthe prevention, detection and management of acciden-tal situations which could have an impact on the safetyof irradiated fuel storage. It particularly studied if theproposed measures would make it possible to managea complete and prolonged loss of coolant of a spentfuel pool and analysed the probability assessmenttransmitted by EDF related to the risk of fuel dewater-ing in such a situation. IRSN conclusions weresubmitted to the French Standing group of Experts fornuclear reactors in November 2002. It has been shownthat the control of the cooling of spent fuel stored inthe spent fuel pools of the power plants will be signifi-cantly improved when the modifications planned byEDF will have been applied. These modifications shall beadapted to be implemented on the most recent powerplants (1,300 and 1,450 MWe).



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ACTIVITIES

Although extremely unlikely, core meltdownaccidents situations which have not yet been

taken into account during initial design of theexisting power plants deserve specific precautions.Significant research has been conducted by theInstitute on the phenomena concerned, in order tocontribute to the prevention and the mitigation ofthe consequences of such accidents. Today, IRSN is amajor actor in research around the world on theaccident situations of PWR core meltdown.

The core meltdown accidents would result from a seriesof failures and could generate significant releases ofradioactive products in the environment.

Studies and researchThe studies and research conducted at the Institute onsevere accidents aim at:– Identifying the possible accident scenarios and assess-

ing their probabilities;– Studying the progress and possible consequences of

such accidents, including the risks of containment failureand the possible radioactive releases.

To achieve this, IRSN develops a research strategy whichcombines analytical experiments, the physical modellingof the phenomena, the development and qualification ofsoftware to be applied to reactors and the performanceof global experiments, notably in test reactors. Researchparticularly studies core degradation, iodine chemistry,aerosol behaviour and containment resistance. They aresubject to international collaboration, in particular withthe European Union, the United States, Japan, Switzer-land and Russia…

A role to support public authoritiesThe task of the Institute is to bring technical elementsenabling the public authorities:– To assess the measures suggested by the licensees

to prevent core meltdown accidents and limit theirconsequences;

– To assess retained or possible means to limit the conse-quences of such accidents;

– To prepare emergency plans and assess in real time, incase of accident, the risks encountered in order to be ina position to take countermeasures to be implementedfor ensuring the protection of populations;

– To improve crisis management with a better assessmentof the effects, measures and interventions provided forand periods of dreaded events;

– To assess the acceptability of the design of possiblefuture reactors.

> Research on the PWR core meltdown accidents

International relations involve the SARNET network.

FP caisson whose loop (in red) simulates a steam generator.

PROBABILISTIC SAFETY ANALYSES (PSA)

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


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Phébus FP is the most significant research programme in the world regarding nuclear safety.Operational since 1978 in the Cadarache (Bouches-du-Rhône) research centre, Phébus is an experimentalreactor of the CEA, which was modified in 1989 to carryout the Phébus FP programme. The Phébus FP experimen-tal facility is a 1/5000 simulator of the main componentsof a pressurized water reactor. It is used to perform globalexperiments reproducing all the phenomena occurringduring a core meltdown accident and contributing to therelease of radioactive products. The Phébus FP programmeis an international programme conducted by IRSN andmobilising 35 organisations from the European Union,the United States, Canada, Japan, South Korea andSwitzerland. In 2002, the participation in this programmeof several organisations from candidate countries to jointhe European Union, was negotiated: Czech Republic,Slovakia, Hungary, Slovenia, Bulgaria and Romania.

The Phébus FP programme includes five tests spread overabout 15 years. The first was performed in 1993 and threeother tests were also performed, respectively, in 1996,1999 and 2000.

After the analysis of the fourth test data, a preliminarysynthesis of the Phébus FP programme, as a whole, wasdeveloped in 2002.

Three main points have emerged:– Computer codes had to be modified. This concerns the

chemical forms of fission products in the primarycooling system, the presence of gaseous iodine amongthe fission products released into the containmentthrough the break in the primary cooling system, theproduction of organic iodine in the containment. Thesephenomena must be subjected to additional experi-mental work;

– Some unexplored phenomena appear significant: thisconcerns the degradation and re-localization of thefuel, the effect of fuel degradation on the releases offission products, the transport of representative fissionproducts in the primary cooling system, the iodinechemistry in the containment when materials from thecontrol rods are present;

– Modelling concerning the thermohydraulic and theaerosol behaviour in the containment, the release andtransport of the fission products are acceptable.

Furthermore, the preparation of the fifth test, planned for2004, gave rise in 2002 to the end of the preliminarycalculation phase, in collaboration with the German, Swissand Japanese partners of the programme. Concurrently,major clean-up work was conducted in the experimentalfacility, before the installation of the new experimentalcircuits.

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

ASTEC, an integrated calculation toolDeveloped for more than ten years with GRS (Gesellschaftfür Anlagen und Reaktorsicherheit – Germany), ASTEC isan integrated software system. It is used to simulate acore meltdown accident in a water reactor, from theinitiating event to the possible releases of fission productsout of the containment. ASTEC is currently used withinthe framework of Probabilistic Safety Assessmentsperformed by IRSN. It is also used for the definition of thePhébus FP experiments. Today, ASTEC is becoming theEuropean reference for integrated system software in itsarea.

The main efforts carried out in 2002 focused on the V1version, delivered during the middle of the year. This willnow be strengthened, in particular within the frameworkof EVITA, the European ASTEC qualification project.Furthermore, new models were developed, concerningiodine in particular.

Lastly, the training of software users started in 2002 andinvolved concerned 40 people from all European countries.

SARNET, creation of a network of excellence oncore meltdown accidentsConducted by IRSN, SARNET is a project which will besubmitted to the first call for tender of the 6th FrameworkProgramme. The purpose of this network is to bettercoordinate the research efforts of European laboratoriesdealing with core meltdown accidents. For IRSN, this isthe following step forward in international collaborationalready conducted in this area.

This is also an opportunity to support the ASTEC softwaresystem at the European level, in order to improve its relia-bility, with the feedback of experiences by European users.

Already, almost 370 researchers and doctorate studentsfrom 52 European organisations have expressed interestin taking part in the network.



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ACTIVITIES

The purpose of radioactive waste management isto confine radioactivity to result in the lowest

risk possible level of risk for human beings and theenvironment. To assess the measures proposed bylicensees, IRSN will be able to evaluate their comple-teness and their quality, in normal or accidentalsituations, for the disposal and of various wastemanagement options. Thus, the Institute has beencarrying out research programmes to acquire appro-priate knowledge in the concerned fields.

Medium and long-term issuesIRSN studies focus in particular on:– The safety of radioactive waste treatment, conditioning,

interim storage and surface disposal facilities;– The disposal possibilities in deep geological formations.

For this purpose, IRSN develops both field experimentsand modelling;

– The studies of the impact on human beings and theenvironment of contaminated sites by former industrialactivities and mining sites.

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

Those key points highlight three types of concerns:– The general knowledge of the site: structural geology

(identification of the secondary fracturing); hydro-geology (outlets and transfer times); chemical andthermal containment capacity of the clay unit;

– The feasibility of the design options of a disposal:assessment of the chemical disturbances; disposallayout and damaging minimization; sealing andrestoring the environment continuity;

– The operation and reversibility conditions of thedisposal.

In 2002, IRSN evaluated the geological and hydro-geological modelling presented by ANDRA for theMeuse/Haute-Marne site. Within this framework, IRSNtook into account the first results of geophysical experi-ments carried out in the underground research laboratoryat Tournemire using a high resolution 3D seismic methodto assess the capacity of the method to detect secondaryfaults in argillaceous media.

Application of the high resolution 3D seismicmethod to detect faults in argillaceous mediaIn a very low permeability clay unit, the transport ofradionuclides preferentially occurs along faults. Therefore,the assessment of the capacity of a clay unit to host deep disposal implies the detection and mapping of theexisting faults.

The high resolution 3D seismic method is a tool aiming atdetecting faults. A seismic survey coordinated by IRSNwas carried out at the Tournemire site (Aveyron).

The principle of the method is the following: vibratortrucks shake the ground to frequencies ranging from 10 to 160 Hz. The 3D propagation of the seismic wavesare reflected by the geological discontinuities. A networkof 5,600 sensors set on the surface and connected to anacquisition unit enables information to be collect, like asonogram.

The main faults can be identified by classical geophysicalmethods. On the contrary, the secondary faults mappedat the Tournemire site cannot be identified by classicalgeophysical seismic methods (2D).

After preliminary studies, the survey took place over 3weeks in November 2001. It mobilized almost 20 people.

> Ensuring waste management safety


Geophone used for seismic recording.

IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 36

According to the first results published in 2002, theanalysis of the data did not allow the identification of the faults in the clay unit. This preliminary result does notmean that the principle of the method is not appropriate.In fact, progress is expected in the future, which willenable a better resolution.

Mining waste management Waste from uranium mines contains radioactive residuesstored on site. Their concentration in radionuclidesclassifies it in the category of low radioactive waste, butits volume, its physical and chemical form and the life-time of the radioelements contained (a period of severalthousand years) nevertheless generate questions regard-ing public protection.

To begin with, IRSN has to express its opinion on theprotection means implemented by the licensee after the decommissioning of the mine. Thus, the study of thefile dealing with the radiobiological impact assessmentafter the redevelopment of the last site operated, Jouac,is currently in progress.

More generally, the expertise showed that mining activityis at the origin of a measurable radiological marking ofthe environment. In order to have more complete infor-mation, IRSN launched a programme of investigations in2002 upon the request of the Ministry of Ecology andSustainable Development. The purpose of this programmeis to assess available knowledge concerning all the sites inorder to identify the situations of significant marking orlack of information. Then, if appropriate, it can be used tocomplete the knowledge on the radiological status in theless studied mining regions and possibly to suggestinflections to the existing measures.

Chernobyl experimental platformIn the area called the “Red Forest”, located a fewkilometres from the Chernobyl power plant, soils anddebris contaminated by the accident were buried inrapidly dug non-waterproof trenches. Subject to theaction of the rain waters, these trenches release radio-nuclides in the natural environment.

In 1999, IRSN initiated co-operation with Ukrainian orga-nisations (IGS and UIAR) and the CEA (Atomic EnergyCommission), in order to study the transport of radio-nuclides in the environment. The knowledge acquiredwithin the framework of this research greatly interestedthe concerned countries. For the Ukrainians, this may beapplied to rehabilitation of the site. For the French, this isbeing used as a full-scale validation of models used forthe storage of radioactive waste or the rehabilitation ofcontaminated sites.

An experimental platform was implemented comprisingequipment used to monitor the contamination. From thisplatform, the researchers study three different environ-ments contaminated in various ways:– The location of the former trench, the most contamina-

ted environment;– The unsaturated zone which extends to the surface

reaching 3.5 m in depth, and in which cracks are notcompletely filled with water;

– The aquiferous formation below 3.5 m, where water fillsin the vacuums left by solid material.

Relevant results were obtained, especially in the trenchand in the aquiferous zone. This work, summarised in2002, was used to identify the particles which mainlycontribute to the radioactivity source, characterise theirrespective dispersions and compare these observations to the modelling. For the unsaturated zone, the forecastof the long-term migration of the radionuclides willrequire the exploration of other phenomena by specificprogrammes.



Chernobyl experimental platform: installation of water sampling probes.Redevelopment of the mining site of COGEMA Lodeve.

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ACTIVITIES

All the research and expertise work conducted inthe Institute provide it with competencies which

find applications beyond nuclear power, in particularin the area of industrial risk.

Expertise of classified facilitiesAs an expert recognized by the Ministry of the Environment,IRSN conducts critical analyses of danger studies performedby industrialists. To do so, it calls upon its competencies,in particular in chemistry, chemical engineering, fire pro-tection and explosion. In 2002, the Institute conductedalmost 40 critical analyses of danger studies concerningfacilities classified for the protection of the environment.The tripling of critical analyses, compared to 2001, ismainly a consequence of the accident of the AZF plant in Toulouse (Haute-Garonne). The expertise performed

in 2002 concerned various plants:petrochemistry, transformation chemis-try, fine chemistry, agricultural and foodsystem, agro-pharmaceuticals, etc. Thesefocused on a very wide range of topics:risks of fire, explosion, thermal runaway,toxic gas dispersion, environmentalimpact. IRSN also performed less com-mon expertises such as the processing ofexemption claims for the implementa-tion of safety valves on pressurizedequipment or the determination ofdomino effects on some industrial sites.

Expertises in olfactometryFor over 30 years, olfactometry has used and improvedthe knowledge and competencies acquired in the nuclearsector on gas transfer and dispersion. Today, IRSNconducts expert activity for industries producingmalodorous gas releases. The results of the olfactometricmeasurements performed by the Institute are used to

orientate the choice of technological solutions intendedto limit the impact of the olfactory pollution of industrieson the environment. IRSN works on this issue in collabo-ration with INERIS (National Institute of the IndustrialEnvironment and Hazards).

In 2002, 15 studies were conducted for industrial facilities(agricultural-food system, rendering and transformationplants, technical land fill centres), research departments,local communities (contaminated site services, treatmentplants) and breeding (pigs, poultry).

The Institute also takes part in training on the subjectfrom professionals working in air quality networks andtreatment plants, DRIRE (Regional Agency for Industry,Research and the Environment) and DSV (VeterinaryServices Branch) members or within the framework ofDESS and DUT on the environment…

Physics of aerosolsPhysics and metrology of aerosols find applications out-side the nuclear area. In addition, since it is little developedin France, the competencies acquired and maintainedwithin IRSN are today recognized all over the world.

Within this framework, the Institute is represented in the scientific committee of the national safety research

> Expertise used for industrial risk control

LPG reception inthe Herrlisheim

site.

Canalisedsampling of an odorous gas sample.

40In 2002, IRSNperformed 40expertise studiesconcerning nonnuclear industrialfacilities.

Panelist sniffing the olfactometer sniffing ports.


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 38

institute, which conducts work on professional risks. Ittakes part in the work of the contamination preventionand study association, bringing together agricultural-food, medical and other industries.In the area of professional risks, IRSN participated in aEuropean commission contract for the improvement ofthe performance of aerosol samplers at the workplace(CALTOOL). The purpose was to test those sampling toolsto compare their efficiency in different situations anddifferent workplaces. The contract ended in 2002 and wasrelated in publications.

Besides, many nuclear-related activities may have widerapplications, in particular for toxic powders. A commoninterest programme is in progress with COGEMA on thesuspension of powders during drops of the containers.

Lastly, the international recognition of its competencieswas expressed by the granting of the “International aerosolfellow Award” in 2002 to a researcher of the Institute.

Probabilistic assessment in a storage andfilling centre for liquefied petroleum gasUpon the request of the Ministry of the Environment,IRSN took on the responsibility for conducting aProbabilistic Safety Assessment applied to a SEVESO-typefacility. The objective of this assessment is to betterunderstand the additional knowledge that a probabilisticassessment could provide for the safety of these facilities.

In collaboration with the French butane and propanecommittee, the site choice was made on a storage andfilling centre of liquefied petroleum gas, managed by theRhône-Gaz company in Herrlisheim (Bas-Rhin).

The assessment was carried out in two stages:– The definition of a study method appropriate to the

facility, in collaboration with the industrialist concerned;– The performance of the assessment per se.

The assessment consisted in identifying the various acci-dental series which may lead to a BLEVE (Boiling LiquidExpanding Vapour Explosion) in case of the heating ofone of the storage capacities, inducing a fire ball, a shockwave and projections, and assessing the probabilities ofthese series. The initiating events of the accidental seriesmay be process failures but also internal hazards (fire,flooding…).

In 2002, the first phase of the project was carried out andpresented to the Ministry. The development of qualitativeevent trees highlighted safety elements which signifi-cantly contribute to the series of undesirable eventsleading to the BLEVE on the one hand, and some difficul-ties to quantify the accidental series, due to the limitedrepresentative nature of some models and the use ofgeneric data, on the other hand.

The assessment involves up to 15 persons in the Institute,with various competencies: safety, development ofProbabilistic Safety Assessments, accident phenomenolo-gy, assessment of weather variations or hazards related tohuman activities in the site environment…

The assessment and conclusions should be submitted inMay 2004.

Air contaminationexperience: suspension

during an accidentalpowder drop.

WORK CONDUCTED WITH INERIS

The collaboration between IRSN and INERIS originatesfrom the will of both organisations to develop theirsynergies.In the area of olfactometry, the collaboration betweenboth organisations concerns:– Expertise combining IRSN competencies for olfacto-

metry and INERIS competencies for physical chemistry.Two assessments were conducted in common in 2002;

– The draft of an “odours” guide, upon the request ofthe ADEME (Agency for the Environment and EnergyControl) and in collaboration with other experts. Thisguide will introduce all the approaches that an indus-trialist shall adopt to limit the olfactory pollutionresulting from his activities;

– The implementation of a reflection group on theregulation, measuring techniques and future Europeanstandard as regards olfactometry in late 2002.

Concerning fire risks, collaboration focuses on researchprojects. In 2002, the work was particularly focused onthe characterisation of the fire power of various fuels.

Lastly, collaboration regarding ecotoxicology particu-larly focuses on research concerning the toxic effects ofuranium on the fish and the development of genotoxi-city markers.

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IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 39

ACTIVITIES

IRSN deals with various aspects of criticality risk,from prevention to the assessment of conse-

quences. The purpose is above all to prevent thedevelopment of a chain fission reaction out of anuclear reactor, i.e. in a facility not intended for thatpurpose (plant, laboratory or transport packing). This type of reaction involves the release of neutronand gamma radiation as well as the production ofradioactive products likely to be spread out of theconcerned facility. The main consequences of acriticality accident would therefore be to irradiatepersons who might be close to the accident site. The Institute develops qualified computer methodsand applies them to the assessment of the measuresused to prevent criticality risk and, in case ofaccident, it assesses the consequences on health andthe environment.

Technical and economical issuesPrevention of criticality risk was a major concern begin-ning with the very first uses of nuclear power. It led to theimplementation of restricting measures: limitation of theproduct quantities, container size, water quantities used,etc.

Progress of knowledge today enables some stresses to bereduced, while ensuring the safety of the facility ortransport packing. In this area, IRSN prepares methods,develops software and conducts case studies. The objectiveof this work is to have accurate means to analyze thecriticality risk.

The qualification and validation of computer tools focuson comparing calculation results based on reality andexperiences approaching critical status. The comparisonof the calculated results and experimental results is usedto establish the accuracy of calculations for specificsituations, and, if appropriate, suggest improvements ofthe calculation techniques.

Beyond research, IRSN also provides expertise, inparticular for laboratories, plants and transport. The workin analysis involves checking that prevention measures,suggested by the licensee on the basis of calculations, areappropriate and sufficient, including cases of possiblemalfunctions. For the transport of fissile materials, theverification of criticality calculations of carriers issystematic. In the case of assessments carried out with

third-party software, counter-calculations are conducted.Every year, over 50 files concerning the transport of fissilematerials, each corresponding to multiple contents, arestudied in the Institute.

CRISTAL, a new generation criticality-safetypackageCRISTAL is a programme conducted by IRSN, developedwith the CEA and financed by COGEMA.

Since 1999, the first version of this software has beenmade available to IRSN, the CEA and major French nuclearindustrialists (COGEMA, Framatome, Technicatome). It isused by 90 engineers and is currently being tested by EDF.Within the framework of this programme, IRSN developsthe 3D multi-group neutron simulation code, Moret IV.Furthermore, it is equipped with the man-machineinterface which ensures the integration of variouscalculation modules, as well as the connection with users,which is used to take into account their experience.

In 2002, a CRISTAL Web site was opened to the public at large; there is also a Web site restricted to users so they can share information, remarks and inquiries. Users can also download documents or correction patches. In addition to the development of a user communitypromoting the exchange and the availability ofinformation, the openness of the site was intended toimplement a working organisation with users, especiallyfor maintenance.

It was updated for the first time in September 2002. Thedevelopment of the next version has been initiated. It willinclude new functionalities and is slated to be delivered in September 2003.

Lastly, IRSN participates in the International CriticitySafety Benchmark Evaluation Project, under the auspicesof the OECD. This project consists in pooling criticalityexperiences which have been conducted around theworld for over 20 years. This work is essential for thequalification of calculation systems such as CRISTAL sincein fact, almost 1,200 criticality experiences from varioussources were recalculated by CRISTAL.

> Controlling criticality risk


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A common interest programme with COGEMAIn 2002, experimental programmes were carried out withinthe framework of the Common Interest Programme initia-ted with COGEMA as of 1996. This programme concernsthe prevention from criticality risks in fuel cycle instal-lations and transport.

The purpose is to quantitatively assess the safety marginsrelated to the loss of reactivity of irradiated fuels, and to develop more accurate calculation methods intended toassess criticality risks. For those fuels, experiences havebeen conducted for six stable fission products causing halfof the reactivity loss generated by the fission products.

In addition, this programme aims at improving the critica-lity calculation systems to meet new needs for nuclearfacilities and the transport packing for fissile materials. The experiments conducted on the Valduc (Côte-d’Or) siteare unique in the world.

An exercise to compare the dosimetry methodsfor criticality accidentsIn 2002, IRSN organised an international intercomparisonexercise of dosimetry for criticality accidents. Thisoperation, jointly conducted with the OECD NuclearEnergy Agency, was performed in collaboration with theValduc CEA centre. It was supported by the EuropeanCommission.

Almost thirty countries from Eastern and Western Europe,North and South America, as well as Asia, participated inthis exercise.

It enabled each of them to test thephysical and/or biological dosimetrytechniques in experimental condi-tions simulating a criticality accident.

This intercomparison had been sche-duled just before the criticality acci-dent which occurred in September1999 in Tokaï-Mura (Japan).

It involved experiences conducted inthe Valduc CEA centre on the Silènereactor, simulating different criticalityaccident configurations generatingan intense release of neutron andgamma radiation.

The results of the final assessmentand the conclusions will be publishedwithin the framework of the “9th

International Symposium on NeutronDosimetry” in Delft (Netherlands) inSeptember 2003. A complete sessionwill be dedicated to this intercompa-rison.

Criticality dosimeters exposed around the Silène reactor.

Internationalintercomparison of dosimetry on the Silènereactor: positioning of dosimeters.

29 different countries

60 laboratories

500 irradiated dosimetersfor the internationalintercomparison ofaccident dosimetryorganised by IRSN in 2002.



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ACTIVITIES

The use of some package types to transport ofnuclear materials is subject to an agreement

issued by the competent authority: DGSNR for civiluse transports, DSND for the transport of materialsfor Defence purposes. IRSN performs studies andresearch as well as expertise on the transport ofnuclear materials.

Expertise of transport packagesEvery year, the Institute transmits between 100 and 150 technical notices on the compliance of transportpackages of nuclear materials according to regulations. In these technical notices, several aspects are considered:– The safety of the radioactive material containment;– Radiation protection of workers and of the public;– Prevention from criticality risks.

The certifications of new packages are issued for a periodof three to five years. In the case of a certificationextension, the Institute performs partial expertise only,with particular emphasis on the examination of acquiredexperience. For some types of packages, the expertiseespecially focuses on the radiolysis risk.

Radiolysis during the transport of nuclear materialsThe phenomenon of radiolysis (decomposition of waterinto hydrogen and oxygen by ionising radiation) mayhave an impact on the safety of the transport packages,as it may lead to an explosion. For this particular issue,the Institute has conducted a review of the packagemodels approved or under special agreement for 10 years.

Given the diversity of the situations encountered and thecomplexity of the radiolysis phenomenon, industrialistshave been requested to base their justifications on expe-rimental values. Industrialists performed measurementsin real conditions, in order to quantify the radiolysisphenomenon for all packages. For this purpose, theydeveloped experimental programmes, including somenow which are nearing completion.

The packages concerned are divided into several categories:– Those used for under-water transport of irradiated fuels

intended for reprocessing: CASTOR S1, EXCELLOX 6, NTL 11, NTL 15. These packages have been equippedwith new catalysts (recombining hydrogen and oxygen)used to remove the gas released by the water radiolysis.The assessment of this equipment is in progress;

– Those used for the transport of organic waste (cellulose,various plastics, gloves…): TN GEMINI, RD 26, RD 15IIB,IU 11, DGD-D-001. Given the difficulty to conduct ana-

lytical experiences, it was decided to proceed on a caseby case basis and to conduct campaigns for measuringthe hydrogen concentration depending on weather and the activity of the waste transported. This was usedto quantify the phenomena and to show that thehydrogen concentrations do not reach safety limits;

– Those used for the transport of plutonium oxide (FS 47,TN BGC-1), for which oxygen absorption, and nothydrogen production, appears.

The safety approach related to the radiolysis risk is agradual and cautious approach which first consists inissuing transport authorisations for power ranges andlimited durations, and then extending these autho-risations depending on the results of the experimentalprogrammes.

> Assessing transport safety

USING FEEDBACK FROM EXPERIENCE

IRSN analyses the incidents and accidents oftransport of nuclear materials. Thus, the analysis ofthe incident occurred on December 29th, 2001 atCharles-de-Gaulle Roissy (Val-d’Oise), during atransport of radioactive products from Sweden to theUnited States led to the following conclusions:– The quality of the package preparation shall be

rigorously controlled;– The packaging of the package content will be better

specified;– The radiation protection programmes, compulsory

since July 2001 for air transports and dosimetricmonitoring of the most exposed workers, will berapidly implemented by the carriers.

COGÉMA 55

Bio CIS 13

CEA 10

Framatome 7

French miscellaneous

12

Foreign 10

DISTRIBUTIONS OF THE 111 TECHNICAL NOTICESRELATED TO THE PACKAGES TRANSMITTED IN 2002


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End of the Common interest programme with COGEMA on the safety of the transport of nuclear materialsStarted in 1996, the Common interest programme ended in 2002 with the completion of a study on thethermal behaviour of the transport packages TN 12/2 andTN 28 VT, subject to fires of variable duration.

According to the regulation, a type-B package shall resista 800° C fire during 30 minutes, in order to be authorised.The purpose of this study was to determine the realisticdurations of fire resistance of the packages for differenttemperature levels.

A calculation approach was used to realistically describethe behaviour of some package materials such as resin.The study used three-dimensional models appropriate tothe simulation of the phenomena and especially toidentify the presence of discontinuities in the packages.

The code developed was qualified using the experimentalresults obtained on a real package and on samples subjectto tests in an oven. The simulation was used to determinethe maximum durations of fire resistance of thesepackages by studying the risks of loss of seal tightness,clad failures and deformation of the internal structure ofthe package.

Four temperatures were studied: 400° C, 600° C, 800° C,1,000° C. Temperatures below 800° C concern mainlymaritime transport. The 1,000° C temperature is associatedwith tunnel-type configurations or special hydrocarbons(kerosene type).

The calculations related to both packages take intoaccount the temperature increase inside the packageafter the end of the fire. For example, the containment ofthe TN 12/2 and TN 28 VT packages is ensured for an800° C fire lasting over 1 h 40, which highlights a safetymargin of about three times the regulatory duration of 30 minutes.

This study confirmed the significance to use three-dimensional models despite the complexity of theirimplementation.

Within the framework of this programme, IRSN develo-ped a very sophisticated tool intended to assess thetemperatures of the packages in various fire conditions:THERMX-PROTÉE, now available for applications to otherpackages.

T=0,050 s T=0,122 s T=0,140 s T=0,250 s

A ship for the transport of spent fuel packages (TN12/2). Return of vitrified residue to Japan in TN28VT transport packages.

A NEW COLLABORATION CONCERNING RADIATION PROTECTION IN TRANSPORTS

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



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ACTIVITIES

T he risk of fire is a major safety concern, given theprobability of a fire in a nuclear facility and

the severe consequences that a non controlled firemight cause. The research, studies and expertiseconducted by IRSN on fires allow better assessmentof the measures taken by the licensees to ensure thesafety of their facilities and promote improvements.

A close connection between expertise and researchThe assessment of the technical measures taken by thelicensees to ensure the safety of their facilities againstfire risks revealed the existence of insufficiently knownareas requiring research actions. These actions includeexperimental programmes and modelling work and theresults of this research contribute to improve the safetymeasures implemented.

Studies underlying areas of uncertaintyThe studies conducted to support safety assessmentfocus on all the mechanisms which can generate releasesof radioactive products following a fire. Among thesestudies, the Probabilistic Safety Assessment conducted onthe risks of core meltdown in case of fire in a 900 MWepower plant particularly highlighted significant uncer-tainty areas that led IRSN to perform research to improveknowledge. This was the case for the following topics:– The combustion of electrical boxes: the CARMELA

programme provided in 2002 first results related to thissubject;

– The propagation to adjoining premises via ventilationand the openings of a fire started in a close and venti-lated room with the DIVA programme being initiated;

– The behaviour of compartmentalisation and contain-ment equipment (doors, fire-dampers, filters…) submittedto stresses resulting from a fire: the STARMANIA pro-gramme, started in 2001 and continued in 2002, studiesthis subject;

– The “characterisation” of fuels: the action conducted by IRSN aims at improving the existing database bymeasuring certain physical properties of almost thirtymaterials.

The first lessons drawn from these research programmeshave already been used for expertise purposes, in particu-lar for the assessment of the vulnerability of the controlrooms of nuclear power plants. Improvements have beenrecommended following this assessment.

Furthermore, the examination of the operationalexperience highlighted other concerns, such as the sootcorrosion aspect and the evolution of the concrete tight-ness submitted to a thermal flux. Those topics are subjectto thorough thinking in order to define, if appropriate,future research programmes.

Most of the topics cited above and the results of thecorresponding research also demonstrate an interest forthe safety of the laboratories and plants. For these typesof facilities, work was initiated in 1998 in order to revisethe Fundamental safety regulation l.4.A, related to fireprotection of basic nuclear installations other thannuclear reactors. The objective is to take into account theprogress of knowledge and to better distinguish problemsin the fire area (compartmentalisation of the premises)and problems in the containment of radioactive materials.The new draft, discussed in November 2001 by the FrenchStanding group of Experts, was deepened in 2002 andwas subjected to application tests in a facility.

> Reinforcing fire protection

SAFETY ASSESSMENT

In 2002, the Institute studied the Fire action Planimplemented by EDF on its installations, and submittedits technical notices to the French Standing group ofExperts for nuclear reactors on November 7th and 21st,2002. These technical notices highlight:– The needed evolution of the baselines, given the

research conducted within IRSN;– Improvement proposals for the CPY control room.

Test of the CARMELAprogramme for studying

the combustion of electric cabinets.


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Research to improve scientific knowledgeThe propagation of a fire to adjoining premises viaventilation and/or the openings of a fire started ina close and ventilated room.The DIVA facility was set up in 2002 to improve know-ledge on the propagation of hot gas or particles toadjoining premises of a burning room, via the ventilationsystem and the other communicating channels (doors,openings,etc.). This facility houses three rooms leadinginto a common corridor. A fourth room is used to studythe propagation to the upper stages. The premises areconnected by doors, for which leakages may be calibrated,and by an industrial-type ventilation network. The firsttests took place in 2002 and their interpretation is inprogress.

The solvent fires in the storage cells of theCOGEMA plant of La Hague (Manche).The FLIP (Liquid fuel fires interacting with a wall) testprogramme was conducted between 1996 and 2002 incollaboration with COGEMA. It concerns the developmentof a pool solvent fire (hydrogenated tetrapropylene-tributyl phosphate or TPH/TBP) that might occur in aroom dedicated to the storage of this solvent. In 2002,the focus was on the carrying out of the final tests andthe interpretation of the tests performed during theprevious years, as well as the qualification of the FLAMMES/SIMEVENT coupled code on the basis of thosetests. A summary document was drafted following thisinstructive programme (for example, on the maximumlevels and the temporal evolutions of the pressures and temperatures for different ventilation network ope-rations).

The behaviour of compartmentalisation andcontainment equipment subject to a fire.To better assess the behaviour of the compartmentalisa-tion elements in case of fire, in particular their resistanceto pressures which may result from these, a programmewas conducted in 2002 in the STARMANIA facilityconcerning the aeraulic behaviour of fire dampers andtheir degree of mechanical resistance. Furthermore, filterclogging, which may lead to a loss of containment of theradioactive substances, in particular by breaking the filtermedium, was studied in the BANCO facility. All the testsperformed on filters were used to develop an empiricalmodel of aeraulic resistance used in the modelling of theinteraction between ventilation and fire.

Combustion mode of electrical boxes.The first tests of the CARMELA programme, conducted in2000 and 2001, were interpreted in 2002. A complemen-tary experimental campaign, CARMELA Bis, was definedand prepared in 2002 to better characterise some physicalparameters used by the model developed during theinterpretation of the CARMELA tests. The programme willbe completed in 2003 by the carrying out of combustiontests on real cabinets.

Suspension of radionuclides.In case of fire involving radioelements, these can bereleased in the form of aerosols or gas. The determinationof the suspension factors is essential to assess thereleases of radioactive materials and the radiologicalconsequences for workers and the fire fighters. Regardingthis subject, IRSN completes and improves the BADIMISdatabase concerning the suspension of particulatecontamination by different mechanisms.

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Solvent pool fire test of the FLIP (Liquid fuel

fire interacting with a wall) programme.

Starmania facility used to study the behaviour of containment and compartmentalisation equipment in case of fire.



IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 45

Non-proliferation of nuclear, chemical and biolo-gical weapons and protection against malevolentactions are two areas where IRSN conducts

expertise work and research. Some of its agents are also authorised to conduct inspections. It reports inparticular to the Senior Civil Servant for Defence of the Ministry of Economy, Finance and Industry.

IRSN makes its knowledge and practices available tothe French authorities and international organisationsinvolved in the implementation in France of treaties ofnon-proliferation of nuclear, chemical and biologicalweapons.

Protecting nuclear facilities and transport of nuclearmaterials against malevolent actions which may leadto radioactive releases in the environment is the aimof the struggle against malevolent actions whichbecame an even greater concern after the terroristattacks in September 2001.

IRSN lends its technical support to public authorities and to theindustrialists for the implementation in France of the internationalcontrols in the non-proliferation area. Initially, only the nuclear sectorwas concerned. Given the experience acquired by the Institute inthis area, the public authorities commissioned it to ensure the samemission for the application of the Convention on the Prohibition ofthe Development, Production, Stockpiling and Use of ChemicalWeapons and on their Destruction (CWC), signed in Paris in January1993. Lastly, since 1999, the Institute has also been involved in thearea of the non-proliferation of biological weapons.


IRSNEnsuring non-proliferation and protection against

malevolent actions

Control of nuclear materials during transport.

62In 2002, IRSN performed 62analyses in the chemical areafor the Senior Civil Servant forDefence of the Ministry ofEconomy, Finance andIndustry.

50 inspections100 reportsIRSN assesses measurementsby operators to protect theirfacilities and nuclear mattercontained in these. Within this framework, the Instituteperformed 50 inspections and transmitted 100 advisorreports to the Senior CivilServant for Defence in 2002.

> Non-proliferation of chemical weapons

IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 46

ACTIVITIES

The Convention on the Banning of Chemical Weaponsentered into force in France in 1997. Since this date, theInstitute has provided expertise and undertaken technicalsupport missions requiring scientific and legal competen-cies, focusing on three activities:

Technical support to the authorities forinternational negotiations and for theimplementation in France of the Convention in the civil sector.The Institute carried out the census of industrialistsconcerned by the Convention, who must declare theproducts they use. It analyses and processes their decla-rations.

Concerning the international relations, in 2002 IRSNparticipated in the expert group implemented by theOrganisation for the Banning of Chemical Weapons, on the homogenization of the declarations. This resulted in November 2002 in defining rules and declarationthresholds for imports and exports of the chemicalproducts concerned, common to all convention signatorycountries. This will imply a change in the French regulatorytexts, manuals and declaration forms. The related workwas launched in 2002.

Advice to industrialists for preparing the declarations and international controls.IRSN advises industrialists for preparing declarations,taking into account the characteristics of their facilities.

Preparatory visits before international inspectionsrepresent for IRSN educational work to the industrialists.The purpose is to make them aware of the provisions ofthe legislative and regulatory Convention texts and of theconsequences for facilities: check of declarations, frequencyof inspections, access of inspectors to “sensitive” areasand information for the economic development of thecompany. IRSN performs preliminary visits of the sites inorder to facilitate the process of the inspections proper. In 2002, the Institute performed 18 preliminary visits.

Supporting the international inspectionsPerformed by the OPCW, the purpose of the inspections isto check the compliance of the information transmittedby the French authorities in the declarations. Duringthese inspections, IRSN, as French state representative,plays a role of interface between inspectors and indus-trialists. The sites inspected are chosen by the OPCW frominformation provided in the declarations.

Until 2000, most of the inspections conducted in theworld concerned the main industrialised countries. Thisrepresented 20 inspections for France. In April 2000, theinspection was extended to all organic chemical products,significantly increasing the number of countries involved.After facing some financial difficulties, the OPCWcontinued as before with the same sustained inspectionpace as of the fourth quarter of 2002.

MONITORING OF TRANSPORT FOR SENSITIVE NUCLEAR MATERIALS

The Transport Operational Echelon (EOT) was createdin 1983 within the Institute to assume operationalresponsibilities in the area of the management andmonitoring of transport of nuclear materials.

Within this framework, every year it examines almost2,000 transport authorisation requests and ensuresthe monitoring of these transports on the nationalterritory.

This involves road, rail, sea or air transport (from or toa port or airport under French jurisdiction).

The monitoring of each transport is in keeping withthe sensitivity of the materials transported. Sometransports, among the most sensitive, follow routesauthorised by the Senior Civil Servant for Defence of the Ministry of Economy, Finance and Industry andare monitored in real time by IRSN, with satellitecommunication means.

This monitoring allows any incident, accident or eventto be detected which may delay or hinder thetransport. In such cases, the EOT takes appropriatemeasures: information to authorities, initiation ofemergency of physical protection actions, transportstop, route change, etc.

In addition to transport monitoring, the agentsauthorised by the EOT conduct unannouncedtransport inspections, in order to ensure thecompliance of the regulatory provisions. Crossingconditions for highway tolls and borders, receptionand parking conditions of convoys, locking andmonitoring of vehicles during stopovers, etc. Morethan 40 inspections are conducted every year, inharbours, stations, borders and airports or nearinstallations authorised to have nuclear materials.Control of nuclear materials

during transport.

[ NON–PROLIFERATION AND PROTECTION AGAINST MALEVOLENT ACTIONS ]


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ACTIVITIES

One of the Institute’s missions is to assess themeasurements taken by the industrialists to

protect their facilities and the transports of nuclearmaterials against possible malevolent actions whichmay cause releases of radioactive products in theenvironment. Of course, the results of those assess-ments remain highly confidential, but the terroristattacks of September 2001 reinforced the concern ofpublic authorities in this area.

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

– The assessment of the sensitivity of the various facilitiesand equipment. Sensitivity is characterised by thesignificance of the consequences which may resultfrom a malevolent action, i.e. quantities of radioactiveor chemical products which may be released in theenvironment;

– The assessment of the vulnerability of the equipmentconsidered sensitive, i.e. the assessment of the difficul-ty to launch a given attack on this equipment;

– The research, if necessary, of complementary provisionsused either to reduce the equipment sensitivity or tomake a possible attack more difficult.

Several typical threats have been defined: their relevancyis subject to a comparison with the lessons drawn fromevents having occurred in France or abroad, possibly in

other industrial sectors outside the realm of nuclear acti-vity. Those events are compiled in a record of malevolentactions, drawn up by the Institute. In 2002, suggestionswere made by the Institute to harden the typical threats,in particular by taking into account the lessons drawnfrom the attacks of September 11th, 2001. Furthermore,IRSN also suggested to the authorities draft regulatorytexts aiming at reinforcing and specifying the regulations.

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

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

Lastly, the Institute conducted experiments and studieson the assessment of damages to buildings, storageponds, and ventilation systems in case of malevolentactions.

> Protection against malevolent actions


Transport of casks of spent fuels.

Digital simulation of an explosive

detonation.

48

IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 48

Malevolent actions against transports of nuclear materialsIRSN conducted research, in particular concerning theresistance of packing to terrorist attacks. The purpose ofthis work is to have tools to assess the consequences ofsuch attacks, to be able to suggest appropriate technicalor regulatory developments. If the packing designresulting from the application of the safety regulationensures a certain degree of defence and if various testswere performed in the past, the approach adopted todayis more systematic with the use of digital simulation. It isintended to focus on the tests to be performed and tomake better use of these.

Since 2000, IRSN has been developing a programmeintended to study a representative assembly of packingsubject to various types of weapons (firearms, high explo-sive charges, antitank weapons, etc.). The related work isjointly conducted with the DGA and the CEA.

In the area of explosive charges, 2002 saw the completionof tests for a first packing, with the validation of associateddigital models.

Concerning perforating charges, a study was conductedin 2002 for this same transport packing and showed thatthe results from the digital simulation were consistentwith the results from experiments.

Concurrently, collaboration was launched with the UnitedStates, the United Kingdom and Germany concerning the possible radiation consequences of an attack of atransport of irradiated fuels with a perforating charge.

STUDY OF IMPACT OF AN AIRCRAFT ON A POWER PLANT

Following the attacks of September 11th, 2001, IRSNperformed a study on the mechanical behaviour ofthe containment of a nuclear power plant in 2002modelling in detail an attacker using a commercialaircraft of currently in operation and consideringdifferent trajectories and speeds as well as differentimpact points.

The attacker model was made with the efficient assis-tance and collaboration of the aircraft manufacturerwhich had models that needed to be adjusted to takeinto account the differences between a frontalcollision and a landing crash. The important aircraftcharacteristics, such as the various masses of theirdistribution, the mechanical behaviour of the differentparts of the aircraft and their connections, as well asspecific engine behaviour were taken into account.

The study conducted by IRSN provides information onthe ultimate containment capacities, regarding bothassembly stability and perforation possibilities, andmaterial needs due to the collapse of the wholefacility.

Digital simulation of an explosive detonation. Transport of packing and spent fuels.

[ NON–PROLIFERATION AND PROTECTION AGAINST MALEVOLENT ACTIONS ]


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 49

> An internationally-oriented Institute

T he purpose of the partnership between differentcountries is to pool resources, enrich knowledgeand share competencies. It supports synergies

between research and expertise.

In the areas of safety, radiation protection or security,the international openness of IRSN has grown overtime. This activity is organised along three lines:deepening scientific and technical knowledge, partici-pating in the creation of guides, recommendations orstandards and supporting the reinforcement ofnuclear radiation protection, safety and securityabroad.

Deepening scientific and technical knowledgeBy increasing knowledge, completing available tools, in particularcomputer codes and improving methods, international co-operationdeveloped by IRSN in the areas of research and expertise contri-butes to better assess risk and improve control. Discussions andwork are conducted within the framework of bilateral or multi-lateral co-operation agreements or programmes launched byinternational bodies and these lead to conclusions which may besubject to international consensus.


IRSNPromoting international relations

Construction of the new “dry” storage facility of irradiated fuels on the Chernobyl site.

29IRSN projects with safety or radiation protection organisations in 29 countries.

ArgentinaBelgiumBrazilBulgariaCanadaChinaCroatiaCubaCzech RepublicEgyptFinlandGermanyHungaryIndiaItaly

JapanMoroccoPortugalRepublic of BelarusRussiaSlovak RepublicSloveniaSouth KoreaSpainSwedenSwitzerlandUkraineUnited KingdomUnited States

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ACTIVITIES [ INTERNATIONAL RELATIONS ]

Active participation in international programmesFor the Framework Programme (FP6) of the EuropeanAtomic Energy Community (EURATOM) for research andtraining activities, 2002 was a transition year with thecontinuation of FP5 and the launch of FP6.

For the 5th PCRD, IRSN contributed significantly in 2002to almost twenty projects: in the area of severe accidents,achievement of COLOSS (European project dedicated tothe study of the core damage during a severe accident)and ENTHALPY (European base of the corium thermo-dynamic data); continuation of BIODOS, related to theradiation protection of workers and the public (dosimetricmodels), ICHEM (study of iodine behaviour in a reactorcontainment), BORIS (study of the migration of radio-elements in the soil).

With the FP6, the European Commission suggested acompletely different approach whereby the Europeanresearch space structur implies that organisations joinforces in networks of excellence, with long-term commonmeans and strategies, or implement wide integratedprojects. IRSN has become strongly involved in thisapproach: the implementation of the SARNET network of excellence on the core meltdown accidents in apressurized water reactor (PWR) is the first example ofthis sort.

Lastly, within the framework of the EURADOS (EuropeanRadiation Dosimetry Group) work, co-financed by theEuropean commission, an intercomparison exerciseregarding radiation dosimetry in the environment wasconducted in 2002. During the year, IRSN was presidedthe EURADOS association, which brings together over 30 European organisations around two main objectives:to make progress in ionising radiation dosimetry and topromote the development of methods in this area.

Among major international programmes, IRSN continuedin 2002 the Phébus programme in which 35 organisationsparticipated and the Cabri-Water loop programme, a wide international co-operation scheme supported by the OECD. It took part in the launch of the MCCI programme (study of the molten core flow out of thevessel and interactions with containment concrete) bringing together 13 OECD countries.

Development of bilateral collaboration2002 was the year for the renewal of the generalagreement between IRSN and the JNC (Japan NuclearCycle Institute) and negotiations for the renewal of thegeneral agreement with the JAERI (Japan Atomic EnergyResearch Institute). The latter will deal in particular withthe release of fission products during a severe accidentand the criticality risks in fuel cycle installations.

Furthermore, co-operation with Russian research institutes,IBRAE (Nuclear Safety Institute of the Russian Academyof Sciences) and Kurchatov, continued in 2002 aroundcomputer codes concerning severe accidents, and thenegotiation to reach an agreement with the Belgian‘Association Vinçotte Nuclear’ (AVN) was initiated.

Lastly, negotiations were conducted with the Bulgarian,Slovenian and Romanian organisations for their partici-pation in the Phébus FP programme.

In the radiation protection area, a co-operation agree-ment was signed in December 2002 between IRSN and the Cuban CPHR (Centro de protección e higiene de lasradiaciones). Initial co-operation issues concern theimpact of the Chernobyl accident on health, the assess-ment of the impact of radioactivity on the environment,the treatment of people accidentally overexposed and the measurement of low-level radioactivity.

2002 was also a year for the reinforcement of collabo-ration between IRSN and Russia (Institute for Bio-physics,Moscow, and Medical Radiological Centre, Obninsk). A new wave of co-operation was launched in 2002 withthe IBRAE Institute in the radio-ecology area (CITRAMEproject).

Taking part in the development of guides,recommendations or standards of nuclearradiation protection, safety and securityThis activity is based on IRSN expertise and aims atdeveloping documents intended, for the most part, toguide nuclear actors in their practices.

In this area, IRSN participates in the work of consultativegroups, committees and working groups from the IAEA,AEN, UNSCEAR, ICRP and the European Commission…


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ACTIVITIES

Promoting the reinforcement of radiationprotection, safety and security abroadThe safety of nuclear facilities in some foreign countriesis a major issue of IRSN international co-operationregarding expertise. The purpose is to promote, throughconcrete collaboration, to the reinforcement of thecompetencies in the concerned countries.

Within this framework, Eastern European countries arethe subject of several collaborative projects and most ofthese are conducted in close co-operation with theGerman GRS. They particularly result in the carrying outof assessments, the implementation or development ofregulatory systems, initiation to the use of computercodes and their transfer. In particular, IRSN participatedin the launch of the international review project of thesafety report of the unit 1 of the Russian power plant in Kursk in 2002. It took part in the implementation of the projects related to the definitive shutdown of theChernobyl nuclear plant, reactors 1 and 2 of Kozloduy(Bulgaria) and the Ignalina (Lithuania) reactor 1, thereduction of the risks that the current sarcophagi mayhave induced, as well as the overall improvements to theUkrainian nuclear power plants, to the MetzamorArmenian plant and to the Ignalina reactor 2.

In Ukraine, a bilateral agreement signed with theUkrainian technical safety organisation (State Scientificand Technical Centre) resulted in 2002 in the launch ofcommon work on waste management, training andsafety studies. The purpose is to compare the practicesand regulations in France and the Ukraine.

Among the events in 2002, the launch in June, during theG8 summit in Kananaskis (Canada), of the “G8 internatio-nal partnership of the non-prolifera-tion of weapons of mass destructionand related materials” led publicauthorities to request IRSN to work onthe areas of securing of nuclear materialsand radioactive sources in the RussianFederation.

In Georgia, following the accidentwhich occurred in December 2001 inLia, where 3 inhabitants were severelyexposed to radioactive sources, IRSNperformed complementary expertise

on one of the patients in 2002: dosimetric reproductionand mapping of the dose received at the level of the skinarea to be transplanted. This expertise was carried out tosupport the medical management of the victim treated inthe Army Hospital of Percy (Haut-de-Seine).

It should be noted that currently relations between IRSNand its partners (safety and radiation protection technicalorganisations, research organisations, etc.) in EasternEurope are developed towards more regular co-operation.IRSN promotes those changes as well as the exchange ofcompetencies with these countries. Thus, the Institutesupported the creation, in September 2002, of the CENS(Centre for Expertise in Nuclear Safety). This network, bringing together the safety organisations from Centraland Eastern Europe, aims at reinforcing expertise capacitiesin these territories.

Beyond Europe, the reinforcement of the co-operationwith China gave rise in 2002 to the adjustment of Chinese needs in the SESAME crisis management system for the French-designed Daya Bay and Ling Aoplants, as well as to many exchanges in the areas of theprotection and fire fighting, the safety of experimentalreactors, etc.

With India, the co-operation agreement between IRSNand the BARC (Bhabha Atomic Research Centre) wasextended to cover radiation protection. Moreover,exchange concerned the application of accidentcomputer codes for safety studies related to Indian powerreactors.


Indian Delegation at IRSN.

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[ INTERNATIONAL RELATIONS ]

Co-operation between IRSN and the GRS (Gesell-schaft für Anlagen und Reaktorsicherheit) began

in 1989 with the signature of a first partnershipagreement, reinforced in 1998 with the creation of aboard of directors bringing together the executivesof both institutes. The numerous joint actions,conducted for over 10 years, have contributed todefine the basis for a European approach to nuclearsafety issues.

The main actions conducted in 2002 – The implementation of the FGI (French-German initiative

for Chernobyl), programme intended to gather, in theform of databases, the technical information availableon the consequences of the Chernobyl accident, in theUkraine, Belarus and Russia, focusing on three issues:sarcophagi safety, transpor of radioelements in theenvironment and public health. These databases will bemade available to public authorities, scientists andpublic.

In 2002, the sarcophagi safety database assessment was prepared for its integration into the internationaldatabase financed by the EBRD (SIP project) within theframework of the construction of the new sarcophagi.Concurrently, the radioecology programme was com-pleted when the radioecological data was integrated inthe REDAC (Radioecological Database after Chernobyl)common database. Furthermore, the “health” aspect ofthe project is proceeding, with the monitoring of long-term effects of the accident on the population. Lastly,the development of an Internet site displaying thegeneral results obtained in the three areas is in progress;

– Co-operation for improving the safety of the EasternEuropean nuclear plants carried out through Riskaudit,an IRSN/GRS subsidiary, and in collaboration with theother European safety technical organisations, withinthe framework of the PHARE and TACIS Europeanprogrammes and the EBRD projects;

– Continuation of the common development of the ASTECcomputer code modelling core meltdown accidents;

– Continuation of the co-operation concerning theexpertise of the EPR PWR project;

– Development of the EUROSAFE project, intended topromote the future creation of a European expertisepool for nuclear safety: in 2002, the fourth EUROSAFEforum, an annual scientific and technical internationalevent, gathered just under 500 participants in Berlin(Germany). 50 scientific and technical presentationswere presented during this exhibition. The EurosafeTribune, a magazine distributed to all forum guests waslaunched in 2002.

Lastly, an Internet site in French, German and English(www.eurosafe-forum.org) has been set up to informparticipants on the reflections and work conducted by safety and radiation protection organisations. The implementation of the EUROSAFE approach isconducted by a programme committee comprising 6European safety and radiation protection organisations:AVN (Belgium), CSN (Spain), GRS (Germany), HSE(United Kingdom), IRSN (France), SKI (Sweden). In 2002,the EUROSAFE approach was financially supported bythe European Commission. This resulted in reinforcingits European dimension.

Concurrently, the year 2002 saw the reinforcement ofAVN/GRS/IRSN co-operation. A first tripartite meetingheld in December in Brussels (Belgium) to reinforce co-operation within the organisation, safety assessmentmethods and safety re-examination. It focused primarilyon the assessment of organisations, the quality of theexpertise according to the new AFNOR standard and safety re-examination.

> Close co-operation between France and Germany


The EUROSAFE Tribunemagazine was launched

in 2001 by IRSN and the GRS, its German partner.

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

IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 53

Communication and information are part of the Institute's missions. To carry out these missions, a commu-nication department was created in 2002. Its purpose is to position the Institute as an expertise and

research organisation in the area of prevention and management of nuclear and radiological risks.

IRSNSupporting information and training

Information missionThe Institute supports information on the risk andprevention of nuclear and radiological risks. It thereforesupports the development of a culture regarding risk inFrance. IRSN takes part in societal debates dealing withthese issues, while listening to and taking into accountpublic expectations regarding information.

Actions in 2002 targeting specific segments of public opinion “Keeping a close watch on nuclear energy” targetingthe general public.For over 15 years, the travelling exhibition “Keeping a closewatch on nuclear energy” has been presented to the generalpublic and more particularly to schools. The purpose is toinform people on the risks related to nuclear power and onthe measures taken to control these. It is organised by IRSNand DGSNR, in collaboration with local authorities. In2002, it was presented in Blois, Bordeaux and Dijon andattracted over 10,000 visitors. Furthermore, the collectionof IRSN booklets was extended in 2002 with a publicationon radioactive waste.

Towards elected officialsWith the organisation in January 2002 of a third day ofinformation on the risks related to radon, IRSN and the

Ministry of Health extended their information actions tolocal representatives.

The participation in the « Salon des maires de France »exhibition was also the opportunity to heighten awarenessof those risks among France's 36,000 mayors , in particularby distributing a letter-statement entitled “Le radon enquestion”.

Annual meetings with health, environment and safe-ty professionals. The presence in professional forumssuch as Medec (March 2002) and Pollutec (November2002) are opportunities for the Institute to discuss withprofessionals and inform them. In the same way, theEUROSAFE forum, the European forum for safety profes-sionals, is an exemplary partnership between IRSN andGRS. Its implementation is conducted by a programmecommittee comprising 6 European safety and radiationprotection organisations. It is intended to promoteEuropean convergence in terms of safety practices.

For the scientific community, several scientific mediawere developed in 2002: – The first scientific and technical report of IRSN, with

3,500 copies distributed in France and abroad;

> Communication based on transparency and education


IRSN exhibition at the “Salon des Maires” forum.

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ACTIVITIES [ COMMUNICATION AND TRAINING ]

– The Internet site dedicated to the scientific publicationsof the Institute;

– A new document in the scientific collection: « Collectivedose – Indications and Contraindications ».

The relations with the media are intended to provideinformation, either related to current events or tosubstantive issues. In 2002, in addition to support for theprogrammes and actions of the Institute, this activityfocused on the creation of IRSN, Chernobyl 16 years after.

Internally, supporting the creation of IRSNIn 2002, the internal communication launched a reflec-tion process on the values of the new Institute withinworking groups, with the intention being to achieve ashared vision of IRSN values. A survey was conducted onpersonnel expectations, based on a representative sampleof the people in the Institute.

> Training

INTERNET: REAL-TIME INFORMATION The IRSN Internet site (www.irsn.org) was set up atthe beginning of 2002. At first, it was designed as aninstitutional site introducing the new Institute, and ithas gradually integrated the contents of the IPSN andOPRI sites, enriched with new pages and a more user-friendly new home page .A new site dedicated to IRSN research and scientificpublications was launched in 2002. It gathers thereferences for articles, conferences and theses,published by the Institute over the last 3 years, as wellas current or future theses, and information on theresearch teams and subjects being treated.In 2002, the IRSN site recorded 165,700 visits by44,500 different visitors, including almost 9,000 forthe scientific site alone.

Participating in training through researchEvery year, the Institute receives doctoral and post-doctoralstudents in its laboratories. In 2002, autonomousmanagement of theses and post-doctoral students wasinstituted, following the creation of IRSN. The theses andpost-doctoral training applications are subjected to aprocedure to assess subjects, conducted by two expertsexternal to the Institute. This procedure is used to checkthe relevancy of the subjects, while promoting discussionsbetween Institute researchers and external experts,teachers and university professors.

In 2002, 11 theses were defended and 22 theses werestarted (including 64% co-financed by companies, localauthorities or research bursaries). On December 31st,2002 13 post-doctoral trainings were in progress,including several training programmes involving foreignstudents (North America, South America, Asia, EasternEurope, North Africa).

One of the objectives of training through research is tofacilitate the transition from the academic world to theworkplace, by enhancing the concordance betweentheses and professional ambitions. Over the last threeyears, 56% of PhD graduates and 80% of post-doctoralstudents went on to sign “open ended” contract. In 2002,a branch of the Bernard Grégory association was createdwithin the Institute, supporting researchers’ transitionfrom academia to the workplace, in particular by intro-ducing them to industry.

Similarly, the organisation of the “Formation par larecherche” days brings together almost 200 people andprovides post-doctoral students with the opportunity to present the state of progression of their work inorganised conferences.

On the IRSN scientific Internet site launched in 2002, the thesis section is among the most consulted areas. The use of the Internet to present completed theses,those in progress and proposals of subjects is highlyappreciated among applicants.

Taking part in the teaching and training effortthrough research is essential to confirm IRSN’s

mission in the area of knowledge development. Thisis also an opportunity to develop openness, both toscientific circles and universities. Over time, thisshould be an efficient means to attract young resear-chers and postdoctoral students to the Institute, thusgenerating recruitment opportunities.

Supporting teachingAs regards teaching, in addition to specific contributionsby Institute agents, IRSN actively participates in trainingin schools of engineering and universities:

– Génie atomique (INSTN, Saclay, Essonne).– DESS de radioprotection (Joseph-Fourier University,

Grenoble, Isère).– Nuclear power option at the Ecole nationale supérieure

d’ingénieurs (ENSI) in Bourges (Cher).– Nuclear and technologies in association option with the

École des mines de Nantes (Loire-Atlantique).– DESS Sciences des aérosols, génie de l’aérocontamina-

tion (University of Paris-XII, Val-de-Marne).

In some cases, partnership agreements have been signed,providing research programmes and reception of trainees.In 2002, agreements were signed with the Joseph-FourierUniversity, the ENSI of Bourges (Cher)., the University ofCaen (Basse-Normandie), the University of Paris-XII (Val-de-Marne) and the University of La Rochelle (Charente-Maritime).


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 55

Proceeding with quality objectivesThe Institute’s partners count on IRSN as an orga-

nisation recognized in the area of the nuclear andradioactivity-related risk assessment, and expect himto prove that its technical and organisational capa-cities enable it to ensure the quality of its activities.

In keeping with this expectation, the SEQUOIAproject was launched in 2000, as a transversal andambitious project for which the first significantstage is the certification of expertise activitiesscheduled for 2004.

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

SEQUOIA, a federative projectThe purpose of the project is to achieve better control ofall IRSN activities and their interaction: realisation of “products” (expertise, research, studies, etc.), manage-ment and support (purchasing, sales, human resourcesmanagement, documentation, etc.).

After a diagnostic phase which confirmed the opportunityand the need for a project of this sort, the followingphase defined the specifications of the future Qualitymanagement system, its scope, identification of the mainprocesses, quality organisation and the method to be

used to upgrade the quality system. In this phase, theactions have been conducted to cover all technical activitiesof IPSN and OPRI, launched with the creation of IRSN.

The upgrading itself began in 2002. Based on a partici-pative approach, it calls upon thematic groups, eachdedicated to the study of a process and including profes-sionals involved in each process. The co-ordination of thisproject and the thematic groups are supported by an out-side service supplier contributing acquired experience onprojects of this sort.

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

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

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

ACCREDITATIONS (ISO 17025 STANDARD)

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

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

Measurement laboratory for environmental radioactivity (Orsay, Essonne).

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

Study laboratory for contamination, purification and ventilation transfers (Saclay).

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

Calibration of instruments used in neutron dosimetry.

Calibration of instruments used in photon dosimetry.

Analysis of radionuclides present in all sample types of the environment.

Physical tests of equipment measuring air contamination by radioactive gas.

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

Analysis of radionuclides present in all sample types of the environment.


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QUALITY AND DEVELOPMENT MEANS

A policy in favour of accreditationIn 2002, IRSN defined a clear policy in favour of accredi-tation of its test and calibration activities, particularlywhen:– Results need to comply with regulatory or contractual

requirements;– Results constitute an undeniable reference;– Results are used to conduct expertise activities.

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

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

Certification in IRSNWithin the framework of the SEQUOIA project, the pur-pose of IRSN is to obtain certification for all of its activi-ties. Certification and certification renewal approacheswere conducted by units intervening in specific areas orto meet originators’ requirements.

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

Technical Centre for the Approval of RadiologicalProtection Instrumentation (Saclay).

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

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

– Acceptance and control of high efficiency filtersand iodine traps of nuclear facilities.

– Acceptance of absorbing samples of the purificationsystems for radioactive gaseous effluents.

– Measurement of radon in the environment andbuildings.

[ QUALITY ]

CERTIFICATION (2000 VERSION OF ISO 9001 STANDARD)


Gamma spectrometry laboratory (left) and benzene synthesis laboratory (right):

two accredited IRSN activities.

IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 57

Human resources and labour relations: supporting the implementation and the development of IRSNSince its creation in February 2002, IRSN has

exercised its responsibilities as an employer,previously assumed by the CEA and by OPRI. Thisstructured 2002 activities around three issues: – The administrative acts necessary for the exercise

of the employer responsibility and employees’personal management;

– Representative personnel authorities;– Management procedures and tools.

Within this context, it is essential to create an attractiveenvironment so that employees who participate in the development of the new Institute find convincingreasons to pursue their career, including those employeesmade available to IRSN by the CEA and employees whobenefit from the status of established civil servants.

At the time of the creation of the IRSN, over half of theemployees contributing to IRSN activities were employedby the CEA (800 persons) and 200 were employed by theformer OPRI or were civil servants. According to theprovisions of the decree dated February 22nd, 2002, CEA employees made available to IRSN have a three-yearperiod from the date of implementation of the decreeduring which they may express their desire to pursuetheir career in the CEA or choose IRSN status.

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

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

the basis of the provisions of the CEA labour convention,appropriate to the environment, size and activities of theInstitute.

This project mobilises, both General Management, whichconsiders it as a central aspect of the human resourcesmanagement of the company, and Human ResourcesManagement, which provides its experience and logisticalsupport to the numerous meetings held on this issue. Thiswork was particularly useful to propose and negotiatedevelopments in the structure and general economicconditions for wage increases and advancement time-tables of non-management employees.

The end of the year was dedicated to the preparation ofthe election of personnel representatives for the variouslegal and conventional authorities which will be directlyconcerned by the quality of the dialogue and discussionsbetween employees and management.

To offer career opportunities to employees beyond IRSNactivities, conditions of mobility between the CEA andIRSN were discussed and resulted in a draft conventionbetween both organisations, transmitted to the concer-ned ministries and to the Ministry of Budget, as providedfor in the decree of February 22nd, 2002. The conventionis intended to encourage exchanges of skills to mutuallyenrich the organisations and offer career opportunitiesfor employees from both bodies. The same type of agree-ment will be developed with other organisations speciali-sing in areas related to IRSN activities. On December 31st,2002, 43 IRSN employees were made available to otherorganisations, including the DGSNR.

Development and control of managementprocedures and toolsIn terms of compensation policies, the payroll packageadopted by the Institute was structured to take intoaccount the diversity of personnel statuses and it hasbeen operational since the end of February 2002.

Over 17 different status categories are managed by thedepartment responsible for this activity.

This structure and its management have been and remaina demanding activity with significant dedicated resour-ces. In Human Resources management, all employees and


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QUALITY AND DEVELOPMENT MEANS [ HUMAN RESOURCES AND LABOUR RELATIONS ]

managers are constantly dedicated to meeting the justi-fied expectations of every employee to receive wage slipswithin deadline.

The IT system was also improved so that fees for missionscarried out are paid as soon as possible and in compliancewith the current regulatory provisions.

Permanence and quality of personnel administration activities and the exercise of employer’s responsibilitiesIn addition to the projects linked to the implementationof the new Institute, Human Resources managementcarried out its basic missions so that laboratories andsupport units continue to have the means required toachieve their operational objectives. It therefore contri-buted by recruiting 150 people, by establishing andmanaging 266 files of temporary employees hired tosupport the various teams, by conducting inductionoperations such as the reception and training of newrecruits. Management of professional travel was ensuredfor France and abroad (more than 8,700 missions treatedand finalised in 2002).

In the training area, the activity represented a budget of€1.4 million in 2002, i.e. 6,000 training hours in threeareas: scientific and technical topics (70%), languagesand office process modernisation.

In 2002, IRSN received 120 trainees, including 70% intheir fifth year of university studies or completing anengineering school. Besides, about twenty foreign contri-butors were received for a stay of six months on average.These trainees come mainly from the Institute's partnerorganisations and follow training within the frameworkof IRSN international agreements.

Among the employer’s duties, the relations with all labourorganisations and administrations intervening in theregulation and control of EPICs (Public establishments ofan industrial and commercial nature) have been defined.The production of legal and regulatory information hasbeen implemented and is now subject to presentations ona regular basis.

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

1,437 workstations.

66% of employees with management status:engineers and management personnel.

34% of employees have non-management status:technicians, administrative and logisticssupport personnel.

42% of employees work directly for IRSN (602 persons).

58% of professionals are made available to IRSN by the CEA (835 persons).

700 IRSN pay slips are produced every month.

6,000 training hours were dispensed in 2002.

8,700 missions were completed.

120 trainee files were processed.

Personnel representatives and trade unionrepresentatives in the Works Committee were elected on January 23rd, 2003 (first round) and on February 6th, 2003 (runoff).

Meetings related to IRSN organisation held throughout the year 2002.

Every year, IRSN receives doctoral and post-doctoral students. Almost 50% of post-doctoratal graduates were hired

by IRSN lasting recent years.


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 59

IRSN 2002 budget

IRSN was created in 2002 as an EPIC (ÉtablissementPublique à Caractère Industriel et Commercial), a specificFrench status for public institutions with industrial and commercial activities, supervised by a designatedaccountant. This resulted in changes in the Institute’s taxobligations and necessitated the implementation of neworganizational, management and accounting tools tocomply with this new status.

This change in status immediately impacted two areas ofthe financial reporting system:– Forecasting was established on the basis of a 12-month

period, but operations were carried out over a 10-monthperiod;

– Documents were presented in the M9-5 standardaccounting format.

The Institute’s total revenues totalled €214.5 million,with 83% being provided by the French Ministry for theEnvironment and Sustainable Development. The remainder,i.e. 17%, was generated by services provided to thirdparties or through mutually-financed programmes, inparticular with EDF and COGEMA.

Expenses for operating costs amounted to €200.4 million,with only €25,120,486.08 in personnel costs. This lowlevel is due to the fact that the majority of employeesformerly with the IPSN are still employed by the CEA,which invoices their cost to the Institute.

The transfer of OPRI and IPSN assets has not yet beenfully completed and therefore these accounting entriesare not included in the IRSN balance sheet. Similarly, no depreciation write-offs have been entered into the2002 annual accounts.

The balance between revenues and expenses amounts to€14.1 million in underlying earnings, providing nearlycomplete organic coverage of investments, which standat €14.7 million for the fiscal year.

In operational terms, the overall balance in workingcapital was reduced by €0.7 million.


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QUALITY AND DEVELOPMENT MEANS [ IRSN BUDGET ]

1 – RECONCILIATION SUMMARY OF ESTIMATES AND REALISATION

A – Profit & Loss account (in millions of euros)

Costs Revenues

Profit & Loss account E R E R

Personnel costs 106.0 25.1 38.5 34.6 Sales: Provision of services

241.8 178.5 Public subsidies

Other operating costs 154.7 175.3 0.1 1.4 Other operating revenues

Total costs 260.7 200.4 280.4 214.5 Total revenues

Earnings (Profit) 19.8 14.1 — — Negative earnings (Loss)

Total balance on Profit & Loss account 280.4 214.5 280.4 214.5 Total balance on Profit & Loss account

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


Costs Revenues

E R E R

Cash Inflow 19.8 14 Cash Outflow

Acquisitions of tangible 19.8 14.7 Public investment subsidiesand intangible assets

Long-term investments Other resources (excluding internal transactions)

Total employees 19.8 14.7 19.8 14 Total resources

Contribution of working capital 0.7 Deduction from working capital

Total balance of table 19.8 14.7 19.8 14.8 Total balance of table


B – Cash flow (in millions of euros)

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

Capacity Deficit

E R E R

Earnings (Profit) 19.8 14.0 Negative earnings (Loss)

+ Book value of assets sold – Revenues from assets sold+ Appropriations to amortisation 0.0 0.0 – Revenues from amortization + and provisions – compensation

– Share of subsidies transferred – to earnings

– Adjustments to amortisation and provisions

Subtotal 19.8 14.0 Subtotal

Cash Inflow 19.8 14.0 Cash Outflow


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2 – PROFIT & LOSS ACCOUNT

A – Income (in millions of euros)

Earnings (before taxes) Financial Year 2002 (10 months)

Operating earnings 213.5

Sales of merchandise

Production sales• Work• Provision of services, studies & activities 34.7

Net turnover 34.7

Closing stock• Production in progress• Services in progress• Revenues

Capitalized production

Operating subsidies 178.6

Adjustments to amortisation and provisions

Transfers of liabilities 0.1

Other revenues 0.1

Investment earnings 1

From holdings

Other securities of fixed asset receivables

Other interest and similar earnings

Adjustments to provisions and transfers of financial liabilities

Positive exchange rate differences

Net income on transfers of investment securities 1

Exceptional earnings 0

On management transactions

On capital transactions • Earnings from asset transfers• Investment subsidies transferred to the year’s Profit & Loss Account • Others

Amortisation compensation

Adjustments to provisions and transfers of non-recurrent liabilities

Total earnings 214.7

Debit balance = Loss

OVERALL TOTAL 214.5


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B – Liabilities (in millions of euros)

Liabilities (excluding taxes) Financial year 2002 (10 months)

Operating liabilities 200.5

Purchase costs of merchandise sold during the year• Merchandise purchases• Fluctuation in merchandise stocks

Costs related to third parties• Purchases of supplies in hand

– Raw materials– Work– Others (studies, services)

• Fluctuation in stock of supplies

• Subcontracting costs 29.1

• Purchases of equipment & supplies not in stock 19

• External services 123.8

Taxes and similar payments – Remuneration costs 0.6– Others 2.9

Personnel costs – Wages & salaries 17.7– Social security charges 7.4

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

Other liabilities

Investment liabilities 0

Appropriations to amortisation and provisions

Interest and similar liabilities

Negative exchange rate differences

Net liabilities on transfers of investment securities

Non-recurrent liabilities 0

On management transactions

On capital transactions• Accounting value of transferred fixed and funded items• Other

Appropriations to amortisation and provisions• Appropriations to regulated provisions• Appropriations to amortisation and other provisions

Total liabilities 200.5

Credit balance = Profit 14

OVERALL TOTAL 214.5

[ IRSN BUDGET ]


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3 – BALANCE SHEET

A – Assets (in millions of euros)

ASSETS Financial Year 2002 (10 months)

Gross Amortisation Netand provisions (to deduct)

Fixed assetsIntangible assets

Initial costsR&D costsConcessions, patents, licences, brands, processes,

software and similar duties and costs 1.3 1.3GoodwillOthers

Intangible assets in progress 0.1 0.1Advances and deposits

Tangible assetsLandBuildings & structures 0.8 0.8Technical installations, equipment and plant 4.8 4.8Others 3.1 3.1

Tangible assets in progress 4.6 4.6Advances and deposits

Investment assetsHoldingsReceivables related to holdingsOther fixed securitiesLoansOthers

Total (I) 14.7 0 14.7

Current assetsStock and work-in-progress

Raw materials and other suppliesProduction in progress (goods & services)Work in progressSemi-finished & finished productsMerchandise

Advances & deposits on orderss 27.6 27.6

Operating receivablesClient receivables & connected accounts 35.7 0.1 35.6Others 54.9 54.9

Miscellaneous receivables Investment securities 47.1 47.1SharesOther securitie Liquid assets 0.3 0.3

Deferred charges Prepayments

Total (II) 165.6 0.1 165.5

Charges to be allocated over several financial years (III)

Loan redemption premiums (IV)

Assets translation variance (V)

OVERALL TOTAL 180.3 0.1 180.2


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 64

B – Liabilities (in millions of euros)

LIABILITIES Financial Year 2002 (10 months)

Shareholder Equity FundsAllowancesAddition to allowances. StateAddition to allowances (bodies other than the State)EquityOther additions to allowances. StateOther additions to allowances. Other bodiesCapital donationsVariance in revaluationReservesRegulated reservesOthersCarried forwardFinancial year earnings (Profit or loss) 14.1

Subtotal: Net equity 14.1

Investment subsidiesRegulated provisions

Total I 14.1

Contingent liability provisionsProvision for risksProvision for liabilities

Total II 0

DebtsFinancial debtsDebenture loansLoans & debts from credit institutionsMiscellaneous financial loans & debts – 0.2Advances and deposits received on current orders 2.4Operating debtsSupplier debts and connected accounts 84.3Fiscal & social security debts 54.8OtherMiscellaneous debtsDebts on fixed capital and connected accounts 6.8

Other debts 17.9Miscellaneous accrualsDeferred earnings 0.1

Total III 166.1

Liabilities translation variance (IV)

OVERALL TOTAL (I+II+III+IV) 180.2

[ IRSN BUDGET ]


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 65


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AgenB.P. 27 47002 Agen CedexTel.: +33 (0) 5 53 48 01 60

Angers 39, rue Joachim-du-Bellay49000 AngersTel.: +33 (0) 2 41 87 83 21

Avignon550, rue de la Tramontane, BP 70295 Les Angles 30402 Villeuneuve-lès-Avignon CedexTel.: +33 (0) 4 90 26 11 00

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ANNEXES [ SITES ]


Beaumont-Hague Rue du vieux cheminB.P. 224 50442 Beaumont-Hague CedexTel.: +33 (0) 2 33 01 05 61

CadaracheB.P. 3 13115 Saint-Paul-lez-Durance CedexTel.: +33 (0) 4 42 25 70 00

Clamart77-83, avenue du Général-de-Gaulle92140 Clamart

Mail: B.P. 1792262 Fontenay-aux-Roses CedexTel.: +33 (0) 1 58 35 88 88

Fontenay-aux-rosesB.P.17 92262 Fontenay-aux-Roses CedexTel.: +33 (0) 1 58 35 88 88

Le Vésinet31, rue de l’Écluse - B.P. 35 78116 Le VesinetTel.: +33 (0) 1 30 15 52 00

OctevilleB.P. 10Rue Max-Pol-Fouchet 50130 Cherbourg-OctevilleTel.: +33 (0) 2 33 01 41 00

OrsayBois des Rames Bâtiment 501 91400 OrsayTel.: +33 (0) 1 69 85 58 40

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

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

SaclayB.P. 68 91192 Gif-sur-Yvette CedexTel.: +33 (0) 1 69 08 60 00

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

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IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 67

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

Aerosol: Dispersion, in very fine particles (about onemicron), of a liquid or solid in a gas (air or oxygen).

AFNOR: French standardisation institute.

AFSSE: French Agency for Environmental Safety.

Alpha (α symbol): Radiation composed of helium 4nuclei, highly ionising but not very penetrating. A sheetof paper is sufficient to stop alpha radiation.

AMANDE: Accelerator for metrology and neutronapplications for external dosimetry.

ANDRA: National Agency for Radioactive WasteManagement (France).

ASTEC: Accident Source Term Evaluation Code, systemsof software developed in collaboration by IRSN and theGRS to assess the physical phenomena interveningduring an accident of core meltdown of a pressurizedwater reactor.

AVN: Association Vinçotte Nucléaire (Belgium).

BBARC: Bhabha Atomic Research Centre (India).

Becquerel (Bq): Official international unit for radio-activity measurement. The Becquerel (Bq) is equal to onedisintegration per second.

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

BIPM: International bureau of weights and measures.

BLEVE: Boiling Liquid Expanding Vapour Explosion.

BNEN: Standardization bureau for nuclear equipment.

BNI: Basic Nuclear Installation.

BNM: National metrology bureau (France).

BORIS: Bioavailability of Radionuclides in Soils.

Burn up fraction: Thermal energy produced by thenuclear fissions in a fuel mass unit. It is measured inmegawatt days per ton (MWj/t).

CCABRI: Test reactor for fuel safety used by the IRSN.

ACARMELA: IRSN research programme on fires in nuclearfacilities aimed at gaining further insight into electricalcabinet fires.

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

CATHARE: Advanced thermal-hydraulic code applied topressurized water reactors.

CEA: Atomic Energy Commission (France).

Cesium (Cs, atomic number 55): Noble, toxic metal whosecharacteristics are comparable to those of potassium.

CHU: French university hospital.

Primary cooling system: Reactor coolant system opera-ting in a closed loop, comprising a series of componentsthat ensures the circulation of water used to extract theheat given off by the reactor core.

CIREA: Interministerial commission for artificial radio-elements

CLI: Local information commission.

CNRS: French National Centre for Scientific Research(France).

COFRAC: French accreditation committee.

COGÉMA: Nuclear matter company (France).

COLOSS: European project devoted to the study of coredegradation in the event of a severe accident.

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

Core: Area of the nuclear reactor where nuclear reactionsoccur.

CRISTAL: New French criticality-safety package developedas part of a joint project between IRSN, CEA and COGEMA.It aims at assessing the criticality risk in all nuclear facilitiesand transport packages where fissile materials are used.

Criticality: Risk of uncontrolled fission phenomena infissile materials.

Criticality accident: Uncontrolled chain fission reactiontriggered in an environment containing fissile materialssuch as uranium 235 or plutonium 239.

CSN: Consejo de Seguridad Nuclear (Spain).

CTC: IRSN emergency response centre.

CTHIR: Technical Centre for the Approval of RadiologicalProtection Instrumentation.

Glossary


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 68

ANNEXES [ GLOSSARY ]

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

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

F FASSET: Framework for ASSessment of EnvironmentalimpacT.

FLAMMES: Software describing the evolution of carbo-nated product fires developed by IRSN.

FLIP: Liquid fuel fire interacting with a wall.

AFramatome: Manufacturer of nuclear steam supplysystems.

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

GGamma (γ symbol): Highly penetrating but not veryionising electromagnetic radiation, emitted during thedisintegration of radioactive elements. This type ofradiation is stopped by concrete or lead screens.

GEA: Atomic study group.

GRNC: Nord-Cotentin radioecology group.

GRS: Gesellschaft für Anlagen und Reaktorsicherheit(Germany).

GSIEN: Group of scientists for information on nuclearenergy (France).

HHAT: Human Alimentary Tract Model.

HFD: High Civil Servant for Defence.

HSE: Health and Safety Executive (United Kingdom).

IIAEA: International Atomic Energy Agency.

IARC: International Agency for Research on Cancer.

IBRAE: Nuclear safety institute of the Russian Academyof Sciences.

ICARE: Interpretation of damaged cores for water-cooledreactors: software simulating the degradation of a PWRcore during a severe accident.

ICHEM: European Iodine Chemistry Project.

ICPE: Listed environmental protection facility.

ICRP: International Commission on Radiological Protection.

IFA: French-German initiative for Chernobyl.

IFREMER: French research institute for exploitation ofthe sea.

IGR: Gustave Roussy Institute (France).

IGS: Institute of Geological Sciences.

ILL: Laue-Langevin Institute (France).

INBS: Secret basic nuclear installation.


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 69

ANNEXES

INDOS: International Dosimetry.

INERIS: National institute for the industrial environmentand hazards (France).

INSERM: National health and medical research institute(France).

INSTN: National institute for nuclear science and tech-nology.

INSU: National institute for sciences of the universe.

InVs: French health watch institute.

IPSN: Institute for protection and nuclear safety (France).

IRSN: Nuclear safety and radioprotection institute(France).

ISO: International Standards Organisation.

ISO 9001: European standard for quality managementsystems.

Isotope: Elements whose atoms have the same numberof electrons and protons, but a different number ofneutrons. They have the same name and the samechemical properties. Around 325 natural isotopes and1,200 artificially created isotopes are currently listed.

AJJAERI: Japan Atomic Energy Research Institute.

JNC: Japan Nuclear Cycle Institute.

ALLOCA: Loss Of Coolant Accident.

LTCRA: Cellular therapy and accidental radiation protectionlaboratory.

AMMCCI: Molten-core Concrete Interaction.

MEDEC: French trade fair for professionals in the healthsector.

MINEFI: Ministry of the Economy, Finance and Industry(France).

MOX: Fuels of mixed uranium and plutonium oxides.

MWe: MegaWatt electric.

ANNEA: OECD Nuclear Energy Agency.

Nuclear fuel: Fissile material (able to undergo a fissionreaction) used in a reactor to develop a nuclear chainreaction. After being used in a nuclear reactor, this isreferred to as irradiated fuel.

Nuclear materials: Materials which can be used tomanufacture an explosive nuclear device. They aredefined from their fissile (for a fission device), fusible (fora thermonuclear bomb), or fertile (capacity to producefissile or fusible materials) characteristics. French legisla-tion retains six nuclear materials: plutonium, uranium,thorium, tritium, deuterium and lithium 6 (deuterium andlithium 6 are not radioactive).

Nuclear safety: Set of measures taken at all levels ofdesign, manufacturing, operation and decommissioningof nuclear facilities to prevent accident and to limit theireffects.

OOAR: Radiation protection assistance office.

OECD: Organisation for Economic Co-operation andDevelopment.

OPCW: Organisation for the Prohibition of ChemicalWeapons.

OPERA: Permanent environmental radioactivity observa-tory.

OPRI: Office for Protection against Ionising Radiation(France).

PPCRD: Research and development framework programme(European Community).

PHARE: European co-operation programme with thecountries of Central Europe.

Phébus: Experimental reactor.

Phébus FP: Research programme devoted to the study offission product (FP) behaviour.

Phénix: 250 MWe fast neutron reactor.

PIC: Common interested programme.

Plutonium: (Pu, atomic number 94). Transuranic chemicalelement. The isotope 239 has a half life of 24,110 years.

POLLUTEC: International trade fair for environment-related equipment, technologies and services for industry.

PSA: Probabilistic Safety Analyses.

PWR: Pressurized Water Reactor.


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 70

[ GLOSSARY ]

RRadiation protection: Set of measures intended toensure the sanitary protection of people and workersagainst negative effects of ionising radiation.

Radioactivity: Property of certain chemical elements whosenuclei spontaneously disintegrate into other elementsemitting ionising radiation.

Radioelement: Natural or artificial radioactive element.

Radionuclide: Radioactive isotope of an element.

RAFT: Reactivity Accident Fuel Test, IRSN research pro-gramme developed in collaboration with EDF and JNC(Japan) concerning the safety of the fast neutron reactors.

REMORA: Study project on the Radionuclide REMObilisationin the Rhône prodelta.

REMOTRANS: REMObilisation, long distance TRANSportand Bioavailability of Radionuclides in Marine sediments.

ASSARA: Automated monitoring of aerosol radioactivity.

SARNET: Severe Accident Research Network.

SCANAIR: Computer system for the analysis of IRSNinjection reactivity accidents.

SEQUOIA: Progressive quality system, IRSN’s goal for thefuture.

SÉSAME: Accident situation progression plan and assess-ment methods. This is a computer system developed byIRSN to assess the releases produced by a pressurizedwater reactor in case of accident.

SIEVERT: Information and assessment system of theexposure to cosmic radiation during flights.

SILÈNE: An IRSN experimental reactor used for criticalityexperiments.

SIMEVENT: Ventilation simulation software developed aspart of a joint project between IRSN, SGN and COGEMA.

SIP: Shelter Implementation Plan.

SISERI: Ionising radiation exposure monitoring informationsystem.

SKI: Statens Kärnkraftinspektion (Sweden).

SSTC: State Scientific and Technical Centre (Ukraine).

STARMANIA: Station for the study of airborne contami-nation transfer and mechanical strength under incidentand accident conditions.

SYMBIOSE: SYstemic Approach for Modelling the Fate ofChemicals in BIOSphere and Ecosystems.

TTACIS: Technical Assistance for Commonwealth ofIndependent States.

Technicatome: Engineering company specialising insafety and reliability systems in severe environments.

TRANSAT: Study project on water ATmosphere TRANSfert.

AUUIAR: Ukrainian Institute of Agricultural Radiology.

Unit: Power production unit including a boiler and aturbo-generator set. A nuclear unit is mainly defined byits type of reactor and the power of its turbo-generator.

UNSCEAR: United Nations Scientific Committee on theEffect of Atomic Radiation.

U02: Uranium dioxide.


IRSN/RA2002/72 p./UK 13/11/03 15:08 Page 71

IRSN CoordinationCommunication Department

PublishingLa Clé des mots

Graphics design and coordinationAristophane agency

Production assistanceLAO Conseil

PrintingNéotypo

Photo creditsContents left page: © IRSN (top), © EDF (bottom).

Contents right page: © IRSN (top), © BERD (middle), © Thomas Gogny (bottom). Pages 5 ,7 and 8 : © Vincent Leloup.Pages 10, 12, 13, 15, 16, 17 : © IRSN.Page 18 : © Thomas Gogny.Page 19 : © Thomas Gogny (left), © Pascal Gennerat (right).Pages 22, 23 : © IRSN.

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

© IRSN Communication

ISSN : 1637-6730Registration: October 2003


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IRSN ACTIVITY REPORT

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Institut de radioprotection et de sûreté nucléaire

IRSNHead office: 77-83, avenue du Général-de-Gaulle – 92140 Clamart

Phone: +33 (1) 58 35 88 88Postal address: B.P. 17 – 92262 Fontenay-aux-Roses Cedex

Web site: www.irsn.org

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