Radium diagnosis campaign - 59327

International Nuclear Information System (INIS)

Gabillaud Poillion, Florence

2012-01-01

In line with the approaches already adopted in France during the 90's on various sites where research and/or radium-extraction activities were mostly conducted in the past, the French public authorities wish from now on to pursue their prevention and site-rehabilitation approach inherited from the French craftsman and medical sectors that used that radioelement. As a matter of fact, radium has been in use in several medical activities, notably in the initial methods of cancer therapy. Similarly, it was also used in some craftsman activities, such as the clock industry, for its radioluminescent properties, the fabrication of lightning conductors or cosmetics until the 60's. Those activities have generated various traces of pollution that have remained today. On the basis of the different inventories of industrial sites where radium may have been held or used, and notably the inventory updated by the French Institute for Radiation Protection and Nuclear Safety (Institut de radioprotection et de surete nucleaire - IRSN) in 2007 at the request of the French Nuclear Safety Authority (Autorite de surete nucleaire - ASN), French State services have potentially identified 134 sites that hosted radium-related activities in France. The radiological status of those sites is either unknown or very partially known by State services. Sites include both dwellings or commercial premises and derelict lands. The 'Radium Diagnosis Campaign' (Operation Diagnostic Radium), consists of a radiological survey carried out by the IRSN. In cases where traces of radium are detected, plans call for the implementation of precautionary measures and of a medical follow-up of the relevant populations. Lastly, radium-contaminated sites are rehabilitated by the French National Radioactive Waste Management Agency (Agence nationale pour la gestion des dechets radioactifs - Andra). That voluntary and positive approach on the part of public authorities is fully financed by public funds, and consequently

Assessment of ICARE/CATHARE V1 Severe Accident Code

International Nuclear Information System (INIS)

Chatelard, Patrick; Fleurot, Joelle; Marchand, Olivier; Drai, Patrick

2006-01-01

The ICARE/CATHARE code system has been developed by the French 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) in the last decade for the detailed evaluation of Severe Accident (SA) consequences in a primary system. It is composed of the coupling of the core degradation IRSN code ICARE2 and of the thermal-hydraulics French code CATHARE2. It has been extensively used to support the level 2 Probabilistic Safety Assessment (PSA-2) of the 900 MWe PWR. This paper presents the synthesis of the ICARE/CATHARE V1 assessment which was conducted in the frame of the 'International ICARE/CATHARE Users' Club', under the management of IRSN. The ICARE/CATHARE V1 validation matrix is composed of more than 60 experiments, distributed in few thermal-hydraulics non-regression tests (to handle the front end phase of a severe accident), numerous Separate-Effect Tests, about 30 Integral Tests covering both the early and the late degradation phases, as well as a 'circuit' experiment including hydraulics loops. Finally, the simulation of the TMI-2 accident was also added to assess the code against real conditions. This validation task was aimed at assessing the ICARE/CATHARE V1 capabilities (including the stand-alone ICARE2 V3mod1 version) and also at proposing recommendations for an optimal use of this version ('Users' Guidelines'). Thus, with a correct account for the recommended guidelines, it appeared that the last ICARE/CATHARE V1 version could be reasonably used to perform best-estimate reactor studies up to a large corium slumping into the lower head. (authors)

Fission Product Experimental Program: Validation and Computational Analysis

Energy Technology Data Exchange (ETDEWEB)

Leclaire, N.; Ivanova, T.; Letang, E. [Inst Radioprotect and Surete Nucl, F-92262 Fontenay Aux Roses (France); Girault, E. [CEA Valduc, Serv Rech Neutron and Critcite, 21 - Is-sur-Tille (France); Thro, J. F. [AREVA NC, F-78000 Versailles (France)

2009-02-15

From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experimental program was performed at the Commissariat a l'Energie Atomique Valduc research facility. The experiments were designed by Institut de Radioprotection et de Surete Nucleaire (IRSN) and funded by AREVA NC and IRSN within the French program supporting development of a technical basis for burnup credit validation. The experiments were performed with the following six key fission products encountered in solution either individually or as mixtures: {sup 103}Rh, {sup 133}Cs, {sup nat}Nd, {sup 149}Sm, {sup 152}Sm, and {sup 155}Gd. The program aimed at compensating for the lack of information on critical experiments involving FPs and at establishing a basis for FPs credit validation. One hundred forty-five critical experiments were performed, evaluated, and analyzed with the French CRISTAL criticality safety package and the American SCALE5. 1 code system employing different cross-section libraries. The aim of the paper is to show the experimental data potential to improve the ability to perform validation of full burnup credit calculation. The paper describes three Phases of the experimental program; the results of preliminary evaluation, the calculation, and the sensitivity/uncertainty study of the FP experiments used to validate the APOLLO2-MORET 4 route in the CRISTAL criticality package for burnup credit applications. (authors)

IRSN annual report 2010

International Nuclear Information System (INIS)

2010-01-01

IRSN, a public authority with industrial and commercial activities, was set up under Article 5 of French Act No. 2001-398 of May 9, 2001, enacted through Order No. 2002-254 of February 22, 2002. This Order was amended on April 7, 2007. The Institute is placed under the joint authority of the Ministries of Defense, the Environment, Industry, Research, and Health. It is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues. Its areas of specialization include the environment and radiological emergency response, human radiation protection in both a medical and professional capacity, and in both normal and post-accident situations, the prevention of major accidents, nuclear reactor safety, as well as safety in plants and laboratories, transport and waste treatment, and nuclear defense expertise. IRSN interacts with all parties concerned by these risks (public authorities, in particular nuclear safety and security authorities, local authorities, companies, research organizations, stakeholders' associations, etc.) to contribute to public policy issues relating to nuclear safety, human and environmental protection against ionizing radiation, and the protection of nuclear materials, facilities, and transport against the risk of malicious acts. In this annual activity reports, IRSN presents the scientific and technical challenges that defines the Contract of Objectives (COB) signed between the Government and IRSN

Contribution to the communication: European fuel behaviour perspective

International Nuclear Information System (INIS)

Pickmann, D.O.; Marin, J.F.; Weidinger, H.; Junkrans, S.; Bairiot, H.

1981-08-01

The safety and security problems particular to pressurized water reactors are reviewed. These problems are followed up at statutory level by the Service Central de Surete des Installations Nucleaires (Central Department of Nuclear Installation Safety) and at technical level by the Institut de Protection et de Surete Nucleaire (Nuclear Protection and Safety Institute) linked to the CEA. The safety analysis is based on the design standards and the technical specifications of reactor components and nuclear substances. They relate to the behaviour of a reactor under normal or accidental operation. The fuel elements are studied in the reactor and outside it by means of loops and power ramps. This information is embodied in models which describe the behaviour of the various parts of the reactor during the accident [fr

IRSN annual report 2011

International Nuclear Information System (INIS)

2012-01-01

IRSN, a public authority with industrial and commercial activities, was set up under Article 5 of French Act No. 2001-398 of May 9, 2001, enacted through Order No. 2002-254 of February 22, 2002. This Order was amended on April 7, 2007. The Institute is placed under the joint authority of the Ministries of Defense, the Environment, Industry, Research, and Health. It is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues. Its areas of specialization include the environment and radiological emergency response, human radiation protection in both a medical and professional capacity, and in both normal and post-accident situations, the prevention of major accidents, nuclear reactor safety, as well as safety in plants and laboratories, transport and waste treatment, and nuclear defense expertise. IRSN interacts with all parties concerned by these risks (public authorities, in particular nuclear safety and security authorities, local authorities, companies, research organizations, stakeholders' associations, etc.) to contribute to public policy issues relating to nuclear safety, human and environmental protection against ionizing radiation, and the protection of nuclear materials, facilities, and transport against the risk of malicious acts. This document is the 2011 annual report of IRSN. It presents the Organization, Progress and main activities in 2011, Transparency and communications policy, safety and radiation protection culture of IRSN. The main activities in 2011 are presented in details: 1 - Safety: Safety of existing facilities: Monitoring reactors, Monitoring fuel cycle facilities and experimental reactors, Containment and fire, Natural hazards, Fuels, Accidents, About defense; Conducting assessments of future facilities: Future waste repositories, Reactors of the future; 2 - Security and non-proliferation: Protection against malicious act; Activities of the advisory

The 24 victims of the Epinal radiotherapy accident

International Nuclear Information System (INIS)

Benderitter, M.; Francois, A.; Clairand, I.; Trompier, F.; Huet, C.; Bottelier-Depois, J.F.; Gourmelon, P.; Gorin, N.

2008-01-01

Full text: During the last 4 years, several incidents/accidents at radiotherapy department occurred in France. The accident at the Public General Hospital in Epinal is the more severe. It was classified level 6 on a 10 degree scale of the ASN/SFRO (Autorite de Surete Nucleaire/Societe Francaise de Radiotherapie Oncologique). This accident is linked to a succession of dysfunctions and human errors. IRSN was elected by the Health Ministry for the identification and medical management of the victims. Concerning the patients treated for their prostate cancer with conformational RT between 2004 and 2005, 24 patients were exposed to 28% excess of dose and suffer from severe late effects (rectitis, cystitis) ranged from grade II to grade IV, some of them suffer from huge dilapidation. Some innovative medical strategies were proposed to the more severe affected patients. A medical follow-up of these patients is actually on the way in parallel to the development of a new research program concerning the improvement of the knowledge and prediction of radiotherapy complications. (author)

Ageing degradation mechanisms in nuclear power plants: lessons learned from operating experience

International Nuclear Information System (INIS)

Bieth, M.; Zerger, B.; Duchac, A.

2014-01-01

This paper presents main results of a comprehensive study performed by the European Clearinghouse on Operating Experience Feedback of Nuclear Power Plants (NPP) with the support of IRSN (Institut de Surete Nucleaire et de Radioprotection) and GRS (Gesellschaft fuer Anlagen und Reaktorsicherheit mbH). Physical ageing mechanisms of Structures, Systems and Components (SSC) that eventually lead to ageing related systems and components failures at nuclear power plants were the main focus of this study. The analysis of ageing related events involved operating experience reported by NPP operators in France, Germany, USA and to the IAEA/NEA International Reporting System on operating experience for the past 20 years. A list of relevant ageing related events was populated. Each ageing related event contained in the list was analyzed and results of analysis were summarized for each ageing degradation mechanism which appeared to be the dominant contributor or direct cause. This paper provides insights into ageing related operating experience as well as recommendations to deal with the physical ageing of nuclear power plant SSC important to safety. (authors)

VVER 1000 SBO calculations with pressuriser relief valve stuck open with ASTEC computer code

International Nuclear Information System (INIS)

Atanasova, B.P.; Stefanova, A.E.; Groudev, P.P.

2012-01-01

Highlights: ► We modelled the ASTEC input file for accident scenario (SBO) and focused analyses on the behaviour of core degradation. ► We assumed opening and stuck-open of pressurizer relief valve during performance of SBO scenario. ► ASTEC v1.3.2 has been used as a reference code for the comparison study with the new version of ASTEC code. - Abstract: The objective of this paper is to present the results obtained from performing the calculations with ASTEC computer code for the Source Term evaluation for specific severe accident transient. The calculations have been performed with the new version of ASTEC. The ASTEC V2 code version is released by the French IRSN (Institut de Radioprotection at de surete nucleaire) and Gesellschaft für Anlagen-und Reaktorsicherheit (GRS), Germany. This investigation has been performed in the framework of the SARNET2 project (under the Euratom 7th framework program) by Institute for Nuclear Research and Nuclear Energy – Bulgarian Academy of Science (INRNE-BAS).

Some particular aspects of control in nuclear power reactors; Conception de la surete en france et influence des imperatifs de surete sur la conception des reacteurs

Energy Technology Data Exchange (ETDEWEB)

Vathaire, F de; Vernier, Ph; Pascouet, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-07-01

This paper reviews the experience acquired in France on the question, of reactor safety. Since a special paper is being presented on reactors of the graphite gas type, the safety of the other types studied in France is discussed here: - heavy water-gas reactors, - fast neutron reactors, - water research reactors of the swimming-pool and tank types. The safety rules peculiar to the different types are explained, with emphasis on their influence on the reactor designs and on the power limits they impose. The corresponding safety studies are presented, particular stress being placed on the original work developed in these fields. Special mention is made of the experimental systems constructed for these studies: the reactor CABRI, pile loop for depressurization tests, loops outside the pile, mock-ups etc. (authors) [French] La presente communication propose une synthese de l'experience acquise en France en matiere de surete des reacteurs. Les reacteurs de la filiere graphite-gaz faisant l'objet d'une communication particuliere, on examine ici la surete des autres types de reacteurs etudies en France: - reacteurs eau lourde-gaz, - reacteurs a neutrons rapides, - reacteurs de recherche a eau des types piscines et tank. Les imperatifs de surete propres aux differentes filieres sont developpes, en mettant l'accent sur leur influence sur la conception des reacteurs et sur les limitations de puissance qu'ils entrainent. Les etudes de surete correspondantes sont presentees, en insistant plus particulierement sur les travaux originaux developpes dans ces domaines. On indique notamment les moyens d'essais qui ont ete construits pour ces etudes: le reacteur CABRI, boucle en pile pour essais de depressurisation, boucles hors pile, maquettes, etc. (auteurs)

2002 scientific and technical report of the IRSN; Rapport scientifique et technique 2002 de l'IRSN

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

The more significant scientific events of the IRSN (Institut of radiation Protection and Nuclear Safety) in 2002, are presented in this report. The first parts concern the reactors, the installations and the radioactive matters transport safety. Part four to six deal with the human and the environment protection. A special part is devoted to the radioactive wastes safety. To illustrate the IRSN cooperation, thesis, research formation and international cooperation are also presented. (A.L.B.)

2002 scientific and technical report of the IRSN; Rapport scientifique et technique 2002 de l'IRSN

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

The more significant scientific events of the IRSN (Institut of radiation Protection and Nuclear Safety) in 2002, are presented in this report. The first parts concern the reactors, the installations and the radioactive matters transport safety. Part four to six deal with the human and the environment protection. A special part is devoted to the radioactive wastes safety. To illustrate the IRSN cooperation, thesis, research formation and international cooperation are also presented. (A.L.B.)

IRSN safety research carried out for reviewing safety cases

International Nuclear Information System (INIS)

Serres, Ch.

2010-01-01

Christophe Serres from IRSN (France) described the independent role of the IRSN regarding research related to nuclear safety in the context of the French Planning Act of 28 June 2006 foreseeing a licence application to be submitted in 2015 for the creation of a deep geological repository. IRSN research programme is organised along research activities devoted to addressing independently-identified k ey safety issues . These 'key issues' should also be of prime concern for the implementer since they relate to the demonstration of the overall safety of the repository, and the level of funding that the implementer should afford to research activities of concern for safety. He explained that the quality and independency of the research programme carried out by IRSN allow building and improving a set of scientific knowledge and technical skills that serves the public mission of delivering technical appraisal and advice, e.g., on behalf of the national safety authority. In particular they contribute to improving the decisional process by making possible scientific dialogue with stakeholders independently from regulator or implementer. The current IRSN R and D programme is developed along the following lines: - Test the adequacy of experimental methods for which feedback is not sufficient. - Develop basic scientific knowledge in the fields where there is a need for better understanding of complex phenomena and interactions. - Develop and use numerical modelling tools to support studies on complex phenomena and interactions. - Perform specific experimental tests aiming at assessing the key parameters that may warrant the performances of the different components of the repository. These studies are carried out by means of experiments performed either at IRSN surface laboratories, or in the Tournemire Experimental Station (TES), an underground facility operated by IRSN in the south-east of France. Targeted actions on research related to operational safety and reversibility

As the transposition goes on in France: new rules

International Nuclear Information System (INIS)

Kiffel, T.

2002-01-01

European directive transposition in radioprotection (96-29 EURATOM for workers and 97-43 for patients) in association with the reformation of radioprotection structures in France will change drastically the situation of radioprotection. New laws (L.1333-1 and L.1333-11) enforce justification, optimisation for the medical exposures and formation of all professionals using radiation. A new ministerial administration (Direction Generale de la Surete Nucleaire et de la Radioprotection) and a new technical operator (Institut de Radioprotection et de Surete Nucleaire) will also change radioprotection. In the new system, radioprotection of the patient becomes as important as for the workers... It's new and will change comportment of professionals. The new rules will probably change the mentality at long term in term of guidelines. Even if radioprotection becomes a very important matter, it is still the time to say that radiation is necessary for medical use in 21. century as well as in the 20. century. (author)

Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

International Nuclear Information System (INIS)

2009-01-01

On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

Progress report I.R.S.N. 2003; Rapport d'activite IRSN 2003

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

This report is divided in six chapters. The first one is devoted to the safety of civil installations, transport and radioactive wastes. In this chapter we find the safety of PWR type reactors, the safety of Cabri reactor, ITER tokamak, the storage of radioactive waste and the criticality of packages with actinides. The second chapter concerns the protection of man and environment, we find the radiation monitoring of workers, the medical management of irradiated personnel, the radiation protection of nuclear power plants. The third chapter is relative to the national defense. The fourth chapter tackles the international relations and the part taken by I.R.S.N. in the Europe construction. The fifth chapter gives the contribution to public information, communication and training. The sixth and last chapter explains the quality policy at I.R.S.N. and how the management is made by a quality option. (N.C.)

IRSN's expertise about nuclear medicine hospital effluents

International Nuclear Information System (INIS)

2009-01-01

This brief note aims at presenting the radioactivity follow up of hospital effluents performed by the French Institute of Radiation Protection and Nuclear Safety (IRSN). This follow up concerns the radioactive compounds and radiopharmaceuticals used in nuclear medicine, and principally technetium 99 and iodine 131. The IRSN has developed a network of remote measurement systems for the monitoring of sewers and waste water cleaning facilities. Data are compiled in a data base for analysis and subsequent expertise. (J.S.)

Progress report I.R.S.N. 2003; Rapport d'activite IRSN 2003

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

This report is divided in six chapters. The first one is devoted to the safety of civil installations, transport and radioactive wastes. In this chapter we find the safety of PWR type reactors, the safety of Cabri reactor, ITER tokamak, the storage of radioactive waste and the criticality of packages with actinides. The second chapter concerns the protection of man and environment, we find the radiation monitoring of workers, the medical management of irradiated personnel, the radiation protection of nuclear power plants. The third chapter is relative to the national defense. The fourth chapter tackles the international relations and the part taken by I.R.S.N. in the Europe construction. The fifth chapter gives the contribution to public information, communication and training. The sixth and last chapter explains the quality policy at I.R.S.N. and how the management is made by a quality option. (N.C.)

2002 scientific and technical report of the IRSN

International Nuclear Information System (INIS)

2003-01-01

The more significant scientific events of the IRSN (Institut of radiation Protection and Nuclear Safety) in 2002, are presented in this report. The first parts concern the reactors, the installations and the radioactive matters transport safety. Part four to six deal with the human and the environment protection. A special part is devoted to the radioactive wastes safety. To illustrate the IRSN cooperation, thesis, research formation and international cooperation are also presented. (A.L.B.)

The new IRSN passive dosemeter using the RPL technique

International Nuclear Information System (INIS)

Fraboulet, P.; Cale, E.; Itie, C.; Bottollier-Depois, Jean-Francois

2008-01-01

Full text: The Institute for Radiological Protection and Nuclear Safety (IRSN) is the French public organisation in charge of research and expertise into nuclear safety and radiation protection. IRSN provides also services in these areas like dosimetric survey for 150,000 workers liable to be exposed to ionising radiation. At present whole-body dosemeters provided by the IRSN laboratory for photons and beta-particles are based on photographic films. In order to anticipate likely supplying decrease and to improve the service, IRSN has decided to replace photographic films by dosemeters based on the radio-photoluminescence (RPL) technology, supplied by the Japanese Company Chiyoda Technol. RPL was chosen after a thorough comparison with other available passive techniques (thermoluminescent dosemeters: TLD, and optically stimulated luminescence: OSL). Constraints due to large-scale production of dosemeters (packaging, shipping, etc.) were taken into account as well. Irradiation tests for five different dosemeters, based on the 3 available techniques (TLD, OSL, RPL) were performed. The main results of these tests are presented (energy, dose and angular response, detection threshold, etc.) together with main technical characteristics of the new RPL dosemeter (range in energy and dose, homogeneity, reproducibility, re-reading, information about radiation type from reading, etc.). This dosemeter is expected to give significative improvements in the IRSN laboratory's provision of service thanks to better dosimetric performances and because it offers the possibility to get information to analyse over-exposure circumstances. (author)

Development of the post-accident expert assessment capacity of I.R.S.N

International Nuclear Information System (INIS)

Repussard, J.

2008-01-01

Emergency preparedness is a key feature of IRSN's mission within the French institutional organisation of nuclear safety and radiation protection. In the event of an accident, IRSN is expected to propose to authorities the appropriate technical decisions in order to safeguard public health, environmental protection, and to restore safety. The article discusses the nature of the challenges that IRSN would have to meet in order to implement its mission during the 'post-accident' phase, which would last a long time if a significative environmental contamination did occur. These four challenges shape the strategy chosen by IRSN to prepare itself for such an eventuality: - to ensure the readiness of its experts, and the validity of its doctrine for intervention, on the basis of research results and of accumulated practical experience, - to maintain state of the art metrology facilities and computer models which would be needed to operate IRSN's response, - to elaborate, and maintain through exercises, plans to mobilize efficiently for the purpose of post-accident operations IRSN's resources which are normally dedicated to other tasks, - the work conducted by IRSN would also be expected to contribute to confidence rebuilding across society, after a nuclear accident. Communication and transparency will play a major role for this, and IRSN's culture and values have to take this fully into account. The conclusion stresses the importance of resource allocation across the different missions of IRSN, the achievement of prevention of accidents through the safety analysis and research processes remaining of paramount importance, and emergency preparedness being the last line of defence. International cooperation is in this respect one of the better ways to enhanced efficiency. (author)

Health physics problems in the context of the development of industrial uses of nuclear energy; Les problemes de radioprotection devant le developpement de l'utilisation industrielle de l'energie nucleaire

Energy Technology Data Exchange (ETDEWEB)

Duhamel, F; Menoux, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-07-01

surete des sites permettent de preciser les parametres de diffusion ou de reconcentration dans les divers milieux naturels de facon a permettre de prevoir le sort des effluents radioactifs depuis les installations qui en sont la source jusqu'a l'homme qui peut y etre expose. L'organisation de la surveillance de la radioactivite sur les sites nucleaires est liee tres etroitement aux etudes de surete. Parmi les nombreuses etudes a mener, on insistera plus particulierement sur les experiences de diffusion atmospherique dont le but est de preciser la valeur des parametres introduits par la theorie tout en permettant de tenir compte de facteurs complementaires. - les etudes hydrologiques, hydrogeologiques et oceanographiques, qui permettent de preciser le sort des ions radioactifs dans l'hydrosphere. - les experiences et etudes liees aux possibilites de rejet ou de stockage des dechets dans le sol. L'ensemble de ces travaux constitue un moyen complementaire, la radioprotection, qui etablit une liaison necessaire entre la surete nucleaire proprement dite laquelle concerne le fonctionnement meme des installations nucleaires, et la surveillance medicale laquelle concerne directement la sante de l'individu et de la population. En meme temps,la radioprotection donne a chacune de ces disciplines une independance qui accroit leur efficacite sur le plan de la securite. (auteurs)

The post-accident nuclear issue: the new crisis expertise challenges for the IRSN; Post-accidentel nucleaire: les nouveaux challenges de l'expertise de crise a L'IRSN

Energy Technology Data Exchange (ETDEWEB)

Champion, D. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Direction de l' environnement et de l' intervention, 78 - Le Vesinet (France)

2010-07-01

The author reports the work performed by two work groups conducted by the IRSN (the French Radioprotection and Nuclear Safety Institute), the first one on the issue of assessment of radiological and dosimetric consequences in a post-accident situation, and the second one on hypotheses to be used to perform predictive assessments of these consequences. First dealing with the end of the emergency phase, he describes how to anticipate actions of protection against immediate post-accident consequences: orientation of the expertise strategy based on the CODIRPA's doctrine, post-accident zoning based on predictive indicators, use of reasonably prudent hypotheses for the first predictive assessments, importance of initial radioactive deposits to perform predictive assessments. Then, the author presents an iterative method of assessment of post-accident consequences: organization of environment radioactivity measurement programmes, periodic update of mapping of initial deposit and of actual deposits at a given time

From the coupling between ion beam analysis techniques and physico-chemical characterization methods to the study of irradiation effects on materials behaviour

International Nuclear Information System (INIS)

Millard-Pinard, N.

2003-01-01

The general purpose of my research work is to follow and to interpret the surface evolution of materials, which have received several treatments. During my PhD and my post-doc work, my field of research was tribology. Since I arrived in the 'Aval du Cycle Electronucleaire' group of the Institut de Physique Nucleaire de Lyon, my research activities are in line with the CNRS program 'PACE ' (Programme sur l'Aval du Cycle Electronucleaire) within the ACTINET network. They are coordinated by the PARIS (Physico-chimie des actinides et autres radioelements en solution et aux interfaces) and NOMADE (NOuveaux MAteriaux pour les DEchets) GDR with ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), EDF and IRSN (Institut de Radioprotection et de Surete Nucleaire) as partner organisations. My work focused on the study of fission products and actinides migration in barrier materials, which may be capable of assuring the long term safety of deep geological repositories. Until now, it was necessary to use the coupling of ion beam analysis techniques and physico-chemical characterization techniques. During the last few months, I have became interested in understanding radiolytic effects. This new orientation has led us to use ion beams as an irradiating tool. These irradiation experiments are pursued in three major projects. The study of cobalt sulfide inhibition effects of radiolysis gas production during the irradiation of model organic molecules. This is a collaboration with the IRSN, the Institut de Recherche sur la Catalyse and the Ecole Nationale Superieure des Mines de Saint-Etienne. A PhD, co-directed by M. Pijolat from ENSMSE and myself, concerning this study will start in October 2003. Water radiolysis effects on iron corrosion are also studied in the particular case of vitrified nuclear waste containers, which will be stored in deep geological repositories. One ANDRA financed PhD, co-directed by Nathalie Moncoffre and myself, is dedicated to this study

From the coupling between ion beam analysis techniques and physico-chemical characterization methods to the study of irradiation effects on materials behaviour; Du couplage des techniques d'analyse par faisceaux d'ions et des methodes de caracterisation physico-chimique a l'etude des effets d'irradiation sur le comportement des materiaux

Energy Technology Data Exchange (ETDEWEB)

Millard-Pinard, N

2003-07-01

The general purpose of my research work is to follow and to interpret the surface evolution of materials, which have received several treatments. During my PhD and my post-doc work, my field of research was tribology. Since I arrived in the 'Aval du Cycle Electronucleaire' group of the Institut de Physique Nucleaire de Lyon, my research activities are in line with the CNRS program 'PACE ' (Programme sur l'Aval du Cycle Electronucleaire) within the ACTINET network. They are coordinated by the PARIS (Physico-chimie des actinides et autres radioelements en solution et aux interfaces) and NOMADE (NOuveaux MAteriaux pour les DEchets) GDR with ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), EDF and IRSN (Institut de Radioprotection et de Surete Nucleaire) as partner organisations. My work focused on the study of fission products and actinides migration in barrier materials, which may be capable of assuring the long term safety of deep geological repositories. Until now, it was necessary to use the coupling of ion beam analysis techniques and physico-chemical characterization techniques. During the last few months, I have became interested in understanding radiolytic effects. This new orientation has led us to use ion beams as an irradiating tool. These irradiation experiments are pursued in three major projects. The study of cobalt sulfide inhibition effects of radiolysis gas production during the irradiation of model organic molecules. This is a collaboration with the IRSN, the Institut de Recherche sur la Catalyse and the Ecole Nationale Superieure des Mines de Saint-Etienne. A PhD, co-directed by M. Pijolat from ENSMSE and myself, concerning this study will start in October 2003. Water radiolysis effects on iron corrosion are also studied in the particular case of vitrified nuclear waste containers, which will be stored in deep geological repositories. One ANDRA financed PhD, co-directed by Nathalie Moncoffre and myself, is dedicated to this study

From the coupling between ion beam analysis techniques and physico-chemical characterization methods to the study of irradiation effects on materials behaviour; Du couplage des techniques d'analyse par faisceaux d'ions et des methodes de caracterisation physico-chimique a l'etude des effets d'irradiation sur le comportement des materiaux

Energy Technology Data Exchange (ETDEWEB)

Millard-Pinard, N

2003-07-01

The general purpose of my research work is to follow and to interpret the surface evolution of materials, which have received several treatments. During my PhD and my post-doc work, my field of research was tribology. Since I arrived in the 'Aval du Cycle Electronucleaire' group of the Institut de Physique Nucleaire de Lyon, my research activities are in line with the CNRS program 'PACE ' (Programme sur l'Aval du Cycle Electronucleaire) within the ACTINET network. They are coordinated by the PARIS (Physico-chimie des actinides et autres radioelements en solution et aux interfaces) and NOMADE (NOuveaux MAteriaux pour les DEchets) GDR with ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), EDF and IRSN (Institut de Radioprotection et de Surete Nucleaire) as partner organisations. My work focused on the study of fission products and actinides migration in barrier materials, which may be capable of assuring the long term safety of deep geological repositories. Until now, it was necessary to use the coupling of ion beam analysis techniques and physico-chemical characterization techniques. During the last few months, I have became interested in understanding radiolytic effects. This new orientation has led us to use ion beams as an irradiating tool. These irradiation experiments are pursued in three major projects. The study of cobalt sulfide inhibition effects of radiolysis gas production during the irradiation of model organic molecules. This is a collaboration with the IRSN, the Institut de Recherche sur la Catalyse and the Ecole Nationale Superieure des Mines de Saint-Etienne. A PhD, co-directed by M. Pijolat from ENSMSE and myself, concerning this study will start in October 2003. Water radiolysis effects on iron corrosion are also studied in the particular case of vitrified nuclear waste containers, which will be stored in deep geological repositories. One ANDRA financed PhD, co-directed by Nathalie Moncoffre and myself, is

Health physics problems in the context of the development of industrial uses of nuclear energy; Les problemes de radioprotection devant le developpement de l'utilisation industrielle de l'energie nucleaire

Energy Technology Data Exchange (ETDEWEB)

Duhamel, F.; Menoux, A. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-07-01

ou les moyens technologiques de protection sont multiples et complexes. Les etudes de surete des sites permettent de preciser les parametres de diffusion ou de reconcentration dans les divers milieux naturels de facon a permettre de prevoir le sort des effluents radioactifs depuis les installations qui en sont la source jusqu'a l'homme qui peut y etre expose. L'organisation de la surveillance de la radioactivite sur les sites nucleaires est liee tres etroitement aux etudes de surete. Parmi les nombreuses etudes a mener, on insistera plus particulierement sur les experiences de diffusion atmospherique dont le but est de preciser la valeur des parametres introduits par la theorie tout en permettant de tenir compte de facteurs complementaires. - les etudes hydrologiques, hydrogeologiques et oceanographiques, qui permettent de preciser le sort des ions radioactifs dans l'hydrosphere. - les experiences et etudes liees aux possibilites de rejet ou de stockage des dechets dans le sol. L'ensemble de ces travaux constitue un moyen complementaire, la radioprotection, qui etablit une liaison necessaire entre la surete nucleaire proprement dite laquelle concerne le fonctionnement meme des installations nucleaires, et la surveillance medicale laquelle concerne directement la sante de l'individu et de la population. En meme temps,la radioprotection donne a chacune de ces disciplines une independance qui accroit leur efficacite sur le plan de la securite. (auteurs)

IC modelling in the IRSN EPR level 1 PSA

International Nuclear Information System (INIS)

Delache, J.

2012-01-01

Today in France, an EPR (European Pressurized Water Reactor) Unit is under construction at the Flamanville site. The creation authorization was granted in April 2007 and the plant commissioning is planned for 2012. The plant operator (EDF) provided for the construction license several PSA (Probabilistic Safety Assessment) studies. IRSN, as TSO (Technical Safety Organisation), wishes to dispose of the appropriate knowledge and tools for the independent verification of the operator studies and so developed its own model of PSA level 1. The goal is not to rebuild the plant operator PSA (with a full scope...) but to dispose of a simplified model able to clearly point out specific important issues. In the IRSN model a particular effort has recently been done on the Digital IC modelling. The IC (Instrumentation and Control) is modelled in the IRSN EPR PSA by using Fault Trees. Instead, EDF EPR PSA applies the COMPACT model to simplify the command and instrumentation logics. The IRSN model is more detailed in order to be more accurate in the global analysis of the Digital IC. For instance the communication ways between automates are considered as well as the failure of support systems. The model is still under development mainly in order to define the CCF (Common Cause Failure) which may be considered. (authors)

VVER-1000 small-medium break LOCAs predictions by ASTEC

International Nuclear Information System (INIS)

Georgieva, J.; Stefanova, A.; Atanasova, B.; Groudev, P.; Tusheva, P.; Mladenov, I.; Dimov, D.; Passalacqua, R.

2005-01-01

This paper deals with an assessment of ASTEC1.1v0 code in the simulation of small and medium break LOCAs (ranging from 30mm up to 70mm equivalent diameter). The reference power plant for this analysis is a VVER-1000/V320 (e.g. Units 5 and 6 at Kozloduy NPP). A preliminary comparison with MELCOR and RELAP-SCDAP severe accident codes will be discussed. This investigation has been performed in the framework of the SARNET project (under the Euratom 6 th framework program) by the FoBAUs group (Forum of Bulgarian ASTEC users). The FoBAUs group aims at the validation of the ASTEC code in the field of severe accidents. Future activities will target the ASTEC capability (as a PSA-level 2 tool) to simulate a large range of reactor accident scenarios with intervention of safety systems (either passive systems or operated by operators). The final target is to assess Severe Accident Management (SAM) procedures for VVER-1000 reactors. The ASTEC1.1v0 code version here used is the one released in June 2004 by the French IRSN (Institut de Radioprotection et de Surete Nucleaire) and the German GRS (Gesellschaft ReactorSicherheit mbH). (author)

Severe accident analysis in a two-loop PWR nuclear power plant with the ASTEC code

International Nuclear Information System (INIS)

Sadek, Sinisa; Amizic, Milan; Grgic, Davor

2013-01-01

The ASTEC/V2.0 computer code was used to simulate a hypothetical severe accident sequence in the nuclear power plant Krsko, a 2-loop pressurized water reactor (PWR) plant. ASTEC is an integral code jointly developed by Institut de Radioprotection et de Surete Nucleaire (IRSN, France) and Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS, Germany) to assess nuclear power plant behaviour during a severe accident. The analysis was conducted in 2 steps. First, the steady state calculation was performed in order to confirm the applicability of the plant model and to obtain correct initial conditions for the accident analysis. The second step was the calculation of the station blackout accident with a leakage of the primary coolant through degraded reactor coolant pump seals, which was a small LOCA without makeup capability. Two scenarios were analyzed: one with and one without the auxiliary feedwater (AFW). The latter scenario, without the AFW, resulted in earlier core damage. In both cases, the accident ended with a core melt and a reactor pressure vessel failure with significant release of hydrogen. In addition, results of the ASTEC calculation were compared with results of the RELAP5/SCDAPSIM calculation for the same transient scenario. The results comparison showed a good agreement between predictions of those 2 codes. (orig.)

Main post-accident management stakes: IRSN's point of view

International Nuclear Information System (INIS)

Andre Oudiz

2006-01-01

Full text of publication follows: Off site management of a radiological crisis covers two phases which need to be clearly distinguished even if there are links between them: emergency phase and recovery phase (also called late or post-accident phase). The presentation will deal with the latter, rather neglected up until recently, but conveying special attention from now on in France and at the international level. It is clear now that the long term management of a radiological or nuclear crisis cannot be reduced to merely site decontamination. Actually, environmental decontamination considerations would be only one amongst other essential economical, social, health, psychological, cultural, and symbolical concerns. This is why off site management of a radiological crisis requires innovative governance, in order to challenge such a complexity. This need for challenge led IRSN to have on the go technical developments and new governance modes reflection. 1) Technical developments: they deal with implementing an organisation, a set of methods, a platform of technical tools which would allow the stakeholders to carry out efficiently their mission during the recovery phase. For example, countermeasures for agricultural and urban rehabilitation are developed within the framework of the 6. PCRDT EURANOS programme. Teams from several countries are involved in common elaboration of rehabilitation strategies based on the best available knowledge. Besides this, simple operational decision aiding tools for the stakeholders (local administration, elected representatives, professional agricultural groups, etc.) are currently developed by IRSN within the framework of the nuclear post-accident exercises. IRSN is also involved in doctrinal reflections about the respective roles of radioactive measurements in the environment and radiological consequences calculation during emergency and recovery phases. Criteria for emergency countermeasures withdrawal are also currently under

IRSN-ANCCLI partnership. IRSN-ANCCLI seminar on decennial inspections of 900 MWe reactors - November 2010

International Nuclear Information System (INIS)

Rollinger, Francois; Delalonde, Jean-Claude; Hubert, F.; Paulmaz, X.; Tindillere, M.; Lheureux, Y.; Junker, R.; Sene, M.

2010-11-01

This seminar addressed the commitment of local information commissions (CLI) in the analysis and follow-up of the third decennial inspections of the French 900 MWe nuclear reactors. A first session addressed topics directly related to these inspections. Contributions proposed under the form of Power Point presentations by experts and representatives of the IRSN, EDF and CLIs addressed the following issues: safety re-examination of EDF 900 MWe reactors at the occasion of the third decennial inspection, activities of the IRSN related to skill management in nuclear power stations, implementation of the third decennial inspection of the unit 1 of the Fessenheim nuclear power station, the issue of follow-up by a local information commission after a decennial inspection. A second session addressed topics not related to decennial inspections and were proposed by Gravelines and Dampierre local information commissions: analysis of significant safety events, issues of skill management in nuclear power stations

Plutonium, nuclear fuel; Le plutonium, combustible nucleaire

Energy Technology Data Exchange (ETDEWEB)

Grison, E [Commissariat a l' Energie Atomique, Fontenay aux Roses (France). Centre d' Etudes Nucleaires, Saclay

1960-07-01

A review of the physical properties of metallic plutonium, its preparation, and the alloys which it forms with the main nuclear metals. Appreciation of its future as a nuclear fuel. (author) [French] Apercu sur les proprietes physiques du plutonium metallique, sa preparation, ses alliages avec les principaux metaux nucleaires. Consideration sur son avenir en tant que combustible nucleaire. (auteur)

Safety challenges after the Fukushima accident. ANCCLI-IRSN work meeting

International Nuclear Information System (INIS)

Demet, Michel; Lheureux, Yves; Sene, Monique; Sene, Raymond; Eimer, Michel; Lachaume, Jean-Luc; Majnoni, Sophia; Marignac, Yves; Revol, Henri; Gilles, Compagnat; Baumont, David; Huet, Cyril; Rebour, Vincent; Besnus, Francois; Le Bars, Igor; Lizot, Marie-Therese; Carre, Christine; Dupuy, Patricia; Jorel, Martial; Lavarenne, Caroline; Rousseau, Jean-Marie; Charron, Sylvie; Gilli, Ludivine

2011-11-01

After a synthetic report of the meeting, this document contains Power Point presentations proposed by the different contributors. These presentations proposed: an overview on additional safety assessments (ECS) and an assessment of 'post-Fukushima' inspections performed in basic nuclear installations; the CLI's opinion on the Gravelines ECS report; an analysis and a discussion of ECS reports of nuclear installations in the perspective of the Fukushima accident; the IRSN analysis of ECS as they are performed by operators; a presentation of the IRSN analysis approach to ECS; contributions of different post-Fukushima ECS permanent groups within the IRSN (these work groups address installation condition, external flooding, and seismic risk); a presentation of the 'fusion prevention' aspects of the management of accidental situations in EDF reactors

IRSN-ANCCLI partnership. Technical dialogue HLW and ILW - Reversibility - Resources - April 2014

International Nuclear Information System (INIS)

Castel, C.; Sene, M.; Gueritte, M.; Hoorelbeke, J.M.; Boissier, F.; Besnus, F.; Matray, J.M.; Serres, Ch.; Fleury, J.M.; Boissavy, Christian

2014-04-01

Power Point presentations proposed by members of the ASN, IRSN, ANDRA or local information commissions (CLI) first address some generalities regarding the Cigeo project of disposal of high-level and intermediate level long-lived radioactive wastes: history and next steps of the information file for the Cigeo projects, points of view on the conclusions of the public debate on Cigeo and of the citizen conference. A set of contributions addresses the issues of reversibility and recoverability: activities performed by a work-group on reversibility, opinion of the ANDRA on reversibility, opinion of the IRSN. A contribution addresses the issues on potential energy resources, and two contributions address the issue of lack of resources: social and economic aspects and exploitability on a short term of geological identified resources, opinion of the IRSN on the geothermal resource. A last set of contributions deals with the disposal safety regarding intrusion (IRSN approach to expertise the risk of intrusion for the disposal, intrusion scenarios taken into account by the ASN)

Complementary Safety Assessments for Research Reactors for the French Nuclear Safety Authority

International Nuclear Information System (INIS)

Kassiotis, Christophe; Rigaud, Antoine; Evrard, Lydie

2013-01-01

The 'Autorite de surete nucleaire' (ASN) requested licensees to undertake stress tests, called complementary safety assessments (CSA), of their installations on May 5th 2011, following the accident that occurred in Japan on March 11th 2011. Their mission consisted in providing feedback on the consequences of potential extreme events. In this process, all the French facilities were divided into three categories of decreasing priority, depending on two main factors: on the one hand, their vulnerability to the various phenomena that led to the Fukushima accident, and on the other hand, the amount of radioactive elements that would be dispersed in the event of a failure of the safety functions. On the 79 high-priority facilities, only five of them are research or experimental reactors (including two currently shutdown or in decommissioning) and their operators (the 'Comissariat a l'energie atomique et aux energies alternatives' (CEA) and the 'Institut Laue Langevin') submitted their reports to the ASN on September 15 th 2011. Concerning the lower-priority facilities, including three other facilities (two research reactors operated by the CEA and a facility operated by ITER Organization) the deadline was September 15 th 2012. Finally, the remaining facilities were not asked to submit a report yet, but they will have to do it later, mainly on the occasion of their next periodic safety review. The analyses of the cliff-edge effects, that may occur in extreme situations (exceptional scale event, combination of several disasters...), led to the definition of a hardened safety core concept by the 'Institut de radioprotection et de surete nucleaire' (IRSN). This hardened safety core of structures, equipment and organizational measures must ensure the ultimate protection of the concerned facilities in extreme situations : it is designed to prevent severe accidents (or curb their progression), limit large scale releases for extreme accidents, and enables the operating teams to

Nuclear Safety. 1997; Surete Nucleaire. 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-19

A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs, technical incidents, and human factor incidents.

Nuclear Safety Charter; Charte Surete Nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

The AREVA 'Values Charter' reaffirmed the priority that must be given to the requirement for a very high level of safety, which applies in particular to the nuclear field. The purpose of this Nuclear Safety Charter is to set forth the group's commitments in the field of nuclear safety and radiation protection so as to ensure that this requirement is met throughout the life cycle of the facilities. It should enable each of us, in carrying out our duties, to commit to this requirement personally, for the company, and for all stakeholders. These commitments are anchored in organizational and action principles and in complete transparency. They build on a safety culture shared by all personnel and maintained by periodic refresher training. They are implemented through Safety, Health, and Environmental management systems. The purpose of these commitments, beyond strict compliance with the laws and regulations in force in countries in which we operate as a group, is to foster a continuous improvement initiative aimed at continually enhancing our overall performance as a group. Content: 1 - Organization: responsibility of the group's executive management and subsidiaries, prime responsibility of the operator, a system of clearly defined responsibilities that draws on skilled support and on independent control of operating personnel, the general inspectorate: a shared expertise and an independent control of the operating organization, an organization that can be adapted for emergency management. 2 - Action principles: nuclear safety applies to every stage in the plant life cycle, lessons learned are analyzed and capitalized through the continuous improvement initiative, analyzing risks in advance is the basis of Areva's safety culture, employees are empowered to improve nuclear Safety, the group is committed to a voluntary radiation protection initiative And a sustained effort in reducing waste and effluent from facility Operations, employees and subcontractors are treated alike, and a high level Of know-how is supported by training and skills maintenance. 3 - Transparency and reporting: Areva endeavors to provide reliable and relevant information enabling an objective assessment of the status of nuclear safety in its facilities (incident reporting, annual report of the general inspectorate, annual reporting on occupational safety during nuclear facility operations). 4 - Glossary.

Long-term behaviour of radioactive nuclides in the environment

International Nuclear Information System (INIS)

Brechignac, F.; Moberg, L.; Suomela, M.

1999-01-01

Report of recent advances in Europe, regarding the long-term development of radioactive nuclides in the environment. The corresponding scientific findings from three projects - Peace, Landscape and Epora (involving 18 European laboratories) - have been collected together. These projects were managed by the IPSN for the European Commission (DG XII) in the framework of the programme 'Surete de la fission nucleaire' (Nuclear fission safety programme). (author)

Treatment of effluent at the Saclay Centre d'Etudes Nucleaires (1960); Le traitement des effluents du Centre d'Etudes Nucleaires de Saclay (1960)

Energy Technology Data Exchange (ETDEWEB)

Wormser, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

The Centre d'Etudes Nucleaires at Saclay possesses several installations from which liquid radioactive effluent is rejected, and it has thus been found necessary to construct a station for the purification of radioactive liquids and to settle various chemical, analytical and technological problems. This report describes, in the following order: - the disposal possibilities at the Centre d'Etudes Nucleaires, Saclay, - the effluents produced at the centre, - the set-up for collecting effluent, - treatment of the effluent, - results of these treatments. (author) [French] La presence, au Centre d'Etudes Nucleaires de Saclay, de plusieurs installations susceptibles de rejeter des effluents liquides radioactifs a necessite la construction d'une station d'epuration d'eaux radioactives et la mise au point de differents problemes chimiques, analytiques et technologiques. Dans ce rapport, nous exposerons successivement: - les possibilites de rejet du Centre d'Etudes Nucleaires de Saclay, - les effluents du centre, - le dispositif de collecte des effluents, - le traitement de ces effluents, - les resultats de ces traitements. (auteur)

Progress report I.R.S.N. 2002; Rapport d'activite IRSN 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

This progress report is divided in three parts. The first one explains the missions of I.R.S.N. and its organisation. The second part concerns the activities: to protect man and environment, contribution to the safety of installations and transports, to look after the non proliferation, to be a driving force in the international relations, to contribute to the information and training. The third part is relative to the quality and means of the development, to continue the quality objectives, the human resources and social relations, the budget in 2002. (N.C.)

Progress report I.R.S.N. 2003

International Nuclear Information System (INIS)

2003-01-01

This report is divided in six chapters. The first one is devoted to the safety of civil installations, transport and radioactive wastes. In this chapter we find the safety of PWR type reactors, the safety of Cabri reactor, ITER tokamak, the storage of radioactive waste and the criticality of packages with actinides. The second chapter concerns the protection of man and environment, we find the radiation monitoring of workers, the medical management of irradiated personnel, the radiation protection of nuclear power plants. The third chapter is relative to the national defense. The fourth chapter tackles the international relations and the part taken by I.R.S.N. in the Europe construction. The fifth chapter gives the contribution to public information, communication and training. The sixth and last chapter explains the quality policy at I.R.S.N. and how the management is made by a quality option. (N.C.)

Simulation of the in-pile test Phebus-FPT3 using ASTEC V2 and ATHLET-CD 2.1A

Energy Technology Data Exchange (ETDEWEB)

Kruse, Philipp; Koch, Marco K. [Bochum Univ. (Germany). Chair of Energy Systems and Energy Economics

2011-07-01

The Phebus-FPT programme, initiated in 1988 by the 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) and the Joint Research Centre (JRC) of the European Commission (EC), was performed in the Phebus facility operated by 'Commissariat a'Energie Atomique' (CEA). The facility represent a 900 MWe Pressurized Water Reactor (PWR) scaled down by a factor 1:5000 which objective is to study fuel degradation and the subsequent release, transport and retention of fission products, structure, control rod and fuel materials, in case of a severe accident. The Phebus-FPT programme consists of integral in-pile tests, varying the fuel burn-up and geometry, the control rod nature, the thermal hydraulic conditions in the bundle and through the experimental circuit as well as in the containment. In primary, the integral experiments should outline a detailed description of the main phenomena of core degradation, fission product release and transport as well as radionuclide interactions. Due to that it is possible to analyse the physical and chemical processes due to a severe accident. With the ascertained data, an evaluation of the accident management measures could be made as well. A secondary aim of the Phebus tests was to enable model development and evaluation of severe accident codes such like ASTEC and ATHLET-CD. (orig.)

Summary record of the experts meeting on the proposed OECD-IRSN STLOC project

International Nuclear Information System (INIS)

2004-01-01

The purpose of this meeting was to determine the interest in member countries for the types of LOCA tests envisaged in the STLOC programme proposed by IRSN. The IRSN proposal was circulated among this Group in advance of the meeting. After the presentations and discussions, the Group recommendations were as follows: different views were expressed as to the need to perform the LOCA integral tests; there was an understanding that the results of separate effect tests (ANL, JAERI, Halden) would need to be obtained before deciding on the intended LOCA tests proposed in STLOC; IRSN and the OECD-NEA should explore the possibility to run the first ST test with air ingress (STLOC1), for which partial funding already exists (this test is foreseen for 2008); the need of LOCA tests as envisaged in STLOC should be re-assessed in about three years time (2006); analytical and experimental progress on LOCA tests should be monitored until then, through for instance the SEGFSM. An executive summary of the IRSN Source term LOCA program LOCA part is given in an appendix

Transfer process studies through a toarcian argilite

International Nuclear Information System (INIS)

Boisson, J.Y.

1996-01-01

Concerning long lived and high level radioactive wastes, the French Wastes Management Research Act (30th December 1991) has set three ways to be studied: separation and/or transmutation, conditioning processes and volumes reduction, and feasibility of geological disposal. ANDRA, in charge of this last point; has the responsibility to create and develop underground laboratories, to elaborate and propose the concept of the future disposal installations with safety demonstration, to be submitted to the French safety governmental authorities (Direction de la Surete des Installations Nucleaires). In order to asses these safety demonstrations, to build up its judgement, DSIN will ask technical advice, from Institut de Protection et de Surete Nucleaire (IPSN). To be able to meet these requirements, IPSN is developing, in the framework of its research and development safety programs, in situ research concerning the confining properties of geological formations. In order to perform experiments in representative conditions concerning mainly geotechnical and hydrogeological properties of very low permeability rocks, appropriate underground sites have been selected in the past in granite and shale formations. IPSN activities at the Tournemire site are the most important activities regarding specifically research about characterization of transfers through an argilite formation. This programme is developed in the framework of a cost sharing research contract between IPSN and EC. (author)

Progress report I.R.S.N. 2002; Rapport d'activite IRSN 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

This progress report is divided in three parts. The first one explains the missions of I.R.S.N. and its organisation. The second part concerns the activities: to protect man and environment, contribution to the safety of installations and transports, to look after the non proliferation, to be a driving force in the international relations, to contribute to the information and training. The third part is relative to the quality and means of the development, to continue the quality objectives, the human resources and social relations, the budget in 2002. (N.C.)

Overview of IRSN R and D on NPP safety, with focus on severe accident

International Nuclear Information System (INIS)

Van Dorsselaere, Jean-Pierre

2015-01-01

IRSN contributes to the continuous improvement of safety level of Gen.II and III reactors, with the aim to approach for Gen.II the target safety level of Gen.III. This needs to build the necessary knowledge to appreciate margins for safety important systems, structures and components in the frame of plant operation life extension beyond 40 years. Research is a major IRSN mission that is tightly linked to expertise needs: it involves 40% of overall budget and, out of radiation protection and safety of waste disposal, around 280 scientists. IRSN has acquired a huge experience in the last 30 years on severe accidents, both on experimental and theoretical aspects, in particular through management of large international research programmes like the Phébus. FP integral experiments in the last 20 years and the coordination of the SARNET network of excellence that continues now in the frame of the NUGENIA European association. Besides, IRSN is developing, in collaboration with GRS (Germany), the integral system code ASTEC that is considered now as the European reference code due to the continuous capitalization of all the international knowledge. The presentation summarizes the ongoing IRSN research on the different phenomena involved in severe accidents, with more focus in the last years on mitigation devices or measures, i.e. for in-vessel and ex-vessel corium coolability, hydrogen explosion risk and source term. IRSN leads several international projects in Euratom frame (such as CESAM on ASTEC, PASSAM on source term mitigation, and IVMR on in-vessel corium retention) or OECD/NEA/CSNI (such as STEM). Moreover, several national projects on the above issues are ongoing with the French actors in this domain. Collaboration between IRSN and India is very active and efficient on ASTEC code with BARC and AERB, in particular through PHWR model development and assessment, and could be extended in the future to other issues either on severe accidents or on other Topics. (author)

Main post-accident management stakes: IRSN's point of view

Energy Technology Data Exchange (ETDEWEB)

Andre Oudiz [Institut de Radioprotection et de Surete Nucleaire (France)

2006-07-01

Full text of publication follows: Off site management of a radiological crisis covers two phases which need to be clearly distinguished even if there are links between them: emergency phase and recovery phase (also called late or post-accident phase). The presentation will deal with the latter, rather neglected up until recently, but conveying special attention from now on in France and at the international level. It is clear now that the long term management of a radiological or nuclear crisis cannot be reduced to merely site decontamination. Actually, environmental decontamination considerations would be only one amongst other essential economical, social, health, psychological, cultural, and symbolical concerns. This is why off site management of a radiological crisis requires innovative governance, in order to challenge such a complexity. This need for challenge led IRSN to have on the go technical developments and new governance modes reflection. 1) Technical developments: they deal with implementing an organisation, a set of methods, a platform of technical tools which would allow the stakeholders to carry out efficiently their mission during the recovery phase. For example, countermeasures for agricultural and urban rehabilitation are developed within the framework of the 6. PCRDT EURANOS programme. Teams from several countries are involved in common elaboration of rehabilitation strategies based on the best available knowledge. Besides this, simple operational decision aiding tools for the stakeholders (local administration, elected representatives, professional agricultural groups, etc.) are currently developed by IRSN within the framework of the nuclear post-accident exercises. IRSN is also involved in doctrinal reflections about the respective roles of radioactive measurements in the environment and radiological consequences calculation during emergency and recovery phases. Criteria for emergency countermeasures withdrawal are also currently under

Strong movement data currently available at IPSN/DAS

International Nuclear Information System (INIS)

Hamaide, D.; Mohammadioun, B.; Mohammadioun, G.

1986-01-01

The collection of recordings and other data on strong seismic motion compiled by the Departement d'Analyse de Surete de l'Institut de Protection et de Surete Nucleaire (Commissariat a l'Energie Atomique) to form a data base known as ''sismotheque'' are presented. Following an introduction wherein the necessity of creating such a repertory for evaluating seismic hazard on the sites of nuclear facilities is explained, a description is given of the means engaged, i.e. motion recorded by the DAS's own laboratory or data procured from other research units in France or abroad. The quantity and quality of the data now available are summarized, as well as the techniques designed to gain access to desired information, illustrated by concrete examples. The paper concludes with recommendations for future developments [fr

IRSN Code of Ethics and Professional Conduct. Annex VII [TSO Mission Statement and Code of Ethics

International Nuclear Information System (INIS)

2018-01-01

IRSN has adopted, in 2013, a Code of Ethics and Professional Conduct, the contents of which are summarized. As a preamble, it is indicated that the Code, which was adopted in 2013 by the Ethics Commission of IRSN and the Board of IRSN, complies with relevant constitutional and legal requirements. The introduction to the Code presents the role and missions of IRSN in the French system, as well as the various conditions and constraints that frame its action, in particular with respect to ethical issues. It states that the Code sets principles and establishes guidance for addressing these constraints and resolving conflicts that may arise, thus constituting references for the Institute and its staff, and helping IRSN’s partners in their interaction with the Institute. The stipulations of the Code are organized in four articles, reproduced and translated.

Assessment report of the Radiation protection and Nuclear Safety Institute (IRSN)

International Nuclear Information System (INIS)

2011-03-01

After having recalled and commented the three main missions of the IRSN (an expertise capacity, a mission of research, a mission of public information and training), this report analyzes and comments the governance of the institute: a very much structured pyramidal organisation based on a quality approach, a human resource management policy adapted to short and middle term needs, patrimony and estate policy, financial and budgetary policy, personnel hygiene and safety policy. It analyzes and comments the different relationship and partnership maintained by the IRSN with institutions and companies. Strengths and weaknesses are outlined and some recommendations are proposed

The ISRN has assessed the safety and radioprotection of the solid radioactive waste management area at CEA/Saclay; L'IRSN a expertise la surete et la radioprotection de la zone de gestion des dechets radioactifs solides du CEA/Saclay

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

Completed by a report of a Permanent Group of Experts on the safety re-examination for the solid radioactive waste management area of the CEA/Saclay, this paper is a statement of the assessment by the IRSN (the French Institute of Radioprotection and Nuclear Safety) of this safety re-examination. It first recalls what a safety re-examination is for a nuclear installation and indicates the documents which have been transmitted by the CEA and analysed. Then, it briefly describes the activities which are performed in the concerned area: collecting, warehousing, conditioning, control and shipping of solid radioactive wastes or useless fuels. The IRSN comments the works done and to be done for the different operations on different types of waste (low or middle activity), and then the different aspects of the installation safety (radiations, confining, fire, climatic events, civil engineering)

IRSN-Ancli seminar on the post-accident context

International Nuclear Information System (INIS)

Didier, Damien; Leroyer, Veronique; Gariel, Jean-Christophe; Meier, Christine; Petitfrere, Michael; Meraux-Netillard, Isabelle; Lerouxel, Roland; Gandouen, Gael; Boutin, Dominique; Charre, Jean-Pierre; Noe, Maite; Quenneville, Celine; Farandeau, Sebastien; Mouchet, Chantal; Pineau, Coralie; Rollinger, Francois; GARIEL, Jean-Christophe; Ando, Ryoko; Nishida, Shoshi; Miazaki, Makoto; Hayano, Ryugo; Lheureux, Yves; Lochard, Jacques; Boilley, David; Godet, Jean-Luc

2014-10-01

The first session addressed the context of post-accident management: main challenges of radiation protection in case of nuclear accident, management of energy situations (specific intervention plans of nuclear plants), elements of doctrine for the post-accident management of an accident. The second session addressed the preparedness of territories to post-accident management: preparation to post-accident management in the Montbeliard district, emergency and post-accidental situation (preparedness at the district scale, example of Loiret), and return on experience from the post-accident exercise in Cattenom. The third session addressed the action undertaken by the ANCCLI and IRSN for the awareness of post-accidental problematic (experiments in Saclay, Marcoule, Gravelines and Golfech, lessons learned from the pilot phase and perspectives). The last session addressed the post-accidental management of the Fukushima accident: approach of the IRSN to learn lessons from the dialogue initiative in Fukushima, round table on challenges on the long term of post-accidental management, Japanese witnesses

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1982-09-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operations of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation pratice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS -or a letter- can also give the result of the examination of the constructor and operator code (RCC) by safety authorities

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1983-01-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operating of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridicial sense; they are called Regles Fondamentales de Surete (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS - or a letter - can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

Progress of IRSN R&D on ITER Safety Assessment

Science.gov (United States)

Van Dorsselaere, J. P.; Perrault, D.; Barrachin, M.; Bentaib, A.; Gensdarmes, F.; Haeck, W.; Pouvreau, S.; Salat, E.; Seropian, C.; Vendel, J.

2012-08-01

The French "Institut de Radioprotection et de Sûreté Nucléaire" (IRSN), in support to the French "Autorité de Sûreté Nucléaire", is analysing the safety of ITER fusion installation on the basis of the ITER operator's safety file. IRSN set up a multi-year R&D program in 2007 to support this safety assessment process. Priority has been given to four technical issues and the main outcomes of the work done in 2010 and 2011 are summarized in this paper: for simulation of accident scenarios in the vacuum vessel, adaptation of the ASTEC system code; for risk of explosion of gas-dust mixtures in the vacuum vessel, adaptation of the TONUS-CFD code for gas distribution, development of DUST code for dust transport, and preparation of IRSN experiments on gas inerting, dust mobilization, and hydrogen-dust mixtures explosion; for evaluation of the efficiency of the detritiation systems, thermo-chemical calculations of tritium speciation during transport in the gas phase and preparation of future experiments to evaluate the most influent factors on detritiation; for material neutron activation, adaptation of the VESTA Monte Carlo depletion code. The first results of these tasks have been used in 2011 for the analysis of the ITER safety file. In the near future, this R&D global programme may be reoriented to account for the feedback of the latter analysis or for new knowledge.

IRSN-ANCCLI partnership. Work session on Complementary safety assessments - November 2011

International Nuclear Information System (INIS)

Lachaume, Jean-Luc; Lheureux, Yves; Sene, Monique; Sene, Raymond; Jorel, Martial; Lavarenne, Caroline; Rousseau, Jean-Marie; Rebour, Vincent; Baumont, David; Dupuy, Patricia

2011-11-01

After an overview by the ASN of complementary safety assessments and an assessment of 'post-Fukushima' inspections of basic nuclear installations, the contributions (Power Point presentations) of this seminar proposed: the opinion of the Gravelines CLI (local information commission) on the Gravelines complementary safety assessment report, an analysis and discussion by the GSIEN on reports of complementary assessment of safety of nuclear installations with respect to the Fukushima accident, an analysis by the IRSN of complementary safety assessments performed by operators, the IRSN approach to analyze complementary safety assessments, reports on installation conditions, external flooding and seismic hazard, 'meltdown prevention' aspects in the management of accidental situations in EDF reactors

Lessons learned form IRSN review of Flamanville 3 Level PSA

International Nuclear Information System (INIS)

Georgescu, G.; Corenwinder, F.

2012-01-01

In the frame of the construction and licensing of Flamanville 3 NPP the PSA (Probabilistic Safety Assessment)plays an important role for the EPR Project assessment. The PSA was used for early design verification of EPR Reactor, several design improvement being defined based on these PSA insights and following the discussions with the French and German safety authorities. IRSN, as the French Safety Authority (ASN) technical support organization, performs the review of the PSA developed by the plant operator (EDF). The paper presents the main issues regarding the using of 'design PSA', identified by IRSN following the review of the internal events Level 1 PSA transmitted by EDF in the frame of the anticipated instruction of the application for operating license of the Flamanville 3 reactor. (authors)

IRSN - Institute of Radiation protection and Nuclear Safety. Report 2014. Corporate societal responsibility

International Nuclear Information System (INIS)

Repussard, Jacques; Dufer, Bruno

2015-06-01

After a discussion of the importance of the societal responsibility of the IRSN as a collective approach, and as an asset for nuclear safety, this report first addresses how to preserve the environment and to manage the risks (reduction of carbon print in the policy of trips and travels, improvement of energy efficiency of IRSN buildings). It describes how to maintain the social commitment at a high level, how to develop responsible purchases and sales, how to strengthen relationships between stakeholders

Adaptive mesh refinement for a finite volume method for flow and transport of radionuclides in heterogeneous porous media

International Nuclear Information System (INIS)

Amaziane, Brahim; Bourgeois, Marc; El Fatini, Mohamed

2014-01-01

In this paper, we consider adaptive numerical simulation of miscible displacement problems in porous media, which are modeled by single phase flow equations. A vertex-centred finite volume method is employed to discretize the coupled system: the Darcy flow equation and the diffusion-convection concentration equation. The convection term is approximated with a Godunov scheme over the dual finite volume mesh, whereas the diffusion-dispersion term is discretized by piecewise linear conforming finite elements. We introduce two kinds of indicators, both of them of residual type. The first one is related to time discretization and is local with respect to the time discretization: thus, at each time, it provides an appropriate information for the choice of the next time step. The second is related to space discretization and is local with respect to both the time and space variable and the idea is that at each time it is an efficient tool for mesh adaptivity. An error estimation procedure evaluates where additional refinement is needed and grid generation procedures dynamically create or remove fine-grid patches as resolution requirements change. The method was implemented in the software MELODIE, developed by the French Institute for Radiological Protection and Nuclear Safety (IRSN, Institut de Radioprotection et de Surete Nucleaire). The algorithm is then used to simulate the evolution of radionuclide migration from the waste packages through a heterogeneous disposal, demonstrating its capability to capture complex behavior of the resulting flow. (authors)

Advanced modeling of the size poly-dispersion of boiling flows

International Nuclear Information System (INIS)

Ruyer, Pierre; Seiler, Nathalie

2008-01-01

Full text of publication follows: This work has been performed within the Institut de Radioprotection et de Surete Nucleaire that leads research programs concerning safety analysis of nuclear power plants. During a LOCA (Loss Of Coolant Accident), in-vessel pressure decreases and temperature increases, leading to the onset of nucleate boiling. The present study focuses on the numerical simulation of the local topology of the boiling flow. There is experimental evidence of a local and statistical large spectra of possible bubble sizes. The relative importance of the correct description of this poly-dispersion in size is due to the dependency of (i) main hydrodynamic forces, like lift, as well as of (ii) transfer area with respect to the individual bubble size. We study the corresponding CFD model in the framework of an ensemble averaged description of the dispersed two-phase flow. The transport equations of the main statistical moment densities of the population size distribution are derived and models for the mass, momentum and heat transfers at the bubble scale as well as for bubble coalescence are achieved. This model introduced within NEPTUNE-CFD code of the NEPTUNE thermal-hydraulic platform, a joint project of CEA, EDF, IRSN and AREVA, has been tested on boiling flows obtained on the DEBORA facility of the CEA at Grenoble. These numerical simulations provide a validation and attest the impact of the proposed model. (authors) [fr

Mortality risk in the french cohort of uranium miners: extended follow-up 1946-1999

International Nuclear Information System (INIS)

Blandine Vacquier; Dominique Laurier; Sylvaine Caer; Benoit Quesne

2006-01-01

Since the 1970's, exposure to radon and to its radioactive decay products has been studied in relation to lung cancer risk among cohorts of miners [1-3]. These studies concluded that cumulative exposure to radon was associated with an increased risk of death from lung cancer. In 1988, the International Agency for Research on Cancer (IARC) classified radon as a known pulmonary human carcinogen [4]. The French cohort of uranium miners has been established in order to assess the mortality risk of miners exposed to low levels of radon and its decay products as well as to other occupational hazards. The primary aim of the cohort study is the quantification of the relationship between cumulated radon exposure and risk of lung cancer death. The study has been conducted by the Institut de Radioprotection et de Surete Nucleaire (IRSN) since 1982, in collaboration with the Occupational Medical Service of COGEMA. The French Data Protection Authority (CNIL) gave approval for this study. Previous analyses have demonstrated an excess of lung cancer death associated with radon exposure. These results regarding lung cancer have been presented in several publications and congress [5-11]. In 2004, the follow-up of this cohort was extended from 31 December 1994 through 31 December 1999. The extension of the follow-up increases the statistical power of the cohort. The present article describes the extended cohort and the analysis of mortality based on the follow-up of the cohort to end of 1999. (authors)

IRSN. Contract of objectives and performance 2014-2018

International Nuclear Information System (INIS)

Le Drian, Jean-Yves; Royal, Segolene; Macron, Emmanuel; Vallaud-Belkacem, Najat; Touraine, Marisol; Fioraso, Genevieve; Repussard, Jacques; Le Guludec, Dominique

2014-01-01

After an introduction which presents and comments the IRSN missions, the achievements of the previous contract, IRSN strengths and improvement perspectives, elements of context, and the contract scope and follow-up, this report presents and describes the three strategic areas of improvement: research, expertise and transparency. One or more indicators are defined for each area as well as a quantitative target (number of publications or actions per year). Objectives are then defined regarding security, safety and non proliferation, radiation protection, and crisis situation. Indicators and targets are as well defined for the various identified or defined associated actions or publications. They notably concern expertise missions for safety authorities, the ability to provide a response adapted to safety stakes with a guaranteed integration of lessons learned from the Fukushima accident, the ability to respond to the evolutions of the nuclear fleet (including in terms of dismantling and waste management), the ability to provide expertise and technical support for a better nuclear material safety, for a better protection of radioactive sources against malevolent actions, to contribute to the international struggle against nuclear threats and to the implementation of international treaties (non proliferation treaty, ban of chemical weapons), the implementation of control and assessment actions regarding the exposure to ionizing radiations, the ability to provide responses in the field of the assessment of radiological risks and of the protection against them, the contribution to a better knowledge of the effects of ionizing radiations, the contribution to the development of doctrines and to the improvement of national and international organisations for the management of a radiological or nuclear crisis. A third chapter addresses objectives related to IRSN governance, knowledge management, and financial management. Indicators and targets are also defined. All these

IRSN-ANCCLI partnership. IRSN-ANCCLI seminar - Safety challenges after the Fukushima accident - January 2012

International Nuclear Information System (INIS)

Compagnat, Gilles; Revol, H.; Rousselet, Yannick; Sene, Monique; Lheureux, Yves; Laurent, Michel; Lavarenne, Caroline; Jorel, M.; Houdre, Thomas; Lachaume, Jean-Luc

2012-01-01

After a synthesis, this document contains the contributions (Power Point presentations) of a seminar which addressed the following topics: remarks by the HCTISN on the process of complementary safety assessments, analysis and discussion by the GSIEN on reports of complementary assessment of safety of nuclear installations with respect to the Fukushima accident, opinion of the Gravelines local information commission (CLI) on the complementary safety assessment report for the Gravelines nuclear power plant, stage point of the Manche INTERCLI work-group on the safety of nuclear installations after Fukushima, presentation by the IRSN of the complementary safety assessments, and opinion of the ASN on complementary safety assessments (ECS) of priority nuclear installations

Ir/Sn dual-reagent catalysis towards highly selective alkylation of ...

Indian Academy of Sciences (India)

Wintec

Organometallic; bimetallic; catalysis; alkylation; benzyl alcohol; iridium, tin. 1. Introduction ... cording to our proposal, the oxidative addition of tin(IV) halides across a ..... 33. 4. Conclusion. In summary, we have demonstrated here an Ir/Sn.

IRSN-ANCCLI partnership. ANCCLI-IRSN seminar: Safety challenges after the Fukushima accident - September 2011

International Nuclear Information System (INIS)

Compagnat, Gilles; Laurent, Michel; Baumont, David; Rebour, Vincent; Quentin, Pascal

2011-09-01

Presented under the form of Power Point presentations, the contributions of this seminar proposed: a presentation by the ASN of the French context and of what is at stake with the complementary safety assessments of the French nuclear power plants, a report of the activities the three local information commissions of the Manche district within the context created by the Fukushima accident, and discussions by IRSN experts of the main safety challenges related to seismic hazard (discussion of the robustness of nuclear installations in this respect), to flooding (risk assessment), to a loss of cooling systems and loss of electric supplies, and to crisis management. Finally, a synthesis of the seminar is proposed

French regulation and waste management

International Nuclear Information System (INIS)

1984-08-01

The organization and the role played by French safety authorities for waste management are described. The French policy for storage and conditioning: basic objectives and waste management optimization are specified. Safety requirements are based on the barrier principle, they are mentioned for packaging and storage. The ''Institut de Protection et Surete Nucleaire'' deals not only with safety analysis but also help the ''autorites ministerielles'' for the development of fundamental safety rules. Examples for spent fuel storage and radioactive materials transport are treated in appendixes [fr

Evaluation of feed and bleed cooling mode in case of total loss of feedwater on 900 MWe PWR

International Nuclear Information System (INIS)

Champ, M.; Cornille, Y.

1989-07-01

The physical studies carried out with the CATHARE code to assess the feed and bleed procedure developed in order to cope with the total loss of feed water on a 900 MWe PWR are presented. These studies allowed the definition of the maximum delays of intervention which would prevent the core from uncovering. Different cases of equipment availability are considered. The data generated will be used in the 900 MWe Probabilistic Safety Assessment which is under way at the Institut de Protection et de Surete Nucleaire

IRSN's viewpoint on the safety and radiation protection of French nuclear power plants in 2007

International Nuclear Information System (INIS)

2009-01-01

This report presents the viewpoint of the IRSN on the safety and radiation protection of EDF's nuclear power plants (NPPs) in operation during 2007. It does not aim to be exhaustive but rather to highlight the points the IRSN considers important for safety. Contributing to maintaining a high level of safety and radiation protection in nuclear facilities in service is one of the seven challenges of the objectives contract signed between the French Government and the IRSN. Safety demands constant vigilance on the part of all the players involved. It is never definitively acquired and must remain a priority and continuously progress, with the plant operator remaining the first entity responsible for the safety of its facility. For the IRSN, part of this mission firstly involves carefully examining and taking into consideration national and international experience feedback, and new scientific knowledge resulting from research. The implementation of improvements, whether technical or organizational or relating to human skills, then comes secondly. This report comprises four sections. In the first section, the IRSN presents the main trends that emerged from its overall review of the safety of the in-service nuclear power plants. The second section addresses the events that have marked the year due to their impact on safety. It also presents a synthesis of the radiation protection events. The third section is devoted to anomalies displaying a generic nature for several power plants. The last section covers the significant changes implemented or scheduled. These are generally modifications or plans of action intended to improve safety performance in the operation or design of the facilities. In spite of sometimes significant disparities in the results between power plants, the IRSN draws the following conclusions from its global review of the year 2007. First of all, no event had serious consequences in the fields of either safety or radioprotection. This good result must

Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

Energy Technology Data Exchange (ETDEWEB)

Lacour, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P. [S.E.M. Hispano-Suiza, 92 - Colombes (France)

1964-07-01

In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines

Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

Energy Technology Data Exchange (ETDEWEB)

Lacour, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P [S.E.M. Hispano-Suiza, 92 - Colombes (France)

1964-07-01

In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines comprennent la seismicite

Protection of environment. Orientation of I.R.S.N

International Nuclear Information System (INIS)

2005-04-01

The Institute of I.R.S.N. has the expertise and research missions in the following area: nuclear safety, reliability of radioactive and fissile materials transport, protection of man and environment against ionizing radiations; protection and monitoring of nuclear matters, protection of installations and transports of radioactive and fissile materials against malevolence. (N.C.)

Overview of IRSN R and D activities on severe accidents

International Nuclear Information System (INIS)

Chaumont, B.; Raimond, E.; Dorsselaere, J.P. Van; Simondi-Teisseire, B.

2009-01-01

IRSN activities on SA include safety assessment for existing and future nuclear power plants and experimental reactors, level 2 Probabilistic Safety Assessment (PSA), development of simulation codes and realization of experiments. R and D concerns the following phenomena: fission products behaviour, in particular iodine and ruthenium chemistry (CHIP and EPICUR experiments); core melting and reflooding of damaged cores (MOZART, BECARRE and PEARL experiments); Molten-Core-Concrete-Interaction; thermo-mechanical behaviour of the reactor coolant system and the vessel; direct containment heating, steam explosion; hydrogen distribution and combustion in containment. Other activities concern integration of knowledge into SA codes, validation of the codes, and benchmarking activities. The main codes developed at IRSN are the ASTEC integral code and the detailed codes such as M3CD for fuel coolant interaction and TONUS for hydrogen risk assessment. One essential application of the SA codes is the systematic analysis of the different possible scenarios in the frame of the development of level 2 PSA. (authors)

The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay; Formation des scientifiques et des techniciens au Centre d'Etudes Nucleaires de Saclay

Energy Technology Data Exchange (ETDEWEB)

Debiesse, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' waeated (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author)Fren. [French] Les besoins considerables actuels et previsibles en chercheurs et scientifiques necessites par l'avevement de l'energie nucleaire imposaient au Commissariat a I'Energie atomique un effort particulier pour augmenter la formation quantitative et qualitative des scientifiques. Les moyens les plus divers ont ete mis en oeuvre: 1- Creation de l'Institut National des Sciences et Techniques Nucleaires par decret de la Presidence du Conseil et de l'Education Nationale en date du 18.6.57. Cet Institut d'Enseignement Superieur (250 etudiants) donne des cours en: genie atomique, mecanique quantique, theorie et technique des Accelerateurs de particules, metallurgie speciale, radiobiologie

Fast neutron spectrometry by bolometers lithium target for the reduction of background experiences of direct detection of dark matter

International Nuclear Information System (INIS)

Gironnet, J.

2010-01-01

Fast neutron spectrometry is a common interest for both direct dark matter detection and for nuclear research centres. Fast neutrons are usually detected indirectly. Neutrons are first slowed down by moderating materials for being detected in low energy range. Nevertheless, these detection techniques are and are limited in energy resolution. A new kind of fast neutron spectroscopy has been developed at the Institut d'Astrophysique Spatiale (IAS) in the aim of having a better knowledge of neutron backgrounds by the association of the bolometric technique with neutron sensitive crystals containing Li. Lithium-6 is indeed an element which has one the highest cross section for neutron capture with the 6 Li(n,α) 3 H reaction. This reaction releases 4,78 MeV tagging energetically each neutron capture. In particular for fast neutrons, the total energy measured by the bolometer would be the sum of this energy reaction and of the incoming fast neutron energy. To validate this principle, a spectrometer for fast neutrons, compact and semi-transportable, was built in IAS. This cryogenic detector, operated at 300 - 400 mK, consists of a 0.5 g LiF 95% 6 Li enriched crystal read out by a NTD-Ge sensor. This PhD thesis was on the study of the spectrometer characteristics, from the first measurements at IAS, to the measurements in the nuclear research centre of the Paul Scherrer Institute (PSI) until the final calibration with the Amande instrument of the Institut de Radioprotection et de Surete Nucleaire (IRSN). (author)

Multi-scale analysis of nuclear reactor thermal-hydraulics-first applications using the NEPTUNE platform

International Nuclear Information System (INIS)

Guelfi, A.; Boucker, M.; Mimouni, S.; Bestion, D.; Boudier, P.

2005-01-01

The NEPTUNE project aims at building a new two-phase flow thermal-hydraulics platform for nuclear reactor simulation. EDF (Electricite de France) and CEA (Commissariat a l'Energie Atomique) with the co-sponsorship of IRSN (Institut de Radioprotection et Surete Nucleaire) and FRAMATOME-ANP, are jointly developing the NEPTUNE multi-scale platform that includes new physical models and numerical methods for each of the computing scales. One usually distinguishes three different scales for industrial simulations: the 'system' scale, the 'component' scale (subchannel analysis) and CFD (Computational Fluid Dynamics). In addition DNS (Direct Numerical Simulation) can provide information at a smaller scale that can be useful for the development of the averaged scales. The NEPTUNE project also includes work on software architecture and research on new numerical methods for coupling codes since both are required to improve industrial calculations. All these R and D challenges have been defined in order to meet industrial needs and the underlying stakes (mainly the competitiveness and the safety of Nuclear Power Plants). This paper focuses on three high priority needs: DNB (Departure from Nucleate Boiling) prediction, directly linked to fuel performance; PTS (Pressurized Thermal Shock), a key issue when studying the lifespan of critical components and LBLOCA (Large Break Loss of Coolant Accident), a reference accident for safety studies. For each of these industrial applications, we provide a review of the last developments within the NEPTUNE platform and we present the first results. A particular attention is also given to physical validation and the needs for further experimental data. (authors)

IRSN-ANCCLI partnership. Two days for more information on nuclear wastes - April 2013

International Nuclear Information System (INIS)

El Jammal, Marie-Helene; Tichauer, Michael; Pellegrini, Delphine; Lehtonen, Markku; Sene, Monique; Mays, Claire; Tallec, Michele; GILLOIRE, Christine; Chantrenne, Nicolas; Bernet, Claude; Castel, Cecile

2013-04-01

During the first day, the contributions addressed the issue of radioactive wastes. These contributions (Power Point presentations) addressed the following topics: discussion of the IRSN opinion survey and perception of radioactive wastes in France, a retrospective of radioactive waste management in France, the inventory of radioactive wastes in France, an international overview of the management of the different wastes (high-level, intermediate-level, long-lived wastes, so on), the different sites of radioactive waste disposal, the on-site warehousing of wastes, the Cigeo project for the storage of high-level and intermediate-level long-lived wastes (location, sizing, principle, handling operations, waste routing, reversibility, authorization process), presentation of the activities of the Cigeo work-group. A paper proposes a synthesis of discussions. The second day addressed the Cigeo project information files: opinion of the ASN in 2006 on researches related to high level and long life waste management, the main safety challenges of the Cigeo project as they are perceived and analysed by the IRSN when informing the ANDRA files (risks in operation phase, IRSN opinion on ANDRA's answers). The activities of the GPMDR (Permanent Group on Radioactive Materials and Wastes) about the Cigeo project are then debated. A synthesis of discussion is proposed

Progress report I.R.S.N. 2002

International Nuclear Information System (INIS)

2003-01-01

This progress report is divided in three parts. The first one explains the missions of I.R.S.N. and its organisation. The second part concerns the activities: to protect man and environment, contribution to the safety of installations and transports, to look after the non proliferation, to be a driving force in the international relations, to contribute to the information and training. The third part is relative to the quality and means of the development, to continue the quality objectives, the human resources and social relations, the budget in 2002. (N.C.)

IRSN's Position on Safety and Radiation Protection at Nuclear Power Plants in France in 2013

International Nuclear Information System (INIS)

2015-01-01

This report does not find any notable change in significant safety-related events from the previous report in 2012. Nevertheless, it confirms the increase in the number of significant radiation protection-related events observed since 2010. IRSN notes that the overwhelming majority of events that occurred in 2013 had no significant impact on plant safety and no consequences for the health of workers and the public. The analysis confirms that EDF's efforts appear to be successful in handling the main causes of certain types of events such as periodic tests that had been increasing in recent years. Nevertheless, vigilance over organizational and human aspects is still necessary during a period of significant staff turnover. IRSN has highlighted the considerable progress protecting nuclear plants from internal and external hazards that led or will lead EDF to implement modifications to its reactors. Finally, IRSN continues to pay particular attention to EDF's efforts to improve reactor safety as a result of stress tests performed after the disaster at the Fukushima-Daiichi Nuclear Power Plant in Japan on 11 March 2011. In the report, IRSN also provides its analysis of several events and anomalies that it considered the most significant in 2013

Crisis management during the SOCATRI incident in July 2008: lessons learned by the IRSN

International Nuclear Information System (INIS)

Champion, D.

2010-01-01

This report describes the successive events which occurred in July 2008 in the SOCATRI plant where a uranium-bearing solution was accidentally released, causing a temporary pollution of two rivers. Then, he reports how this event has been managed, firstly through a mobilization of public authorities and early decisions, secondly through sampling and measurements performed by the IRSN (the management of the obtained results is also commented), thirdly through expertise investigations by the IRSN, fourthly through relationship with local authorities, and finally through media and public information. For each of these aspects, the author discusses the lessons learned, and proposes ways to improve the management of such an accident

IRSN - Annual Report 2013. Financial Report 2013. Enhancing nuclear safety

International Nuclear Information System (INIS)

Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Aurelle, Jacques; Bigot, Marie-Pierre; Bruna, Giovanni; Charron, Sylvie; Clavelle, Stephanie; Cousinou, Patrick; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Dumas, Agnes; Franquard, Dominique; Laloi, Patrick; Lorthioir, Stephane; Monti, Pascale; Rollinger, Francois; Rouyer, Veronique; Rutschkovsky, Nathalie; Scott De Martinville, Edouard; Tharaud, Christine; Verpeaux, Jean-Luc; Jaunet, Camille; Hedouin, Jean-Christophe; Pascal-Heuze, Charlotte

2014-03-01

IRSN, a public entity with industrial and commercial activities, is placed under the joint authority of the Ministries of Defense, Environment, Industry, Research, and Health. It is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues. Its areas of specialization include the environment and radiological emergency response, human radiation protection in both a medical and professional capacity, and in both normal and post-accident situations, the prevention of major accidents, nuclear reactor safety, as well as safety in nuclear plants and laboratories, transport and waste treatment, and nuclear defense and security expertise. IRSN interacts with all parties concerned by these risks (public authorities, in particular nuclear safety and security authorities, local authorities, companies, research organizations, stakeholders' associations, etc.) to contribute to public policy issues relating to nuclear safety, human and environmental protection against ionizing radiation, and the protection of nuclear materials, facilities, and transport against the risk of malicious acts. This document is the 2013 issue of IRSN's activity report. Content: 1 - Organization, key figures; 2 - Strategy: Progress and main activities in 2013, Transparency and communications policy, Promoting a safety and radiation protection culture; 3 - Activities: Safety (Safety of existing facilities, Studies and researches, About defense, Conducting assessments of future facilities); Nuclear security and non-proliferation (Nuclear security activities, International non-proliferation controls); Radiation protection - environment and human health (Environmental and population exposure, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); Emergency and post-accident situations efficiency; 4 - Efficiency: Health, safety, environmental, protection and quality, Human resources

Radioactivity monitoring status in French Polynesia in 2008. Results from IRSN's monitoring network

International Nuclear Information System (INIS)

2009-01-01

Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. The task addresses two objectives: - To monitor the levels of artificial radioactivity in all sectors of the environment and in major foodstuffs; - To estimate the exposure of the Polynesian population to this artificial radioactivity. The IRSN has monitored radioactivity levels in French Polynesia, excluding the Mururoa and Fangataufa nuclear experimentation centres, since 1962. This task is realized by the IRSN's Environmental Study and Monitoring Laboratory located in Tahiti (Vairao) This monitoring was instigated at the time when atmospheric nuclear weapons testing was being performed by the major powers (the United States, the Soviet Union, the United Kingdom, France and China), causing fallout of artificial radionuclides, over several years, on a planetary scale. In French Polynesia, the IRSN is most particularly interested in fallout resulting from the 41 tests carried out by France in this region of the globe between 1966 and 1974, and in its consequent effects on the population. Today, just as in metropolitan France, the IRSN carries out monitoring as part of its mission to constantly monitor radiological protection factors. The monitoring takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes and consists of taking monthly samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. For more than 40 years, the IRSN takes part in the evaluation of the dosimetric consequences of these atmospheric depositions in French Polynesia. This laboratory is established in Tahiti. The ingestion component of this dosimetric evaluation requires to collect the most representative samples of

IRSN's viewpoint on the safety and radiation protection of French nuclear power plants in 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

This report presents the viewpoint of the IRSN on the safety and radiation protection of EDF's nuclear power plants (NPPs) in operation during 2007. It does not aim to be exhaustive but rather to highlight the points the IRSN considers important for safety. Contributing to maintaining a high level of safety and radiation protection in nuclear facilities in service is one of the seven challenges of the objectives contract signed between the French Government and the IRSN. Safety demands constant vigilance on the part of all the players involved. It is never definitively acquired and must remain a priority and continuously progress, with the plant operator remaining the first entity responsible for the safety of its facility. For the IRSN, part of this mission firstly involves carefully examining and taking into consideration national and international experience feedback, and new scientific knowledge resulting from research. The implementation of improvements, whether technical or organizational or relating to human skills, then comes secondly. This report comprises four sections. In the first section, the IRSN presents the main trends that emerged from its overall review of the safety of the in-service nuclear power plants. The second section addresses the events that have marked the year due to their impact on safety. It also presents a synthesis of the radiation protection events. The third section is devoted to anomalies displaying a generic nature for several power plants. The last section covers the significant changes implemented or scheduled. These are generally modifications or plans of action intended to improve safety performance in the operation or design of the facilities. In spite of sometimes significant disparities in the results between power plants, the IRSN draws the following conclusions from its global review of the year 2007. First of all, no event had serious consequences in the fields of either safety or radioprotection. This good result

The radiation protection of workers I.R.S.N. activity in 2005 in the field of the radiation protection management; La radioprotection des travailleurs Activite de l'IRSN en 2005 dans le domaine de la gestion de la radioprotection

Energy Technology Data Exchange (ETDEWEB)

Rannou, A.; Ameon, R.; Boisson, P.; Clairand, I.; Couasnon, O.; Franck, D.; Scanff, P.; Rehel, J.L.; Thevenet, M

2008-07-01

This report presents the main work carried out by the Institute of Radiation Protection and Nuclear Safety (I.R.S.N.) in the year 2005 for the management of occupational radiological protection. It draws up an assessment for this same year of the occupational external exposures to ionizing radiation in France on the basis of passive dosimetry data transmitted to the I.R.S.N. by the approved dosimetric laboratories. (author)

Promoting radiation protection in France and Europe. The key role of IRSN, French Technical Safety Organisation

Energy Technology Data Exchange (ETDEWEB)

Repussard, Jacques [IRSN - Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France). Direction des Affaires Internationales - Delegation aux Relations Internationales

2012-07-01

IRSN, the Institute for Radiological Protection and Nuclear Safety was set up in France under Article 5 of French Act No. 2001-398 of May 9, 2001 as the French 'Technical Safety Organization' (TSO) expert in nuclear and radiological risks. It contributes to the implementation of public policies concerning nuclear safety and security and protection of human health and environment against ionizing radiation. IRSN interacts with all the parties concerned by these policies (public authorities, operators and stakeholders) while keeping its independence of judgment. (orig.)

The IRSN Emergency Center during the Fukushima NPS Accident: Responding to Health Concerns

International Nuclear Information System (INIS)

Jourdain, J.R.; Busset, A.; Monti, P.; Vial, E.; Laloi, P.; Bottollier-Depois, J.F.; Rannou, A.; Aigueperse, J.

2012-01-01

This series of slides presents the response brought by IRSN (Institute of Radiation protection and Nuclear Safety) to the health worries of public authorities and the population about the Fukushima accident. In order to tackle this problem efficiently, IRSN decided to bring together health experts in a dedicated team within the IRSN's emergency response center. The objective of the Health Unit were to evaluate and communicate the potential health consequences for people exposed to radioactive releases in Japan and France. 6 dedicated phone lines and one e-mail address have been opened to answer questions from the French population and nationals living in Japan. During the 4 weeks following the tsunami, more than 1300 requests have been received. Another task of the Health Unit was to organize provision of dosimeters and performing measurements for nationals returning from Japan. 287 passive dosimeters have been provided, mostly for journalists and the French embassy in Tokyo, 40 active dosimeters have been provided to the French embassy in Tokyo. Among the lessons learnt we can say that the consequences of the lack of transparency for the Chernobyl accident are still present in France, that French public does not trust the politicians but is confident with information given by experts, and the most important: there is a clear lack of knowledge about radiation protection issues in the French medical communities. (A.C.)

Stakes of a cooperation: preliminary survey to CLI and the IRSN. ANCLI/IRSN meeting on the 24 March 2004

International Nuclear Information System (INIS)

Gadbois, S.; Vaillant, L.

2004-01-01

This document presents the objectives, the methodology and the results of a survey performed to local information commissions (CLI) and the IRSN (Institute of radioprotection and nuclear safety) on their expectations in terms of release monitoring and of control of the environment of nuclear installations. It also outlines the identified problems and suggests actions to solve them. The quality of these issues is defined according to five categories: quality of relationships between actors involved in monitoring, quality of indicators available to local actors, scientific quality, knowledge of health and environmental impacts, and the taking of the global environment quality into account

IRSN's monitoring strategy for former uranium mining sites: regional radiological report approach

Energy Technology Data Exchange (ETDEWEB)

Audrey, L.L.; Marie-Odile, G.; Damien, T. [Institut de radioportection et de surete nucleaire - IRSN (France)

2014-07-01

Radiological monitoring of the environment in France was one of the basic missions assigned to the IRSN upon its creation. It is performed regularly through measurement and sampling networks across France, particularly around nuclear facilities. To supplement this system and increase its effectiveness and utility, IRSN recently began issuing regional baseline reference states using radiological reporting. Application of this reporting is currently underway in regions where uranium was mined. The Dordogne river basin is one of twenty basins impacted by uranium mining. Covering some twenty sites, it was selected by IRSN for its initial mining reporting. The objective is to gain detailed knowledge of the distribution of natural radioactivity related to the presence of uranium and its radioactive decay products, including radium, in mining areas and the river basin in general. This knowledge will supplement data already available as part of AREVA's regulatory site reporting, and provide access to a baseline reference state for radioactivity in the environment at local and regional levels. Since the impact of former uranium mining sites is basically tied to water circulation, sampling projects are designed based on the drainage system. Samples are taken of water, sediment and biological indicators such as fish and aquatic plants. Samples are then analysed to determine uranium, radium and polonium concentration. An initial sampling campaign took place in October 2012. It involved an initial contact with local organisations (Regional Directorate for the Environment, Town and Country Planning and Housing (DREAL), local information and oversight committee (Clis), regional public watershed board (EPIDOR), water agencies, mayors, hunting clubs, fishing federation, farmers, etc.). It will be supplemented by a second sampling campaign in late spring 2013 designed to take into account any local issues, including those associated with local water usage (irrigation, livestock

The Sytar network: a radioactivity observatory

International Nuclear Information System (INIS)

Robeau, D.; Calmet, D.

1992-01-01

A Radiological Transmission and Early Warning System (SYTAR) connects a network of stations all over France to the Emergency Centre of the Institut de Protection et de Surete Nucleaire in Fontenay aux Roses. Under normal circumstances, radiological data collection is done in three different ways, (i) a real time transmission of total alpha and beta in aerosols and external gamma radiation measurements performed and relayed by beacons fitted with sequential filters; (ii) a transmission of recorded data containing results of alpha spectrometry: weekly beta and gamma measurements of biological indicators, (iii) in accident conditions the rate of data delivery is stepped up

Crisis management during the SOCATRI incident in July 2008: lessons learned by the IRSN; La gestion de crise lors de l'incident de socatri de juillet 2008: les lecons tirees par L'IRSN

Energy Technology Data Exchange (ETDEWEB)

Champion, D. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Direction de l' environnement et de l' intervention, 78 - La Vesinet (France)

2010-07-01

This report describes the successive events which occurred in July 2008 in the SOCATRI plant where a uranium-bearing solution was accidentally released, causing a temporary pollution of two rivers. Then, he reports how this event has been managed, firstly through a mobilization of public authorities and early decisions, secondly through sampling and measurements performed by the IRSN (the management of the obtained results is also commented), thirdly through expertise investigations by the IRSN, fourthly through relationship with local authorities, and finally through media and public information. For each of these aspects, the author discusses the lessons learned, and proposes ways to improve the management of such an accident

Stakes of a cooperation: preliminary inquiry led with the C.L.I. and I.R.S.N; Enjeux d'une cooperation: enquete prealable menee aupres de CLI et de l'IRSN

Energy Technology Data Exchange (ETDEWEB)

Gadbois, S. [MUTADIS, 75 - Paris (France); Vaillant, L. [Centre d' Etude sur l' Evaluation de la Protection dans le Domaine Nucleaire, 92 - Fontenay aux Roses (France)

2004-07-01

The national association of local commissions of information (A.N.C.L.I.) and the institute of radiation protection and nuclear safety (I.R.S.N.) agreed to define experimental actions for year 2004 within the framework of their protocol concerning the scientific and technical support brought by the institute to the local commissions of information (C.L.I) in this perspective, both organizations wished beforehand to realize an inquiry on the expectations of the C.L.I. and the I.R.S.N. in follow-up of release and surveillance of the nuclear installations environment. The present document reports objectives and methodology of the inquiry, results obtained notably by underlining the identified problems and the actions suggested to remedy it. (N.C.)

IRSN 2007 barometer: perception of risks and security by French people. Global results

International Nuclear Information System (INIS)

2007-07-01

This report presents under the form of graphs and comments the results of the annual IRSN opinion poll on matters of risk and security. The IRSN is the French Institute of Radioprotection and Nuclear Safety. Different themes are analysed: the present concerns for French people (in the present society, for the environment, about industrial risks and the image of science), the perception of expertise (who should control an installation, the role and the image of scientific experts, access to expertise documents), the public interest in risk issues (topic of interest, participation to information sessions), the attitude in front of 30 risk situations (presently perceived risks, confidence in public authorities to ensure their protection, truth about information on hazards, hierarchy of 30 situations). The last part is dedicated to the nuclear domain (nuclear risk, skill and credibility of interveners)

Comments on the A. Aurengo document entitled 'the 2003 I.R.S.N. model of Chernobylsk accident fallout in France' - 18 december 2005

International Nuclear Information System (INIS)

2006-01-01

The present document brings the principal comments of I.R.S.N. on the analysis note of the 18. december 2005 treating the 2003 I.R.S.N. model on the Chernobylsk accident fallout in France, transmitted by Mister A. Aurengo. (N.C.)

Joint scientific publication by the INSERM and IRSN concerning child leukaemia about French nuclear power stations on the Internet site of the 'International Journal of Cancer' the 4 January 2012; Publication scientifique conjointe Inserm et IRSN concernant les leucemies chez l'enfant autour des centrales nucleaires francaises sur le site internet de la revue 'International Journal of Cancer' le 4 Janvier 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-01-12

This document describes the cooperation between the INSERM and IRSN in the field of child leukaemia about nuclear power stations, and presents the published study: context and objectives, methodology (epidemiological data, geographical data), and obtained results (risks and comparison with a German study)

Ageing management of AG3NET beam tubes in ORPHEE Research

International Nuclear Information System (INIS)

Florence, Gupta; Maud, Corbel

2013-01-01

The materials used in research reactors come from the best compromise between research needs and safety issues such as integrity of equipment during their whole life. For example, aluminium alloys such as AG3NET are interesting for research reactors dedicated to the production of neutron flux since they are transparent to neutrons but they become fragile under irradiation. Therefore the evolution of material's mechanical properties under irradiation is a topic of interest for research reactors safety and operators must implement an ageing management program of equipment subject to irradiation. This kind of aluminium alloys compound is used in many French research reactors like the Jules Horowitz reactor (JHR) and ORPHEE reactor operated by the Atomic Energy and Alternative Energies Commission (CEA) or the high flux reactor (HFR) operated by the Laue-Langevin Institute (ILL). Particularly, in the ORPHEE reactor, AG3NET is used for beam tubes, located in the heavy water tank surrounding the core, which guide neutrons towards experimental stations. The failure of a beam tube in ORPHEE reactor can lead to a reactivity insertion in the core, whose effects can be managed by the control rods system. Nevertheless, to control the effects of ageing on such equipment, the operator plans to replace the beam tubes on the basis of a criterion he defined. For the ORPHEE's second periodic safety review, the operator has re-evaluated the situation of the beam tubes with regard of this criterion and has established a beam tube replacement schedule. The 'Institut de Radioprotection et de Surete Nucleaire' (IRSN), as a technical support of the French nuclear safety authority, assessed the elements presented by the CEA for this periodic safety review and concluded that the replacement criterion used for these equipment lead to reach a fragile behaviour of the materials. Thus, the breaking of several beam tubes can't be excluded but this situation can leads to severe consequences on the

Comments on the A. Aurengo document entitled 'the 2003 I.R.S.N. model of Chernobylsk accident fallout in France' - 18 december 2005; Commentaires sur le document d'A. Aurengo intitule 'Le modele IRSN 2003 des retombees de l'accident de Tchernobyl en France' - 18 decembre 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-01-15

The present document brings the principal comments of I.R.S.N. on the analysis note of the 18. december 2005 treating the 2003 I.R.S.N. model on the Chernobylsk accident fallout in France, transmitted by Mister A. Aurengo. (N.C.)

The radiation protection of workers I.R.S.N. activity in 2005 in the field of the radiation protection management

International Nuclear Information System (INIS)

Rannou, A.; Ameon, R.; Boisson, P.; Clairand, I.; Couasnon, O.; Franck, D.; Scanff, P.; Rehel, J.L.; Thevenet, M.

2008-01-01

This report presents the main work carried out by the Institute of Radiation Protection and Nuclear Safety (I.R.S.N.) in the year 2005 for the management of occupational radiological protection. It draws up an assessment for this same year of the occupational external exposures to ionizing radiation in France on the basis of passive dosimetry data transmitted to the I.R.S.N. by the approved dosimetric laboratories. (author)

Quantifying differences between computational results and measurements in the case of a large-scale well-confined fire scenario

International Nuclear Information System (INIS)

Audouin, L.; Chandra, L.; Consalvi, J.-L.; Gay, L.; Gorza, E.; Hohm, V.; Hostikka, S.; Ito, T.; Klein-Hessling, W.; Lallemand, C.; Magnusson, T.; Noterman, N.; Park, J.S.; Peco, J.; Rigollet, L.; Suard, S.; Van-Hees, P.

2011-01-01

Research Highlights: → We performed a numerical benchmark in the framework of an OECD experimental program of a pool fire in a well-confined compartment. → The benchmark involves 17 participants using 8 fire models, 3 CFD and 5 zone models. → We investigated the capabilities of validation metrics for a real large-scale fire. → Six quantities were compared during the whole fire duration. → It is important to consider more than one metric for the validation process. - Abstract: The objective of this work was to quantify comparisons between several computational results and measurements performed during a pool fire scenario in a well-confined compartment. This collaborative work was initiated under the framework of the OECD fire research program and involves the most frequently used fire models in the fire community, including field and zone models. The experimental scenario was conducted at the French Institut de Radioprotection et de Surete Nucleaire (IRSN) and deals with a full-scale liquid pool fire in a confined and mechanically ventilated compartment representative for nuclear plants. The practical use of different metric operators and their ability to report the capabilities of fire models are presented. The quantitative comparisons between measurements and numerical results obtained from 'open' calculations concern six important quantities from a safety viewpoint: gas temperature, oxygen concentration, wall temperature, total heat flux, compartment pressure and ventilation flow rate during the whole fire duration. The results indicate that it is important to use more than one metric for the validation process in order to get information on the uncertainties associated with different aspects of fire safety.

Effect of spacer grids on CHF in tube bundles

International Nuclear Information System (INIS)

Jayanti, Sreenivas; Valette, Michel

2004-01-01

Spacers grids are used to support tube bundles in steam generators and in nuclear reactor fuel assemblies. These grids interface with the flow and heat transfer in a number of ways and their effect has been studied by a number of researchers. It is known that generally they have a beneficial effect on critical heat flux (CHF) in typical nuclear reactor assemblies. However, the enhancement obtained depends on the geometric characteristics of the spacer grids as well as on the parameter range in terms of pressure, local mass velocity and quality. In the present study, the problem is approached in the context of a one-dimensional three-field model. Unlike in previous approaches, no specific modeling of the constitutive laws is made to account for spacer effects and only the geometric details such as the reduction in the cross-sectional area and the hydraulic diameter are included in the calculation which is otherwise the same as that for flow through a single tube. It is shown by comparison with literature data that this approach leads to satisfactory prediction of the thermal-hydraulic effects of spacers and that the beneficial effects of spacers on dry out can be manifested only when the entrainment rate is neither too high nor too low. Their effect on reducing the post-dry out wall temperature is also limited to certain cases. The present work has been performed as part of the EDF-CEA Neptune project also supported by the Institut de Radioprotection et de Surete Nucleaire (IRSN, France) and FRAMATOME-ANP. NEPTUNE is a new set of two phase thermalhydraulic computer codes devoted to safety analysis of nuclear power plants. (author)

A fast running method for predicting the efficiency of core melt spreading for application in ASTEC

International Nuclear Information System (INIS)

Spengler, C.

2010-01-01

The integral Accident Source Term Evaluation Code (ASTEC) is jointly developed by the French Institut de Radioprotection et de Surete Nucleaire (IRSN) and the German Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH to simulate the complete scenario of a hypothetical severe accident in a nuclear light water reactor, from the initial event until the possible radiological release of fission products out of the containment. In the frame of the new series of ASTEC V2 versions appropriate model extensions to the European Pressurised Water Reactor (EPR) are under development. With view to assessing with ASTEC the proper operation of the ex-vessel melt retention and coolability concept of the EPR with regard to melt spreading an approximation of the area finally covered by the corium and of the distance run by the corium front before freezing is required. A necessary capability of ASTEC is in a first step to identify such boundary cases, for which there is a potential that the melt will freeze before the spreading area is completely filled. This paper presents a fast running method for estimating the final extent of the area covered with melt on which a simplified criterion in ASTEC for detecting such boundary cases will be based. If a boundary case is detected the application of a more-detailed method might be necessary to assess further the consequences for the accident sequence. The major objective here is to provide a reliable method for estimating the final result of the spreading and not to provide highly detailed methods to simulate the dynamics of the transient process. (orig.)

IRSN preliminary considerations of the Fukushima event impact on the GENIV reactors

International Nuclear Information System (INIS)

Blanc, Daniel

2012-01-01

• The IRSN study aims to identify main specific safety issues for each GEN IV concept with regards to the European Nuclear Safety Regulatory Group (ENSREG) stress tests topics: → Earthquake; → Flooding; → Loss of the heat sink; →Loss of the power supply; → Combination of the two previous ones; → Severe accident management. • These main specific safety issues are identified as far as they could have a specific impact on: → Grace times; → Cliff edge effects; → Difficulties to cope with them. • The situation is different between existing reactors and for reactors not yet designed because the hazard level may be increase for the new reactors. • Nevertheless, the “hardened safety core” concept may be kept for extreme situations and will be identified on the basis of the above mentioned main specific safety issues. This analysis is a preliminary one based of the IRSN knowledge about the six GEN IV concepts issued from safety assessment already performed (in particular on the French SFRs already built) and publications

Accident of the Fukushima-Daiichi nuclear power station. Situation two years after the event - IRSN file

International Nuclear Information System (INIS)

2013-03-01

Two years after the Fukushima accident, this report proposes a review of the situation in Japan, and of the European and international actions aimed at preventing the occurrence of another nuclear accident and its radiological consequences. It is based on information available at the end of January or February 2013. After a recall of the situation in Japan and Europe in 2011 (recall of the accident, of the different simulation, calculation and information actions undertaken by the IRSN, launching of a program of additional safety assessments and of European stress tests), the report addresses the situation in Japan two years after the accident: evolution of the nuclear risk management governance, status of the Fukushima-Daiichi power station, health and environmental impact and management of the post-accidental phase, actions undertaken by the IRSN (dose assessment, cooperation in the field of severe accidents, participation to the Fukushima Dialogue). The next part details the contribution of the IRSN to the strengthening of safety and radiation protection at the international level (in relationship with international organizations: IAEA, UNSCEAR and WHO). Additional technical information is provided in appendix, as well as a report on the environmental impact of the accident, and a report on the post-accidental management of the accident

IPSN activity report 1999

International Nuclear Information System (INIS)

2000-01-01

The IPSN (Institut de Protection et de Surete Nucleaire) carries out for the Government, studies and inspections on nuclear installations at many life steps (design, realisation, exploitation, shutdown and dismantling). To obtain quality researches, the Institut performs studies in all domains concerned by the safety and its improvement. The main projects of the year 1999, in the following topics are presented: the nuclear installations and the radioactive wastes safety, the crisis and nuclear materials management, the human and the environment protection, the international activities and cooperation, the quality insurance. It provides also information on the cooperation, the budget, the human resource policy and the communication activities. (A.L.B.)

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The IPSN (Institut de Protection et de Surete Nucleaire) carries out for the Government, studies and inspections on nuclear installations at many life steps (design, realisation, exploitation, shutdown and dismantling). To obtain quality researches, the Institut performs studies in all domains concerned by the safety and its improvement. The main projects of the year 1999, in the following topics are presented: the nuclear installations and the radioactive wastes safety, the crisis and nuclear materials management, the human and the environment protection, the international activities and cooperation, the quality insurance. It provides also information on the cooperation, the budget, the human resource policy and the communication activities. (A.L.B.)

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The IPSN (Institut de Protection et de Surete Nucleaire) carries out for the Government, studies and inspections on nuclear installations at many life steps (design, realisation, exploitation, shutdown and dismantling). To obtain quality researches, the Institut performs studies in all domains concerned by the safety and its improvement. The main projects of the year 1999, in the following topics are presented: the nuclear installations and the radioactive wastes safety, the crisis and nuclear materials management, the human and the environment protection, the international activities and cooperation, the quality insurance. It provides also information on the cooperation, the budget, the human resource policy and the communication activities. (A.L.B.)

In the event of a nuclear accident in France: the IRSN makes its expertise available for the management of the post-accidental consequences

International Nuclear Information System (INIS)

Cessac, B.; Herviou, K.

2013-01-01

The lack of organisation, methodologies and strategies to respond to the post-accidental consequences of a nuclear accident in France has been point out in 2004. In 2005, a Post-accident Management Steering Committee (CODIR-PA) has been established by the French Nuclear Safety Authority (ASN) to define the first elements of an updated French doctrine on the management of situations following a nuclear accident or a radiological emergency. The process involves several partners among them IRSN which provides a technical and scientific support. Developments made by the IRSN for more than twenty years in the field of sciences of the environment, of the man health and of metrology have indeed brought a strong basis to support current reflexions. In this context, IRSN contributes to make some proposals in order to elaborate a zoning for the implementation of protective action in post-accidental situations. This zoning is focused on actions regarding locally produced foodstuffs which may be contaminated as well as on the issue of relocation of population when the ambient level of radioactivity does not allow anymore people to stay in the area. Moreover, in case of emergency situation resulting in contaminated areas, the IRSN makes as well its expertise available to public authorities by suggesting optimized strategies to manage the effects in the environment and on the population. In the prolongation of its action during the emergency phase, the IRSN must continue to mobilize its human capacities and its technical means to answer the specific needs which are posed at the time of the post-accidental phase. The first elements of doctrines of management of post-accidental situations emitted by the CODIR-PA bring a new visibility to the IRSN in its future developments, in particular on the practical and operational aspects of the expertise during an emergency. The incident that occurred in France in July 2008 has shown the central position of the IRSN as a support to the

Sensitivity and Uncertainty Analyses Applied to Neutronics Calculations for Safety Assessment at IRSN

International Nuclear Information System (INIS)

Ivanov, Evgeny; Ivanova, Tatiana; Pignet, Sophie

2013-01-01

Objective of the presentation: • Present IRSN vision relevant to validation of stand-alone neutronics codes on support of the fuel cycle and reactor safety assessment for fast neutron reactors. • Provide work status, future developments and needs for R&D working program on validation methodology for neutronics of fast systems

The IRSN's earliest assessments of the Fukushima accident's consequences for the terrestrial environment in Japan

International Nuclear Information System (INIS)

Champion, D.; Korsakissok, I.; Didier, D.; Mathieu, A.; Quelo, D.; Groell, J.; Quentric, E.; Tombette, M.; Benoit, J.P.; Saunier, O.; Parache, V.; Simon-Cornu, M.; Gonze, M.A.; Renaud, Ph.; Cessac, B.; Navarro, E.; Servant-Perrier, A.C.

2013-01-01

In 2011 the IRSN conducted several assessments of atmospheric radioactive releases due to the Fukushima Daiichi NPP accident (March 11, 2011) and of their impact on Japan's terrestrial environment. They were based on the IRSN's emergency management tools and on the abundant information and technical data gradually published in Japan. According to these assessments, the main release phase lasted from March 12 to 25, 2011 and impacted Japanese land in two events, the first on 15 and 16 March, in which the main radioactive deposits were formed, and the second from March 20 to 23, which was less significant. The highest amounts of radioactive deposits were found in an area extending upwards of several tens of kilometers northwest of the plant. Lower amounts were discontinuously scattered in an area extending up to over 250 km away. Initially composed mainly of short-lived radionuclides, the deposits' activity sharply decreased in the subsequent weeks. Since the summer of 2011, cesium-134 and cesium-137 have become the residual deposits' main components. According to IRSN estimates, in the absence of protection, the doses due to exposure to the radioactive plume during the atmospheric release phase may have been potentially higher for people who remained in coastal areas up to several tens of kilometers north and south of the damaged plant. Thereafter, people living up to 50 km northwest of the plant, outside the 20-km emergency evacuation zone, were potentially most vulnerable to residual radioactive deposits over time. (authors)

Security report on Siloe - the descriptive part. (1963); Rapport de surete de Siloe - partie descriptive (1963)

Energy Technology Data Exchange (ETDEWEB)

Ageron, P; Chatoux, J; Denielou, G; Jacquemain, M; Mitault, G; Robien, E de; Rossillon, F [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1963-07-01

This report is a full description of the site, the reactor, the building and the experimental facilities. It gives the nuclear, thermodynamic and hydrodynamic characteristics of the core. (authors) [French] Ce rapport decrit completement le site, le reacteur, les batiments et les installations experimentales. Il donne les caracteristiques nucleaires, thermodynamiques et hydrodynamiques du coeur. (auteurs)

2011 report on radioactivity monitoring in French Polynesia. Summary of results from the IRSN monitoring network

International Nuclear Information System (INIS)

Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; Cagnat, X.; Jonhson, I.; Taputu, G.; Paeamara, H.; Tamarii, R.; Temarohirani, T.; Flores, T.

2013-01-01

Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It helps to guarantee the best possible protection for the population. Carried out in Polynesia since 1962, this monitoring focuses on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) which are representative of the five archipelagoes. It consists in taking monthly samples of various kinds from the different environmental compartments (air, water, soil, food, etc.) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagoes of the region and are taken from the marine environment of the open sea, the lagoon environment and the terrestrial environment. Almost all samples are measured at the IRSN Laboratory for the Study and Monitoring of the Environment, based in Vairao on the island of Tahiti, plus a few samples at the IRSN Orsay Laboratory. The year 2011 was marked by the Fukushima nuclear accident, which occurred on March 11. Within this context, IRSN stepped up its monitoring activities in French Polynesia and was able to confirm the absence of radiological impact in New Caledonia and Polynesia. As the results of these analyses were published in the previous annual report (report DEI/SESURE 2011-40), this report does not include all the data and results relating to the accident, but provides a summary for the year 2011. As in recent years, levels of radioactivity, which fell steadily as of 1974 when French atmospheric nuclear weapons testing came to an end, were stable and very low in 2011. The residual radioactivity is mainly due to 137 Cs. In terms of additional dose, this artificial and residual radioactivity is lower than 5 μSv.yr -1 (5 micro-sieverts per year). This corresponds to less than 0.5% of exposure due to natural radioactivity in Polynesia (approximately 1000 �

IRSN annual report 2012 - including Financial report 2012

International Nuclear Information System (INIS)

Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Baudry, Michel; Bigot, Marie-Pierre; Charron, Sylvie; Clavelle, Stephanie; Cousinou, Patrick; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Dumas, Agnes; Franquard, Dominique; Goudal, Bernard; Jalouneix, Jean; Laloi, Patrick; Monti, Pascale; Richer, Gerard; Rollinger, Francois; Rouyer, Veronique; Rutschkovsky, Nathalie; Scott De Martinville, Edouard; Tharaud, Christine; Verpeaux, Jean-luc; Jaunet, Camille; Hedouin, Jean-Christophe

2013-01-01

This annual report for the French nuclear safety and radiation protection Institute (IRSN) addresses its organizational aspects (highlights, figures illustrating the activity, organizational chart, councils and committees), proposes a summary of activities and presentation of the strategy (transparency and communication policy, promotion of a safety and radiation protection culture). The main part addresses the activities regarding safety, nuclear security and non-proliferation, radiation protection of the environment and in terms of human health, and emergency and post-accidental situations. The last part addresses issues of efficiency (property, health, safety, environmental protection and quality, and human resources). A financial report is also proposed and contains a management report, financial statements, and an appendix to annual accounts

IRSN's Position on Safety and Radiation Protection at Nuclear Power Plants in France, 2012

International Nuclear Information System (INIS)

2014-01-01

After working a year to consolidate the data, the annual report on the radiation protection and safety of nuclear power plants in France gives the IRSN's independent point of view on all progress and problems concerning safety and radiation protection encountered in the French nuclear power plant fleet in 2012. The first part of the report presents the main trends that emerge from IRSN's overall assessment of the radiation protection and safety performance of currently operating nuclear power plants for the year 2012. The year 2012 has witnessed an increase in the total number of significant events. However, IRSN notes the absence in 2012 of incidents with a potentially significant impact on nuclear power plant safety, the surrounding environment or nearby communities in a context of large-scale personnel renewal. This increase can mainly be explained by EDF's implementation of an improved nonconformance detection and handling procedure which led to the identification, in 2012, of various non-conformances presumably present for several years but previously undetected. With regard to radiation protection, IRSN notes that the effective dose received by the majority of exposed workers over a period of 12 consecutive months is below the annual public radiation dose limit. Faults may occur with nuclear power plant equipment or reactor monitoring systems. Given the standardisation of EDF nuclear power plant reactors, such faults may affect an entire reactor series or even the entire reactor fleet. A few examples deemed particularly significant by IRSN are presented in the second part of this report. French nuclear reactors are subject to modifications throughout their operating lives, particularly with a view to ensuring continuous safety improvement, this is the subject of the third part of the report. Most of these modifications are the result of studies conducted within the framework of ten-yearly safety reviews, leading to the definition and

Requirements to be taken into account in the design, qualification startup and operation of electrical equipment for safety-related electrical systems

International Nuclear Information System (INIS)

1985-07-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to provide the rules to be respected in order that safety-related electrical systems can perform its function under plausible operating conditions

General rules applicable to civil works

International Nuclear Information System (INIS)

1981-07-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. For civil works, the use of the RCC. G (Design and Construction Rules for Civil works of 900 MWe PWR Nuclear Power Plants) is accepted with conditions described in this RFS

Classification of mechanical components electrical systems and civil works structures

International Nuclear Information System (INIS)

1984-12-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to define the various classifications used in French regulatory practice with regard to safety

Meteorological instrumentation

International Nuclear Information System (INIS)

1982-06-01

RFS or ''Regles Fondamentales de Surete'' (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety , while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the ''Service Central de Surete des Installations Nucleaires'' or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to specify the meteorological instrumentation required at the site of each nuclear power plant equipped with at least one pressurized water reactor

Design of the containment spray system

International Nuclear Information System (INIS)

1985-12-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The present RFS defines the functional requirements of the containment spray system and proposes certain complementary criteria or methods to be used in its equipment design

Site geological and geotechnical studies, determination of soil characteristics and soil response studies

International Nuclear Information System (INIS)

1985-08-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to specify the soil characteristics to be determined and the soil response studies to be performed as part of site geological and geotechnical studies

Requirements to be taken into account when designing safety-related mechanical components conveying or containing pressurized fluid and classified as level 2 or 3

International Nuclear Information System (INIS)

1984-12-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to specify the requirements to be taken into account when designing mechanical components conveying or containing pressurized fluid and which are in safety class 2 or 3

Stakes of a cooperation: preliminary inquiry led with the C.L.I. and I.R.S.N

International Nuclear Information System (INIS)

Gadbois, S.; Vaillant, L.

2004-01-01

The national association of local commissions of information (A.N.C.L.I.) and the institute of radiation protection and nuclear safety (I.R.S.N.) agreed to define experimental actions for year 2004 within the framework of their protocol concerning the scientific and technical support brought by the institute to the local commissions of information (C.L.I) in this perspective, both organizations wished beforehand to realize an inquiry on the expectations of the C.L.I. and the I.R.S.N. in follow-up of release and surveillance of the nuclear installations environment. The present document reports objectives and methodology of the inquiry, results obtained notably by underlining the identified problems and the actions suggested to remedy it. (N.C.)

IRSN methodological guide to conducting workplace studies in compliance with French regulations

International Nuclear Information System (INIS)

Donadille, L.; Rehel, J. L.; Deligne, J. M.; Queinnec, F.; Aubert, B.; Bottollier-Depois, J. F.; Clairand, I.; Jourdain, J. R.; Rannou, A.

2007-01-01

Under French regulations governing radiation protection of workers, dosimetric workplace studies are mandatory. However, their practical implementation is not described. IRSN has developed a guide to help stakeholders in the radiological protection of workers conduct such studies. It proposes a general methodology applicable to most cases and 'workplace sheets', which apply this methodology to specific occupational settings. At present, two sheets are available: Conventional radiology and interventional radiology. (authors)

Siloette, Siloe mock-up; Siloette, modele nucleaire de siloe

Energy Technology Data Exchange (ETDEWEB)

Delcroix, V; Jeanne, G; Mitault, G; Schulhof, P [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1964-07-01

Siloette is the Siloe mock-up. The main installations are described: various tanks, building, auxiliaries, control systems... Precis ions are given about precautions taken for using spent fuel elements. (authors) [French] Siloette est le modele nucleaire de SILOE. On decrit ses diverses installations: bassins, batiments, auxiliaires, controle... Des precisions sont donnees sur les precautions prises pour y utiliser des elements uses. (auteurs)

Organic chemistry and radiochemistry: study of chemical interactions between iodine and paint of French nuclear reactor in a severe accident situation

International Nuclear Information System (INIS)

Aujollet, Y.

2005-01-01

In Phebus (French in pile facility; PWR scale 1/5000) experiments, performed by the Institut de Radioprotection et de Surete Nucleaire, few quantities of organic iodides were registered after interaction between iodine and reactor containment paint. This study concerns all mechanisms of chemical reactions between iodine and the polymer of the paint in order to estimate the organic iodides released from the paint. At first, all the paint components had been identified. Several models of chemical sites of the polymer were synthesized and tested with iodine in different conditions of temperature and radiation. These experiments showed interactions between iodine and secondary or tertiary amines by charge transfer. In few cases, the complex of tertiary amines creates oxidation reactions. (author)

Dynamic modeling of the cesium, strontium, and ruthenium transfer to grass and vegetables

International Nuclear Information System (INIS)

Renaud, P.; Real, J.; Maubert, H.; Roussel-Debet, S.

1999-01-01

From 1988 to 1993, the Nuclear Safety and Protection Institute (Institut de Protection et de Surete Nucleaire -- IPSN) conducted experimental programs focused on transfers to vegetation following accidental localized deposits of radioactive aerosols. In relation to vegetable crops (fruit, leaves, and root vegetables) and meadow grass these experiments have enabled a determination of the factors involved in the transfer of cesium, strontium, and ruthenium at successive harvests, or cuttings, in respect of various time lags after contamination. The dynamic modeling given by these results allows an evaluation of changes in the mass activity of vegetables and grass during the months following deposit. It constitutes part of the ASTRAL post-accident radioecology model

Surveillance of health care workers exposed to ionising radiation: Rimed pilot study

International Nuclear Information System (INIS)

2008-01-01

The project so-called RIMED aimed to set up epidemiological surveillance of health care workers exposed to ionizing radiation. A pilot study was conducted in a sample of hospital personnel to examine the possibility of identifying exposed subjects in order to analyse mortality patterns according to occupational characteristics such as medical departments or occupations in a historical cohort. Seven hospitals participated in this pilot study. Health-care workers who had worn a dosimeter up to December 2003 were to be included in this cohort. The subjects' identification data were obtained from the SISERI (Systeme d'information de la surveillance de l'exposition aux rayonnements ionisants - Ionizing Radiation Exposure Monitoring Information System) database managed by the Institut de radioprotection et de surete nucleaire - Radiation Protection and Nuclear Safety Institute (IRSN). The SISERI system was in a 'pilot' phase in 2004. According to SISERI database, a total of 5126 subjects were found to have worn a dosimeter up to December 2003. The subjects' identification data were completed by the administrative services of the hospitals and occupational physicians searched for subjects' occupational data. Information required for the vital status search was satisfactorily completed only for 38% of the cohort subjects. This pilot study showed that obtaining data from SISERI database completed by hospital administrative data in 2004 led to a database of insufficient quality for epidemiological surveillance. The Institut de veille sanitaire (French Institute of Public Health Surveillance) recommends that transmission by the employers of some specific personal or occupational data of the exposed subjects should be made compulsory. In this way, SISERI system should be able to constitute any database with required quality for epidemiological surveillance of ionizing radiation exposed subjects. (authors)

Studies about pressure variations and their effects during a fire in a confined and forced ventilated enclosure: safety consequences in the case of a nuclear facility

International Nuclear Information System (INIS)

Hugues Pretrel; Laurent Bouilloux; Jerome Richard

2005-01-01

Full text of publication follows: In a nuclear facility, the cells are confined and forced ventilated and some of them are equipped with isolation devices designed to close in case of a fire. So, if a fire occurred, the pressure variations in the cell could be important. This contribution presents the safety concerns related to pressure variation effects (propagation of smokes and/or flames through the fire barriers, propagation of radioactive material) and the research works carried out by the french 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) on this topic. These research works are composed of two different studies. The first study permits to quantify the overpressure and depression levels and to reveal the influence of the fire heat release rate (HRR), of the characteristics of the cell, of the ventilation layout (especially the airflow resistances of the ventilation branches) and of the control of the fire dampers. This study is based on three sets of experimental tests performed in three large-scale facilities of various dimensions (3600 m3, 400 m3 and 120 m3 in volume) and with several settings of the ventilation network. The analysis focuses on the conditions that lead to significant overpressure and depression peaks and identifies the level of fire HRR and airflow resistances for which pressure peaks may become a safety concern. The second study allows to characterise the behaviour of sectorisation and containment equipments subject to pressure stresses. The mechanical resistance of some equipments (doors, fire dampers) subject to pressure stresses as well as the aeraulic behaviour of this equipment (gas leak rates) are determined in order to assess the potential transfer of contamination in the ventilation networks. (authors)

Statement of the IRSN on compensatory arrangements made by the Ionisos company after the significant event which occurred on June the 22, 2009 in the Pouzauges ionization installation (INB n.146)

International Nuclear Information System (INIS)

2010-01-01

This reports exposes the IRSN's opinion (the French Nuclear safety and radioprotection institute) on the actions undertaken by the Ionisos Company after a first statement issued by the IRSN after a significant event which occurred in June 2009. These actions are concerning a personnel access door and the conveyor access doors to the ionizing cell. For the first problem, the IRSN considers the solution adopted by Ionisos as a temporary one and proposes a better one which is recommended to be implemented as soon as possible. For the second one, despite statements by Ionisos on the impossibility for a person to access the ionizing cell, the IRSN states that such risk of intrusion exists and recommends actions and procedures to avoid it

Associative memories in nuclear physics; Les memoires associatives en physique nucleaire

Energy Technology Data Exchange (ETDEWEB)

Blanca, E; Carriere, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1967-07-01

Experiments in nuclear physics involve the use of large size 'memories'. After showing the difficulties arising from the use of such memories, the authors give the principles of the various programming methods which make it possible to operate the memories associatively thus benefiting from a reduction in size and better operational conditions. They attempt to estimate the shape and dimensions of an associative memory with cable connections which could be designed specially for nuclear research, contrary to those actually in service. (authors) [French] Les experiences de physique nucleaire necessitent l'emploi de 'memoires' de grandes dimensions. Apres avoir montre les inconvenients que presente l'utilisation de telles memoires, les auteurs exposent les principes des diverses methodes de programmation qui permettent d'assurer un fonctionnement des memoires sur le mode associatif donc une reduction de leurs dimensions et un meilleur usage. Ils tentent d'evaluer le format d'une memoire associative cablee qui, contrairement a celles qui existent actuellement, serait prevue specialement pour l'experimentation nucleaire. (auteurs)

IRSN 2007 scientific and technical report

International Nuclear Information System (INIS)

2008-01-01

This report presents the most significant research works and studies performed in 2007 by the French Institute of radiation protection and nuclear safety (IRSN) on different themes: radioactivity in the environment (recent advances in metrology, radioactivity migration in unsaturated media and surface water sheets, assessment of radiological sensitivity, sensitivity indicators, mass circulation modelling, geological storage in clay formation), accidents in nuclear installations (first results of tests on Phebus, study of ruthenium chemistry, UF 6 behaviour in case of accidental releases, physical phenomena and consequences of criticality accidents, thermal-hydraulic R and D), health effects of ionizing radiations (clinic oriented studies, leukaemia risk, the Envirhom program, sorting exposed populations, radiation protection, reference levels), simulation, computing tools and metrology (Monte Carlo simulation, fire modelling and numerical studies, new approaches to metrology, enrichment determination by gamma spectrometry measurements), installation safety and security studies (seismic study, characterization of active geologic faults, comparative study of a steam generator tube failure in France and in Finland on the EPR, protection of nuclear installations against flooding)

The IRSN's scientific strategy for the progress of nuclear safety, nuclear security and radiation protection

International Nuclear Information System (INIS)

2015-12-01

This publication defines the new strategy of the IRSN to fulfil its role in nuclear safety, in the protection of mankind and of the environment against ionizing radiations, and in the protection of nuclear materials, installations and transports against malevolent acts. The IRSN is also involved in public information, and as an actor and a partner in the definition of other major public policies such as research and innovation, work health or environmental health. In a first part, the report highlights these missions, the current evolution of the international scientific, technological and economic context, and briefly evokes the major scientific challenges for the next decade. The second part highlights the abilities and capacities of the IRSN to support scientific approaches and works. The main orientations are then formulated and commented: to justify scientific orientation backgrounds and means to assign, to associate final recipients to research works, to implement initiatives to develop national, European and international cooperation in the field of nuclear and radiological risks, to develop academic partnerships and to participate to national research alliances, to develop collaboration with industries, nuclear operators and actors of the medical sector, to possess tools to perform numeric simulation, to guarantee the access for the Institute to research and experimentation infrastructures and data bases, to develop methodologies and tools for aid to decision, to perpetuate knowledge and know-how for a better renewal of risk assessment. The report then presents the main questions of interest regarding radiation protection and nuclear safety

Incidents in transport of radioactive materials for civil use: IRSN draws lessons from events reported between 1999 and 2007

International Nuclear Information System (INIS)

2008-01-01

Some 900,000 packages of radioactive materials for civil use are transported each year in France. The great majority of these shipments involve radioactive materials used in the fields of medicine, pharmaceuticals, industry or property. Transport of radioactive materials linked to the nuclear fuel cycle actually represents only 15% of transport. A great variety of material is transported, differing in weight (from a few grams to tens of tons), form, activity and packaging. The associated risks are also different: radioactive contamination, external exposure to ionising radiation, chemical risk etc. In its role of technical support to safety and radioprotection authorities, IRSN's mission is to assess the design, manufacturing, testing and use of packaging and transport systems. The Institute is also involved in the management and analysis of events that occur during transport of radioactive materials. To assist with this, the IRSN manages a database which lists reported deviations, anomalies, incidents and accidents (known in a generic way as 'events') relating to transport. With an aim of reduction of the risks related to transport, the feedback resulting from the thorough analysis of the notified events is capitalized by IRSN, just as the feedback of the assessments of the safety analysis reports of the various package designs. Based on these feedbacks, IRSN proposes axes of improvement relating to package designs and transport operations, and regulatory evolutions, as well as priority topics for the inspections carried out by the French Nuclear safety authority (ASN). The IRSN has carried out a transversal analysis of all events in transport of radioactive materials that occurred in France from 1999 to 2007 as listed in its database (i.e. 901 events). For each event, some 70 parameters have been recorded from the analysis of the notifications and reports of the events, transmitted by the operators (type of event, type of package, level on the INES scale). This

ASTEC application to in-vessel corium retention

International Nuclear Information System (INIS)

Tarabelli, D.; Ratel, G.; Pelisson, R.; Guillard, G.; Barnak, M.; Matejovic, P.

2009-01-01

This paper summarizes the work done in the SARNET European Network of Excellence on Severe Accidents (6th Framework Programme of the European Commission) on the capability of the ASTEC code to simulate in-vessel corium retention (IVR). This code, jointly developed by the French Institut de Radioprotection et de Surete Nucleaire (IRSN) and the German Gesellschaft fuer Anlagen und Reaktorsicherheit mbH (GRS) for simulation of severe accidents, is now considered as the European reference simulation tool. First, the DIVA module of ASTEC code is briefly introduced. This module treats the core degradation and corium thermal behaviour, when relocated in the reactor lower head. Former ASTEC V1.2 version assumed a predefined stratified molten pool configuration with a metallic layer on the top of the volumetrically heated oxide pool. In order to reflect the results of the MASCA project, improved models that enable modelling of more general corium pool configurations were implemented by the CEA (France) into the DIVA module of the ASTEC V1.3 code. In parallel, the CEA was working on ASTEC modelling of the external reactor vessel cooling (ERVC). The capability of the ASTEC CESAR circuit thermal-hydraulics to simulate the ERVC was tested. The conclusions were that the CESAR module is capable of simulating this system although some numerical and physical instabilities can occur. Developments were then made on the coupling between both DIVA and CESAR modules in close collaboration with IRSN. In specific conditions, code oscillations remain and an analysis was made to reduce the numerical part of these oscillations. A comparison of CESAR results of the SULTAN experiments (CEA) showed an agreement on the pressure differences. The ASTEC V1.2 code version was applied to IVR simulation for VVER-440/V213 reactors assuming defined corium mass, composition and decay heat. The external cooling of reactor wall was simulated by applying imposed coolant temperature and heat transfer

Reports by the Parliamentary Office for scientific and technological assessments. Thursday, June 16, 2011. Transparency in nuclear safety; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 16 juin 2011. Transparence en matiere de surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-06-15

In a first session dedicated to modalities of transparency in the field of nuclear safety, members of the French Parliament hear and discuss the interventions of representatives of the French nuclear safety authority (ASN), AREVA, EDF, the CEA, the French institute of radiation protection and nuclear safety (IRSN), of the High committee for transparency and information on nuclear safety (HCTISN). The second session addresses the improvement of transparency and comprised interventions by representatives of the OECD and of local commissions of information (ANCCLI)

Post graduate course of radiation protection. V. 1-2; Cours post-universitaire de radioprotection. V. 1-2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

In September 1991, the General Conference of IAEA, in the resolution GC/XXXV/RES/552 demanded the Director General to formulate the propositions in the field of education and teaching of radiation protection. After its meeting in 1993, the General Conference (document GC/XXXVII/1067) a program of education in radiation protection and nuclear safety. The IAEA has chosen L'Instut national des science et techniques nucleaires (INSTN) de Saclay, France, to perform the french training for its long-term education in nuclear field. During the nine weeks in May and June 1994, 24 participants from 22 countries attended 80 courses presented by 70 teachers. The organizers have attained a successful cooperation of competent French organizations in the field of radiation protection and nuclear safety as: Institut de protection et de surete nucleaire (IPSN), Commissariat a l'energie atomique (CEA), Compagnie generales des matieres nucleaires (COGEMA), Agence nationale pour la gestion de dechets radioactif (ANDRA), Office de protection contre les raynnements ionisants (OPRI), Electicite de France (EDF), as well as outstanding specialists in the medical field. The series of these lectures are presented in these two volumes. Admitting that the education and training in the field of radiation protection and nuclear safety are responsibilities of national authorities the IAEA hopes that this published material would be widely used by the Member States as a basis for their training programs in the mentioned field.

Post graduate course of radiation protection. V. 1-2

International Nuclear Information System (INIS)

1995-01-01

In September 1991, the General Conference of IAEA, in the resolution GC/XXXV/RES/552 demanded the Director General to formulate the propositions in the field of education and teaching of radiation protection. After its meeting in 1993, the General Conference (document GC/XXXVII/1067) a program of education in radiation protection and nuclear safety. The IAEA has chosen L'Instut national des science et techniques nucleaires (INSTN) de Saclay, France, to perform the french training for its long-term education in nuclear field. During the nine weeks in May and June 1994, 24 participants from 22 countries attended 80 courses presented by 70 teachers. The organizers have attained a successful cooperation of competent French organizations in the field of radiation protection and nuclear safety as: Institut de protection et de surete nucleaire (IPSN), Commissariat a l'energie atomique (CEA), Compagnie generales des matieres nucleaires (COGEMA), Agence nationale pour la gestion de dechets radioactif (ANDRA), Office de protection contre les raynnements ionisants (OPRI), Electicite de France (EDF), as well as outstanding specialists in the medical field. The series of these lectures are presented in these two volumes. Admitting that the education and training in the field of radiation protection and nuclear safety are responsibilities of national authorities the IAEA hopes that this published material would be widely used by the Member States as a basis for their training programs in the mentioned field

National Institute for Radiological Protection and Nuclear Safety - IRSN. Annual Report 2016, Financial Report 2016

International Nuclear Information System (INIS)

2017-01-01

IRSN is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues in France and in the international arena. Its work therefore concerns a wide range of complementary fields, including environmental monitoring, radiological emergency response, radiation protection and human health in normal and accident situations, prevention of major accidents, and safety and security relating to nuclear reactors, plants, laboratories, transportation, and waste. It also carries out assessments in the nuclear defense field. In addition, IRSN contributes to government policy in nuclear safety, the protection of human health and the environment against ionizing radiation, and measures aimed at safeguarding nuclear materials, facilities and transportation operations against the risk of malicious acts. Within this context, it interacts with all the organizations concerned including public authorities, in particular nuclear safety and security authorities, local authorities, businesses, research organizations, and stakeholder associations. This document is IRSN's annual and financial report for 2016. Content: 1 - Activity Key Figures; 2 - Strategy; 3 - Panorama 2016; 4 - Activities: safety (Safety of civil nuclear facilities, Experimental reactors, Nuclear fuel cycle facilities, Human and organizational factors, Reactor aging, Severe accidents, Fuel, Criticality, Fire and containment, Natural hazards, Defense-related facilities and activities, Radioactive waste management, Geological disposal of radioactive waste); security and nonproliferation (Nuclear security, Nuclear nonproliferation, Chemical weapons ban); radiation protection - human and environment health (Environmental monitoring, Radon and polluted sites, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); emergency and post-accident situations (Emergency preparedness and response, Post

Technique of nuclear reactors controls; Technique des controles des reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Weill, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1953-12-15

This report deal about 'Techniques of control of the nuclear reactors' in the goal to achieve the control of natural uranium reactors and especially the one of Saclay. This work is mainly about the measurement into nuclear parameters and go further in the measurement of thermodynamic variables,etc... putting in relief the new features required on behalf of the detectors because of their use in the thermal neutrons flux. In the domain of nuclear measurement, we indicate the realizations and the results obtained with thermal neutron detectors and for the measurement of ionizations currents. We also treat the technical problem of the start-up of a reactor and of the reactivity measurement. We give the necessary details for the comprehension of all essential diagrams and plans put on, in particular, for the reactor of Saclay. (author) [French] Nous avons aborde le probleme de la ''Technique du Controle des reacteurs nucleaires'' dans le but de realiser le controle du reacteur de Saclay. C'est ainsi que nous avons ete amene a etudier le probleme dans son ensemble, tel qu'il se pose pour tout reacteur a uranium naturel. Ce travail traite principalement du domaine des mesures a caractere nucleaire et s'etend dans le domaine des mesures thermodynamque de niveaux, etc... mettant en relief les caracteristiques nouvelles exigees de la part des detecteurs du fait de leur utilisation dans le flux de neutrons thermiques. Dans le domaine de mesures nucleaires, nous indiquons principalement les realisations et les resultats obtenus pour les detecteurs de neutrons thermiques et pour la mesure de courants d'ionisations. Nous traitons egalement du probleme technique du demarrage d'un reacteur et du probleme de la mesure de la reactivite. Nous donnons les details necessaires a la comrehension de tous les schemas et plans de cablages essentiels mis au point, en particulier, pour le reacteur de Saclay. (auteur)

Modelling the IRSN's radio-photo-luminescent dosimeter using the MCPNX Monte Carlo code

International Nuclear Information System (INIS)

Hocine, N.; Donadille, L.; Huet, Ch.; Itie, Ch.

2010-01-01

The authors report the modelling of the new radio-photo-luminescent (RPL) dosimeter of the IRSN using the MCPNX Monte Carlo code. The Hp(10) and Hp(0, 07) dose equivalents are computed for different irradiation configurations involving photonic beams (gamma and X) defined according to the ISO 4037-1 standard. Results are compared to experimental measurements performed on the RPL dosimeter. The agreement is good and the model is thus validated

Achievements in testing of the MGA and FRAM isotopic software codes under the DOE/NNSA-IRSN cooperation of gamma-ray isotopic measurement systems

International Nuclear Information System (INIS)

Vo, Duc; Wang, Tzu-Fang; Funk, Pierre; Weber, Anne-Laure; Pepin, Nicolas; Karcher, Anna

2009-01-01

DOE/NNSA and IRSN collaborated on a study of gamma-ray instruments and analysis methods used to perform isotopic measurements of special nuclear materials. The two agencies agreed to collaborate on the project in response to inconsistencies that were found in the various versions of software and hardware used to determine the isotopic abundances of uranium and plutonium. IRSN used software developed internally to test the MGA and FRAM isotopic analysis codes for criteria used to stop data acquisition. The stop-criterion test revealed several unusual behaviors in both the MGA and FRAM software codes.

Seismic instrumentation

International Nuclear Information System (INIS)

1984-06-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The aim of this RFS is to define the type, location and operating conditions for seismic instrumentation needed to determine promptly the seismic response of nuclear power plants features important to safety to permit comparison of such response with that used as the design basis

Evaluation of potential hazards presented by the nearby industrial environment and transportation routes

International Nuclear Information System (INIS)

1982-05-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to define methods for determining risks created by potential hazards represented by the industrial environment and transportation routes in the vicinity of a PWR, in order to verify design criteria acceptability with regard to such hazards

Safety objectives and basic design for surface centres for long-term storage of solid radioactive waste with short or medium half-life and low or medium specific activity

International Nuclear Information System (INIS)

1984-06-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The role of this RFS is to define the safety objectives and the basic design philosophy for surface centres for long-term storage of packages of radioactive waste with short or medium half-life and with low or medium specific activity

General rules applicable to quality assurance

International Nuclear Information System (INIS)

1981-11-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The aim of this rule is to define a series of measures to meet these general regulatory equipments. By applying this rule, the quality assurance code of practice for nuclear power plant safety, established by the International Atomic Energy Agency (I.A.E.A.), is considered to be observed

Determination of radioactivity released from fuel to be considered in accident safety analysis

International Nuclear Information System (INIS)

1980-01-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to define a margin of conservatism on activity values used in the following safety analysis - determination of instrumentation ranges - definition of equipment accessibility to personnel - qualification of equipment to post-accident conditions - determination of waste release to the environment

Civil Works Seismic Designs

International Nuclear Information System (INIS)

1985-12-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. This rule defines: - the parameters characterizing the design seismic motions - the calculation methods - the mathematical schematization principles on which calculations are based - the use of the seismic response for the structure checking - the content of the documents to be presented

Hazards related to external flooding

International Nuclear Information System (INIS)

1984-04-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. This RFS is intended to give state-of-the-art definitions of: - an acceptable method to determine water levels to be used in flood design of a facility - facility design principles required to meet the principles above

Development in France of nuclear safety technical regulations and standards used in the licensing procedure

International Nuclear Information System (INIS)

Lebouleux, P.

1983-04-01

Initially, the Commissariat a l'Energie Atomique was the overall structure which encompassed all nuclear activities in France, including those connected with radiological protection and nuclear safety. As other partners appeared, the Authorities have laid down national regulations relative to nuclear installations since 1963. These regulations more particularly provide for the addition of prescriptions with which the applicant must comply to obtain the necessary licenses and the establishment of General Technical Regulations pertaining to nuclear safety. The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operation of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. A RFS, or a letter, can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

Experiments on the risk of sump plugging on French PWR

International Nuclear Information System (INIS)

Armand, Y.; Mattei, J.M.; Vicena, I.; Gubco, V.; Batalik, J.; Murani, J.; Davydov, M.; Melikhov, O.I.; Blinkov, V.N.

2003-01-01

The 'Institut de Radioprotection et de Surete Nucleaire' has decided to perform an experimental program of studies on the risk of sump plugging in a 900 MWe pressurized water reactor (PWR). A general overview of the literature has been conducted between October 1999 and November 2000, ending by the definition of an approach methodology and the written of technical specifications. The problem identified gave rise to an European call for tenders leading to four contracts signed in november 2001. Three contracts are managed by VUEZ (Slovakia), the last by EREC (Russia). The methodology and the facilities devoted to these studies are presented in this paper, the preliminary results observed are also presented. The objectives for 2003 to finalize the program and the safety assessment are presented. (authors)

Radioecological studies tied to the French nuclear power station programme: aims, nature and mode of execution

International Nuclear Information System (INIS)

Delile, G.

1980-01-01

Under present French practice, assessing the effects of radioactive discharges due to the various likely accident situations comes under 'L'Analyse de Surete Nucleaire' (Nuclear Safety Analysis). The assessment of radioactive discharges relating to normal working comes within the framework of radioecologic studies. Radioecology studies are undertkaen for every power station project. They consist in: - studying what is to be done with radioelements discharged as liquids or gases, - estimating their impact on the populations in the areas of influence of the power station and checking that this impact is permissible, - establishing a surveillance measuring programme for checking against the predictions made and, if required, determining the modifications to be made to the facilities or to their method of operation [fr

The nuclear law: safety. 2006-2010

International Nuclear Information System (INIS)

Bringuier, P.

2010-01-01

The author discusses the legal evolutions related to nuclear safety between 2006 and 2010. He identifies three main topics of unequal importance. Firstly, he comments the implementation of an international reference framework which has been completed at the European level and which aims at the harmonization of safety and security rules. Secondly, he comments the creation of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire). Thirdly, he comments the recast of the standard framework in order to update the French law with respect to the international reference framework. This leaded to a new distribution of power and authority, to more complete and constraining procedures, and to the definition of procedures for each step of an installation life cycle

Hearing of Mrs Marie-Pierre Comets and Mr Marc Sanson, commissioners of the Nuclear Safety Authority (ASN), as well as Mrs Marie-Claude Dupuis, general manager of the National Agency for the management of radioactive wastes (ANDRA), on the nuclear events in Cadarache

International Nuclear Information System (INIS)

2009-01-01

Representatives of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire) and of the French National Agency for the Management of Radioactive Wastes (ANDRA, Agence nationale pour la gestion des dechets radioactifs) answer questions about an incident which occurred in a workshop, where MOx fuel was produced and which is now being dismantled. It appeared that the amount of plutonium present in the gloveboxes has been largely under-assessed: 8 kg were expected, 22 kg of plutonium have already been recovered, and finally 39 kg might be recovered by the end the dismantling operations. Other issues are addressed like the ANDRA's projects of radioactive material geological storage, their technical and institutional aspects, and then again about the late declaration of the Cadarache incident

The IRES electronic seal

International Nuclear Information System (INIS)

Gourlez, P.; Funk, P.; Brochard, D.; Moreau, J.F.; Martin, J.C.

2001-01-01

In the framework of the French Support Program for the IAEA Safeguards, the 'Institut de Protection et de Surete Nucleaire' (IPSN), developed an electronic seal called Integrated and Reusable Electronic Seal (IRES) that enables independent verification by different inspectorates (IAEA, Euratom, and National Inspectorate) Furthermore, a bilateral co-ordination between Euratom and French domestic safeguards takes place in some French facilities regarding a common approach concerning the seals especially in case of crisis situation. The seal can be remotely interrogated by radio frequency and integrated to other Containment/surveillance systems by serial line RS 485. Data are authenticated and the IRESMAG software manages in the seal reader all functionalities of the seal and records inspection data compatible with the IAEA's Seal Database

Cabri - water loop a new IPSN-OECD international research program

International Nuclear Information System (INIS)

Anon.

2001-01-01

In 1993, the Institut de Protection et de Surete Nucleaire (IPSN, the French Nuclear Safety and Radiation Protection Institute) working with EDF (electric utilities) and backed by the NRC (Nuclear Regulatory Commission, USA) launched a research program, dubbed Cabri REP Na addressing uranium oxide-based fuels and MOX fuels. So far twelve tests have been conducted including eight on UO 2 fuel and four on MOX fuel. More testing is now required to determine fuel performance at higher specific burn-up levels in typical PWR (Pressurized Water Reactor) conditions, the purpose being to determine the acceptance criteria for tomorrow's fuels. IPSN has defined a new research program for the Cabri reactor. The OECD's Nuclear Energy Agency is quarterbacking the international program called 'Cabri-Water Loop'. (authors)

Operational safety of geological disposal: IRSN project 'EXREV' for developing a safety assessment strategy for the operation and reversibility of a geological repository

International Nuclear Information System (INIS)

Tichauer, M.; Pellegrini, D.; Serres, C.; Besnus, F.

2014-01-01

A high-level waste geological disposal facility is envisioned by the legislator in the French Planning Act no. 2006-739 of 28 June 2006. This act sets major milestones for the operator (Andra) in 2013 (public debate), 2015 (licensing) and 2025 (operation). In the framework of the regulatory review process, IRSN's mission is to conduct an assessment of the safety case provided by Andra at every stage of the process for the French regulator, namely the Nuclear Safety Authority (ASN). In 2005, IRSN gathered more than twenty years of research and expertise in order to provide a comprehensive appraisal of the 'Dossier 2005' prepared by Andra, related to the feasibility of a geological disposal in the Callovo-Oxfordian clay formation. At this time, the description of the operational phase was only at a preliminary stage, but this step paved the way for developing an assessment strategy of the operational phase. In this perspective, IRSN set up the EXREV project in 2008 in order to build up a doctrine and to identify key safety issues to be dealt with. (authors)

The I.R.S.N.-2003 model of Chernobylsk accident fallout in France; Le modele IRSN 2003 des retombees de l'accident de Tchernobyl en France

Energy Technology Data Exchange (ETDEWEB)

Aurengo, A

2005-12-15

In conclusion, the whole of the method impreciseness, the sometime important variation between the very simplifying hypothesis used and the available data ( especially for the air contamination and the fallout of nuclear tests), the variations between the results of the model and the measurements, its incompatible results with these ones exposed and validated in the report I.P.S.N.-1997, lead to consider that the I.R.S.N.-2003 model does not allow a reliable quantitative estimation of Chernobylsk fallout and let alone the dosimetry estimations for which it has been used. (N.C.)

Contribution to the study of several chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses; Contribution a l'etude de quelques nuisances chimiques au centre d'etudes nucleaires de Fontenay-aux-Roses

Energy Technology Data Exchange (ETDEWEB)

Megemont, C; Grau, C [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1968-10-01

From the checking of 2750 index cards of hazards, the study relates the distribution of the chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses. Those concerning the greatest number of agents in the Centre are classified according to the categories corresponding to the different conditions of working. Thus, the most important are put forward. Then, the authors rapidly make a review of hazards which may have some special interest because they appear more specific of the nuclear energy or because they are the most frequently noted on the index cards of hazards. The case of the tributylphosphate is studied more precisely. (authors) [French] A partir de l'examen de 2750 fiches de nuisances, l'etude porte sur la repartition des nuisances chimiques au Centre d'Etudes Nucleaires de Fontenay-aux-Roses. Celles qui concernent le plus grand nombre d'agents du Centre sont classees selon les categories correspondant aux differentes conditions de travail. Les plus importantes d'entre elles sont ainsi mises en evidence. | Les auteurs passent ensuite en revue, rapidement, les nuisances qui peuvent presenter un interet particulier soit parce qu'elles semblent plus specifiques de l'Energie Nucleaire, soit parce qu'on les rencontre le plus frequemment sur les fiches de nuisances. Le cas du tributylphosphate est envisage de facon plus detaillee. (auteurs)

An absolute nuclear magnetic resonance magnetometer; Magnetometre absolu a resonance magnetique nucleaire

Energy Technology Data Exchange (ETDEWEB)

Salvi, A [Commisariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1961-10-15

After an introduction in which the various work undertaken since the discovery of nuclear magnetic resonance is rapidly reviewed, the author describes briefly In the first chapter three types of NMR magnetometers, giving the advantages and disadvantages of each of them and deducing from this the design of the apparatus having the greatest number of qualities Chapter II is devoted to the crossed coil nuclear oscillator which operates continuously over a wide range (800 gamma). To avoid an error due to a carrying over the frequency, the measurement is carried out using bands of 1000 {gamma}. Chapter III deals with frequency measurements. The author describes an original arrangement which makes possible the frequency-field conversion with an accuracy of {+-} 5 x 10{sup -6}, and the differential measurement between two nuclear oscillators. The report finishes with a conclusion and a few recordings. (author) [French] Apres une introduction rappelant les divers travaux effectues en resonance magnetique nucleaire depuis sa mise en evidence, l'auteur decrit sommairement dans le premier chapitre trois types de magnetometre a R.M.N. enumerant les avantages et les inconvenients de chacun a partir desquels il projet, l'appareillage reunissant le maximum de qualites. Le chapitre II est consacre a l'oscillateur nucleaire a bobines croisees permettant un fonctionnement continu dons une large plage (800 gamma). Pour eviter une erreur due a l'entrainement de frequence, la mesure s'effectue par bandes de 1000 {gamma} chacune. Le chapitre III traite la mesure de frequence. L'auteur expose un montage original permettant la traduction frequence-champ avec une precision egale a {+-} 5.10{sup -6}, et la mesure differentielle entre deux oscillateurs nucleaires. Une conclusion et quelques enregistrements terminent ce travail. (auteur)

Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

Energy Technology Data Exchange (ETDEWEB)

Hartmann-Boutron, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1963-06-15

An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

Mechanics and electronics as auxiliary techniques in nuclear research and exploitation; Mecanique et electronique auxiliaires de la recherche et de l'exploitation nucleaire

Energy Technology Data Exchange (ETDEWEB)

Weill, J. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre d' Etudes nucleaires de Saclay, Departement Electronique, Groupe Controle des Reacteurs (France)

1959-07-01

Electronics and mechanics form the basic techniques used in the field of measurement and control in nuclear physics experiments, and in nuclear machine installations. The delegate describes some instruments typical of the use of these techniques in the fields of calculation, detection, amplification and nuclear Installations. Reprint of a paper published in 'Bulletin S.F.M.' n. 25 (3. quarter 1957) [French] L'electronique et la mecanique constituent les techniques de base utilisees clans le domaine des mesures et du controle effectues dans les experiences de physique nucleaire et dans les installations des engins nucleaires. Le Conferencier decrit plusieurs appareils caracteristiques de l'emploi de ces techniques dans les domaines du calcul, des detecteurs, de l'amplification et des lnstallations nucleaires. Reproduction d'un article publie dans le 'Bulletin S.F.M.' n. 25 (3e trimestre 1957)

Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

Energy Technology Data Exchange (ETDEWEB)

Hartmann-Boutron, F. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1963-06-15

An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

IRSN review 2011/2014. Openness to society - Review of actions, 5 years after the chart

International Nuclear Information System (INIS)

2015-01-01

After having recalled the commitments defined by the Charter for Openness to Society adopted by the IRSN in 2009, this report proposes a review of undertaken and performed actions in terms of access to information, of openness to partnership (notably with local information commissions or CLIs, and also with other local actors), of influence of the openness on the Institute work orientation, and of internal culture of openness

Epidemiological follow-up of nuclear fuel cycle workers in France: Review of IRSN's studies - 2017 report

International Nuclear Information System (INIS)

2017-10-01

This report reviews the progresses in knowledge provided by the epidemiological research conducted by the IRSN. It concerns follow-up studies of health effects of workers employed in the nuclear fuel cycle, in link with their occupational chronic exposure to ionizing radiation, from external irradiation or internal contamination

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1999, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Activity report 1998; Rapport d'activite 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1998, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Activity report 1998

International Nuclear Information System (INIS)

1998-01-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1998, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

IPSN activity report 1999

International Nuclear Information System (INIS)

1999-01-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1999, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

S.Y.L.V.E.S.T.R.E. database for quality and radioecological expertise at I.R.S.N; La base de donnees S.Y.L.V.E.S.T.R.E. au service de la qualite et de l'expertise en radioecologie a l'IRSN

Energy Technology Data Exchange (ETDEWEB)

Duffa, C. [IRSN/DEI/SESURE/LERCM, 83 - La Seyne-sur-Mer (France); Antonelli, C.; Vray, F.; Salaun, G. [CEA Cadarache, IRSN/DEI/SESURE/LERCM, 13 - Saint-Paul-lez-Durance (France); Marant, M.J. [Communication and Systemes, 13 - St Paul-Lez-Durance (France)

2007-04-15

S.Y.L.V.E.S.T.R.E. is an I.R.S.N. database, allowing improvement and storage of data concerning radioactivity measurements on environmental samples. Continuously supplied and upgraded since its creation in 1991, it is now an essential tool for quality. It is also a precious tool used by experts. Users have an easy access to the dedicated interface through internal I.R.S.N. network. They can introduce data concerning sample collections, preparations and measurements, export sections of data for checking or assessment. Several peripheral tools or programs (numerical field tablets, bar-code sample labelling, multi-criterion requests automation,...) have been developed in order to improve the application and to minimize manual data captures or replicates. (authors)

The IRSN Risk Perception Barometer: analyzing the 1997 - 2008 period and comparing expert, public and residents of a nuclear facility perceptions

International Nuclear Information System (INIS)

El Jammal, Marie H.

2008-01-01

Full text: Since 1997, IRSN conducts a yearly survey designed to understand how the French population perceives risk: the IRSN barometer. In this survey, 30 risks are investigated from three different angles: a) Seriousness of the risk; b) Trust in the authorities; c) Credibility of information given about these risks. The 30 risks include situations widely covered by the media (traffic accidents, smoking, alcohol, etc.), as well as situations of which the public can be unaware (such as radon in homes) and situations perceived as low risk (X-rays, noise, etc.). The list includes nuclear power plants, nuclear waste storage, Chernobyl pollution impacts, chemical industries, chemical waste, transportation of hazardous chemicals, etc. Statistical analysis of the answers highlighted five groups of risks in relation with a common rationale of perception by the French people. This will be presented as the first part of the paper. The conclusion will show that the risk perceptions of the French population are not at all versatile. Their perception logic is based on the perceived seriousness of the risk, on their 'trust in the protective measures taken by the French authorities' and on the perceived credibility of information. Risk perception varies greatly with age, gender, culture and level of education. We know this with the IRSN Barometer and others opinion pools. However, few surveys are carried out among experts in risk. Do they have a different perception of risk from the general public? It's the subject of a study entitled PERPLEX (Perception of Risk by the Public and Experts) who was realized in October 2004. This will be presented in the second part of the paper. The same question can be asked for the population who live near a nuclear power plant or other nuclear facility. So, in November 2007, 318 residents in the vicinity of twenty nuclear facility have answered at the IRSN's annual barometer questionnaire. The results of these three surveys will be presented

The Development of Severe Accident Codes at IRSN and Their Application to Support the Safety Assessment of EPR

International Nuclear Information System (INIS)

Caroli, Cataldo; Bleyer, Alexandre; Bentaib, Ahmed; Chatelard, Patrick; Cranga, Michel; Van Dorsselaere, Jean-Pierre

2006-01-01

IRSN uses a two-tier approach for development of codes analysing the course of a hypothetical severe accident (SA) in a Pressurized Water Reactor (PWR): on one hand, the integral code ASTEC, jointly developed by IRSN and GRS, for fast-running and complete analysis of a sequence; on the other hand, detailed codes for best-estimate analysis of some phenomena such as ICARE/CATHARE, MC3D (for steam explosion), CROCO and TONUS. They have been extensively used to support the level 2 Probabilistic Safety Assessment of the 900 MWe PWR and, in general, for the safety analysis of the French PWR. In particular the codes ICARE/CATHARE, CROCO, MEDICIS (module of ASTEC) and TONUS are used to support the safety assessment of the European Pressurized Reactor (EPR). The ICARE/CATHARE code system has been developed for the detailed evaluation of SA consequences in a PWR primary system. It is composed of the coupling of the core degradation IRSN code ICARE2 and of the thermal-hydraulics French code CATHARE2. The CFD code CROCO describes the corium flow in the spreading compartment. Heat transfer to the surrounding atmosphere and to the basemat, leading to the possible formation of an upper and lower crust, basemat ablation and gas sparging through the flow are modelled. CROCO has been validated against a wide experimental basis, including the CORINE, KATS and VULCANO programs. MEDICIS simulates MCCI (Molten-Corium-Concrete-Interaction) using a lumped-parameter approach. Its models are being continuously improved through the interpretation of most MCCI experiments (OECD-CCI, ACE...). The TONUS code has been developed by IRSN in collaboration with CEA for the analysis of the hydrogen risk (both distribution and combustion) in the reactor containment. The analyses carried out to support the EPR safety assessment are based on a CFD formulation. At this purpose a low-Mach number multi-component Navier-Stokes solver is used to analyse the hydrogen distribution. Presence of air, steam and

Information report presented, in application of article 146 of the regulation, by the commission of finances, of general economy and of the plan, about the Institute of radioprotection and nuclear safety; Rapport d'information depose en application de l'article 146 du reglement par la Commission des finances, de l'economie generale et du plan, sur l'Institut de radioprotection et de surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-04-01

This report follows a control made at the French institute of radioprotection and nuclear safety (IRSN) in order to analyse how the budget allowed to this institute is used. The report presents successively: the main missions of the IRSN (competences, activities in the Paris region), the structure of incomes and expenses (the budget allowed by the Ministry of ecology and sustainable development), the difficulties encountered during the start-up of the institute (conditions of creation, budget regulation), the debate about the fiscal deficiency (fiscal regime applied and resulting difficulties), and the perspectives of evolution of the institute. The comments made by the commission after the presentation of the report are summarized in a last part. (J.S.)

Status of radioactivity monitoring in French Polynesia in 2011. Synthesis of the results from the IRSN's monitoring network

International Nuclear Information System (INIS)

Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; Cagnat, X.

2012-11-01

Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, HivaOa, Mangareva and Tubuai) representing the five archipelagos, and consists of taking regular samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, from the lagoon environment and from the terrestrial environment. Almost all samples are measured at the Laboratory for the Study and Monitoring of the Environment IRSN, based in Vairao on the island of Tahiti. The year 2011 was marked by the Fukushima nuclear accident, which occurred on March 11. In this context, IRSN conducted a strengthened monitoring of French Polynesia, thus confirming the absence of radiological impact in Caledonia and Polynesia. The results of analyzes have been published in the previous annual report (report DEI/SESURE 2011-40), this report does not include all data and results for the year 2011, but establishes a synthesis for this year. During the year 2011, results fall under the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-sieverts per year). This value corresponds to less than 0,5 % of exposure due to natural radioactivity in Polynesia (approximately 1 000 μSv.y -1 ). (authors)

Comparative measurements performed by the IRSN, the ACRO and the CRIIRAD on some points of a pillbox of the Vaujours Fort (77)

International Nuclear Information System (INIS)

2014-01-01

As an association reported a relatively high measurement of radioactivity on the site of the Vaujours Fort, the IRSN, the ACRO and the CRIIRAD have been asked to perform comparative measurements on this site. After having briefly recalled some elements of the site history, described the areas concerned by this control, indicated the expected radioactive elements, this report presents the measurements which were to be performed: dose equivalent rate, beta radiation, hardware used by the IRSN. It presents the measurement protocol: planned protocol and implemented protocol. It comments the measurement performance: noise, selection and measurement of reference points, measurements on different points. It proposes a comparative analysis of results obtained on the different points and on a sample. Measurements are then discussed. Photos and measurement tables are provided in appendix

IRSN safety research carried out for reviewing geological disposal safety case

International Nuclear Information System (INIS)

Serres, Christophe; Besnus, Francois; Gay, Didier

2010-01-01

The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

Collective dose IRSN view on its indications and contraindications

International Nuclear Information System (INIS)

Supervil, S.

2002-10-01

The concept of collective protection appeared in 1959 in the first report of the international commission on Radiological Protection (ICRP). During the course of the next decades, ICRP gave details on the use of collective dose, in particular on its role in the process of optimization of protection. The collective dose, effective and /or equivalent, may be used to assess the dosimetric impact of an activity or a source over a group of people, to assess the number of stochastic effects that could result from the exposure of a group of people. The methods of calculating the collective dose are considered, assessment of the levels of exposure, assessment of the health effects. I.R.S.N. reminds that the collective dose constitutes an indicator of the risk of stochastic effects for example in the field of regulatory dose limits. Consequently, the collective dose cannot in any case constitute an indicator of the deterministic effects. (N.C.)

Safety and radiation protection within the French electronuclear fleet in 2014. The IRSN's opinion

International Nuclear Information System (INIS)

2015-11-01

This annual report concerns the 58 pressurized water reactors of the French electronuclear fleet which are currently being operated. After a presentation of this fleet, and a discussion of the global assessment of safety and radiation protection within this fleet (discussion of the noticed trends), this document first reports the analysis performed by the IRSN of some important events and anomalies which occurred in 2014: the presence of migrating elements in the primary circuit which resulted in the damage fuel assembly sheaths (in Saint-Laurent des Eaux), the spraying of electric equipment due to a water flow from leaky hoppers, and the risk of unavailability of important equipment due to a high temperature in the room of the emergency back-up turbo generator set. The next chapter comments significant evolutions: renewal of the command-control system for the 1300 MWe reactors, risks induced on the Gravelines nuclear plant site by the exploitation of the Dunkirk methane terminal, and internal EDF arbitrages related to declarations regarding events which occurred in Val de Loire nuclear plants. These evolutions illustrate how expertises performed by the IRSN on request by the ASN complement EDF expertises and are a contribution to the improvement of installation safety

IRSN's radiological proficiency testings: a key for managing the quality of test laboratories in charge of the environmental radioactivity survey in France?

Energy Technology Data Exchange (ETDEWEB)

Ameon, R.; Gleizes, M.; Maulard, A.; Moine, J.; Vignaud, C. [Institute for Radioprotection and Nuclear Safety, IRSN (France)

2014-07-01

In France, many actors are involved in environmental monitoring (IRSN, operators of nuclear facilities, State services, approved air quality monitoring associations, environmental protection associations, private environmental laboratories...). The French National Network for Environmental Radioactivity Monitoring (RNM) federates all these entities. RNM brings together the environmental measurement results made in a regulatory framework on the French territory and make them available to the public through a web site. The quality of these measurements is guaranteed by subjecting the test laboratories to an approval procedure under the control of the French nuclear safety authority (ASN). The approval procedure includes administrative requirements (the laboratory shall meet ISO 17025 requirements) and the participation to proficiency testings (PT) provided by IRSN in order to demonstrate their technical competence. As approvals cover all components of the environment, the five-year PT program is defined on a combination of: - 6 types of environmental matrices: water, soil/sediments, biological matrices (tea, tobacco, fish, milk,...), aerosols on filters, gas-air (activated charcoal cartridge) and ambient air (RPL dosimeters), - 17 categories of radioactive measurements: g-emitters, gross a, gross b, {sup 3}H, {sup 14}C, {sup 90}Sr/{sup 90}Y, pure b-emitters, U isotopes and U content, Th isotopes, {sup 226}Ra and decay products, {sup 228}Ra and decay products, Pu/Am, {sup 129}I/{sup 131}I, noble gases, g-dose rate. Following ISO/CEI 17043 requirements, IRSN, as an accredited PT provider is in charge of: - Preparation and dispatch of test items, - Control of the homogeneity and stability of produced test items, - Determination of the assigned values, - Analysis of the results transmitted by participants in terms of relative bias, En number and z-score, - Publication of the report. PT program managed by IRSN groups 6 to 7 interlaboratory comparisons per year. Each of

Containment Modelling with the ASTEC Code

International Nuclear Information System (INIS)

Sadek, Sinisa; Grgic, Davor

2014-01-01

ASTEC is an integral computer code jointly developed by Institut de Radioprotection et de Surete Nucleaire (IRSN, France) and Gesellschaft fur Anlagen-und Reaktorsicherheit (GRS, Germany) to assess the nuclear power plant behaviour during a severe accident (SA). It consists of 13 coupled modules which compute various SA phenomena in primary and secondary circuits of the nuclear power plants (NPP), and in the containment. The ASTEC code was used to model and to simulate NPP behaviour during a postulated station blackout accident in the NPP Krsko, a two-loop pressurized water reactor (PWR) plant. The primary system of the plant was modelled with 110 thermal hydraulic (TH) volumes, 113 junctions and 128 heat structures. The secondary system was modelled with 76 TH volumes, 77 junctions and 87 heat structures. The containment was modelled with 10 TH volumes by taking into account containment representation as a set of distinctive compartments, connected with 23 junctions. A total of 79 heat structures were used to simulate outer containment walls and internal steel and concrete structures. Prior to the transient calculation, a steady state analysis was performed. In order to achieve correct plant initial conditions, the operation of regulation systems was modelled. Parameters which were subjected to regulation were the pressurizer pressure, the pressurizer narrow range level and steam mass flow rates in the steam lines. The accident analysis was focused on containment behaviour, however the complete integral NPP analysis was carried out in order to provide correct boundary conditions for the containment calculation. During the accident, the containment integrity was challenged by release of reactor system coolant through degraded coolant pump seals and, later in the accident following release of the corium out of the reactor pressure vessel, by the molten corium concrete interaction and direct containment heating mechanisms. Impact of those processes on relevant

Nuclear energy education and training in France

International Nuclear Information System (INIS)

2010-01-01

In its continuing use of nuclear power, France faces numerous challenges, including the operation and maintenance of its existing array of reactors, waste management, the decommissioning of obsolete reactors, and research and development for future nuclear systems. All of these efforts must recognize and conform to international requirements. These activities mean that all participants in the French nuclear industry must continually update their approaches and skills, with respect to both domestic and worldwide nuclear power development. This requirement calls for the hiring and training of thousands of scientists and engineers each year in France and its partner or customer countries. Over the next ten years, domestic and international nuclear power activities in France will call for the recruitment of about 13,000 engineers with Master of Science or Ph.D. degrees, and 10,000 science technicians and operators with Bachelor of Science degrees. The chief employers will be EDF, AREVA, GDF-Suez, national agencies such as the Agence nationale pour la gestion des dechets radioactifs (ANDRA), sub-contractors, and R and D agencies such as the Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA), and the technical safety organization, Institut de Radioprotection et de Surete Nucleaire (IRSN). France has made a commitment to support countries that are ready to create the human, institutional, and technical conditions required to establish a civilian nuclear energy programme that meets all the requirements of safety, security, non-proliferation and environmental protection for present and future generations. These efforts are conducted through the France International Nuclear Agency (AFNI). In response to the need for competence-building in nuclear energy production, France now offers training opportunities in both French and English education programmes. Partnerships created by French nuclear energy participants and by AFNI can provide dedicated programmes

Nuclear biological studies in France; Les etudes de biologie nucleaires en France

Energy Technology Data Exchange (ETDEWEB)

Coursaget, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1961-07-01

On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

Dialogue around industrial sites. Synthesis of a thinking method of I.R.S.N; Concertation autour des sites industriels. Synthese d'une demarche de reflexion de l'IRSN

Energy Technology Data Exchange (ETDEWEB)

Sugier, A.; Oudiz, A. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Heriard Dubreuil, G.; Gadbois, S. [Mutadis, 94 - Vitry (France); Schneider, Th. [Centre d' Etude sur l' Evaluation de la Protection dans le Domaine Nucleaire CEPN, 92 - Fontenay aux Roses (France)

2003-12-15

The present report gives an account of results on a research work about 'the stakes of the dialogue around the follow up of nuclear and non nuclear industrial facilities' and on conclusions of a seminar, on the same subject that stood at Ville D' Avray from the 21. to 22. of January 2003. This seminar has gathered different actors (administration, experts, associations, industrial operators) concerned by the dialogue around these installations. The work has been directed by I.R.S.N. and had for object to give the knowledge of the French and International experience in matter of dialogue around nuclear and non nuclear industrial sites. (N.C.)

Evaluation by the Department de Surete Nucleaire of unsolved PWR safety problems

International Nuclear Information System (INIS)

Dupuis, M.C.; Cayol, A.; Fourest, B.

1980-04-01

The deterministic or probabilistic methods of safety analysis and the analysis of accidents used at the design and construction stage have enabled certain safety problems connected with the PWR programme in France to be identified. Some of these problems have already been stressed by the NRC whereas others are specific to the safety approach practised in France. These problems have led to the adoption of special measurements on the reactors already in operation and should be accounted for in the design of future installations. Analysis of running experience and of incidents should be used to check the validity of the steps taken at the design stage and to identify the weak points of the facilities, especially in their piloting and at the man-machine interface [fr

Activity report 1998; Rapport d'activite 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1998, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Design basis for the operational modelling of the atmospheric dispersion

International Nuclear Information System (INIS)

Doury, A.

1987-11-01

Based on the latest practices at the Institut de Protection et de Surete Nucleaire of the Commissariat a l'Energie Atomique (CEA), we shall first present the basis elements used for a simple and adequate modelling method for assessing hypothetical atmospheric pollution from transient or continuous discharge with any given kinetics under various weather conditions which are not necessarily stationary or uniform, which are likely to occur even with little or no wind. Discharges shall be considered as sequences of instantaneous successive puffs. The parameters deduced experimentally or from observations are functions of the transfer time and cover all time and space scales. The restrictions of use are indicated, especially concerning heavy gases. Finally, simple formulas are proposed for concentrations and depositions so as to be able to make a rapid estimation of the orders of magnitude with almost no computation [fr

Expert system for the investigation of safety system availability on a 900 MWe PWR

International Nuclear Information System (INIS)

Chauliac, C.; Deplanque, B.; To, L.H.

1988-01-01

A computer program of the expert system type would appear to be an elegant and effective tool for rapid diagnosis of safety system availability in accident situations. The expert system developed for this purpose by the Institut de Protection et de Surete Nucleaire (Institute for Nuclear Safety and Protection) has been described in this paper; its logic process has been examined in detail and illustrated by means of two examples. In its present form, this expert system monitors the availability of 21 main systems. In its final form (1989), 37 main systems will be tested. It will then include descriptions of between 1500 and 2000 objects and will utilize about 1000 rules. It will be run (as is presently the case) in a workstation with windowing facilities and graphic result displays which provide the highest degree of user-friendliness

Franco-German cooperation for the physical protection of the EPR reactor

International Nuclear Information System (INIS)

Jalouneix, J.; Hagemann, A.

2001-01-01

This article presents the proceeding that has been followed in the EPR (European pressurized water reactor) project concerning physical protection against malevolent actions and robbery of nuclear materials. Before the different options of the nuclear island were definitely set, a task group had been constituted to examine if these options could hamper the setting of physical protection measures that are required by the legislation of the 2 countries. Another group composed of experts from IPSN/GRS (Institut de Protection et de Surete Nucleaire / Gesellschaft fur Anlagen und Reaktorsicherheit) had the task to define common requirements concerning the physical protection of reactors in Germany and in France. In this framework the EPR project team has prepared a technical document reviewing the different dispositions that have been retained to assure the physical protection of the reactor. (A.C.)

Design basis for the operational modelling of the atmospheric dispersion

International Nuclear Information System (INIS)

Doury, A.

1987-10-01

Based on the latest practices at the Institut de Protection et de Surete Nucleaire of the Commissariat a l'Energie Atomique (CEA), we shall first present the basis elements used for a simple and adequate modelling method for assessing hypothetical atmospheric pollution from transient or continuous discharge with any given kinetics under various weather conditions which are not necessarily stationary or uniform, which are likely to occur even with little or no wind. Discharges shall be considered as sequences of instantaneous successive puffs. The parameters deduced experimentally or from observations are functions of the transfer time and cover all time and space scales. The restrictions of use are indicated, especially concerning heavy gases. Finally, simple formulas are proposed for concentrations and depositions so as to be able to make a rapid estimation of the orders of magnitude with almost no computation [fr

The impact of automation on operator performance. An explorative study

International Nuclear Information System (INIS)

Tasset, Daniel; Charron, Sylvie; Miberg, Ann-Britt; Hollnagel, Erik

1999-01-01

This study addresses the issue of human-automation interaction in nuclear power plant control rooms. It was initiated by the Institut de Protection et de Surete Nucleaire (IPSN - France) in 1996, and has been carried out in a co-operation between the Institutt for Energiteknikk (IFE) and IPSN, 1996-1998. The purpose of the study is to contribute to the understanding of how automatic systems affect operator performance in nuclear power plants. The results of the project will be used in two ways. First, they will support the identification of particular human-automation issues of interest for future human-automation studies. Second, they will be used by IPSN to initiate the development of a knowledge-based aimed at supporting the conduction of comparative analyses between different human-automation set-ups in French nuclear power plants (author) (ml)

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1999, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Radon in houses - identification of sources and pathways of transfer

International Nuclear Information System (INIS)

Robe, M.C.; Rannou, A.; Le Bronec, J.

1992-01-01

The Institut de Protection et de Surete Nucleaire (IPSN) is studying the remedial actions to reduce high concentration of radon in houses. The first step to know how to modify houses is to identify radon sources and pathways of transfer to upper floors. A pilot study in Brittany was designed to develop a simple method of diagnosis. This investigation was based on indoor and outdoor measurements of 222 Rn activity concentration in the air and 222 Rn area exhalation rate from the soils and walls, measurements of the potential alpha energy concentration of 222 Rn daughters and the ventilation rate. The structural characteristics of houses and the influence of the life style of the inhabitants were examined. Analysis of the results showed that a limited number of parameters can be selected for use in a rapid radon diagnosis. (author)

Status of 2009 radioactivity monitoring in French Polynesia. Results of IRSN's monitoring network

International Nuclear Information System (INIS)

2010-01-01

Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes, consists in regularly collecting samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagoes of that territory. They come from the marine environment of the open sea, from the marine lagoon environment and from the terrestrial environment. Almost all samples are measured at the IRSN Laboratory for the Environment Study and Monitoring, based in Vairao, Tahiti Island. The 239 samples collected in 2009 were measured by Hp-Ge low background gamma spectrometry in order to be able to characterize lowest possible radioactivity levels. The levels of activity of Pu isotopes have also been determined for 17 selected samples and tritium activities for 15 water samples. The results for the year 2009 are in the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro Sieverts per year). This value corresponds to less than 0, 5 % of exposure due to natural radioactivity in Polynesia (approximately 1000 μSv.y -1 ). (authors)

Treatment of the loss of ultimate heat sink initiating events in the IRSN level 1 PSA

International Nuclear Information System (INIS)

Dupuy, Patricia; Georgescu, Gabriel; Corenwinder, Francois

2014-01-01

The total loss of the ultimate heat sink is an initiating event which, even it is mainly of external origin, has been considered in the frame of internal events Level 1 PSA by IRSN. The on-going actions on the development of external hazards PSA and the recent incident of loss of the heat sink induced by the ingress of vegetable matter that occurred in France in 2009 have pointed out the need to improve the modeling of the loss of the heat sink initiating event and sequences to better take into account the fact that this loss may be induced by external hazards and thus affect all the site units. The paper presents the historical steps of the modeling of the total loss of the heat sink, the safety stakes of this modeling, the main assumptions used by IRSN in the associated PSA for the 900 MWe reactors and the results obtained. The total loss of the heat sink was not initially addressed in the safety demonstration of French NPPs. On the basis of the insights of the first probabilistic assessments performed in the 80's, the risks associated to this 'multiple failure situation' turned out to be very significant and design and organisational improvements were implemented on the plants. Reviews of the characterization of external hazards and of their consequences on the installations and French operating feedback have revealed that extreme hazards may induce a total loss of the heat sink. Moreover, the accident that occurred at Fukushima in 2011 has pointed out the risk of such a loss of long duration at all site units in case of extreme hazards. In this context, it seems relevant to further improve the modelling of the total loss of the heat sink by considering the external hazards that may cause this loss. In a first step, IRSN has improved the assumptions and data used in the loss of the heat sink PSA model, in particular by considering that such a loss may affect all the site units. The next challenge will be the deeper analysis of the impact of external hazards on

Information report presented, in application of article 146 of the regulation, by the commission of finances, of general economy and of the plan, about the Institute of radioprotection and nuclear safety; Rapport d'information depose en application de l'article 146 du reglement par la Commission des finances, de l'economie generale et du plan, sur l'Institut de radioprotection et de surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-04-01

This report follows a control made at the French institute of radioprotection and nuclear safety (IRSN) in order to analyse how the budget allowed to this institute is used. The report presents successively: the main missions of the IRSN (competences, activities in the Paris region), the structure of incomes and expenses (the budget allowed by the Ministry of ecology and sustainable development), the difficulties encountered during the start-up of the institute (conditions of creation, budget regulation), the debate about the fiscal deficiency (fiscal regime applied and resulting difficulties), and the perspectives of evolution of the institute. The comments made by the commission after the presentation of the report are summarized in a last part. (J.S.)

Analytic index for nuclear physicians uses; Repertoire analytique a l'usage des physiciens nucleaires

Energy Technology Data Exchange (ETDEWEB)

Ballini, R.; Barloutaud, R.; Bernas, R.; Bretonneau, P.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Joffre, H.; Laboulaye, H. de; Lesueur, C.; Leveque, A.; Moreau, J.; Naggiar, V.; Papineau, L.; Prugne, P.; Schuhl, C.; Studinowski, FJ.; Netter, F.; Raievski, V.; Valladas, G. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of new publications, always more numerous and more varied. To remedy to this facts that we tried, in the service of Nuclear Physics of the CEA, to give to the documentation a character of a collective and systematized work. The present report covers the literature appeared between first January 1950 and first July 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le premier Janvier 1950 et le premier Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

Use of integral experiments for the assessment of a new 235U IRSN-CEA evaluation

Directory of Open Access Journals (Sweden)

Ichou Raphaëlle

2017-01-01

Full Text Available The Working Party on International Nuclear Data Evaluation Co-operation (WPEC subgroup 29 (SG 29 was established to investigate an issue with the 235U capture cross-section in the energy range from 0.1 to 2.25 keV, due to a possible overestimation of 10% or more. To improve the 235U capture crosssection, a new 235U evaluation has been proposed by the Institut de Radioprotection et de Sûreté Nucléaire (IRSN and the CEA, mainly based on new time-of-flight 235U capture cross-section measurements and recent fission cross-section measurements performed at the n_TOF facility from CERN. IRSN and CEA Cadarache were in charge of the thermal to 2.25 keV energy range, whereas the CEA DIF was responsible of the high energy region. Integral experiments showing a strong 235U sensitivity are used to assess the new evaluation, using Monte-Carlo methods. The keff calculations were performed with the 5.D.1 beta version of the MORET 5 code, using the JEFF-3.2 library and the new 235U evaluation, as well as the JEFF-3.3T1 library in which the new 235U has been included. The benchmark selection allowed highlighting a significant improvement on keff due to the new 235U evaluation. The results of this data testing are presented here.

Nuclear and sustainable development; Nucleaire et developpement durable

Energy Technology Data Exchange (ETDEWEB)

Audebert, P.; Balle, St.; Barandas, Ch.; Basse-Cathalinat, B.; Bellefontaine, E.; Bernard, H.; Bouhand, M.H.; Bourg, D.; Bourgoignon, F.; Bourlat, Y.; Brunet, F.; Buclet, N.; Buquet, N.; Caron, P.; Cartier, M.; Chagneau, E.; Charles, D.; Chateau, G.; Collette, P.; Collignon, A.; Comtesse, Ch.; Crammer, B.; Dasnias, J.; Decroix, G.; Defoy, B.; Delafontaine, E.; Delcroix, V.; Delerue, X.; Demet, M.; Dimmers, G.; Dodivers, S.; Dubigeon, O.; Eimer, M.; Fadin, H.; Foos, J.; Ganiage, D.; Garraud, J.; Girod, J.P.; Gourod, A.; Goussot, D.; Guignard, C.; Heloury, J.; Hondermarck, B.; Hurel, S.; Jeandron, C.; Josse, A.; Lagon, Ch.; Lalleron, Ch.; Laurent, M.; Legrand, H.; Leveau, E

2006-07-01

On September 15. and 16., 2004, at Rene Delcourt invitation, President of the C.L.I. of Paluel and Penly, took place the 4. colloquium of the A.N.C.L.I.. Jean Dasnias, new President of the C.L.I., welcomed the colloquium. Hundred of persons participated. The place of the nuclear power in the energy perspectives of tomorrow, its assets and its weaknesses in front of the other energies and within the framework of a sustainable development, are so many subjects which were discussed. The different tackled subjects are: the stakes in the sustainable development; energy perspectives; the reactors of the fourth generation; nuclear power and transparency; sustainable development and I.R.S.N. (N.C.)

Marine radio-ecology, surveying and predicting: French coasts watched by the IRSN; In the search for finer predictions; Answering the questions of a city council before works

International Nuclear Information System (INIS)

Anon.

2012-01-01

A set of articles presents the activities and missions undertaken by the IRSN in order to control, understand and predict the behaviour of radionuclides in the sea. Twenty three measurement stations are located along the French coasts to survey the radioactivity of water, of sediments, and of sea flora and fauna. Through various programs and projects, researchers are developing always more refined models to simulate and predict the behaviour of radioactive releases in the sea, and their consequences. Beside, the IRSN intervenes as an expert, for example to assess whether there is radiological risk for workers and sea food when dredging sediments in the harbour of La Rochelle

The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay

International Nuclear Information System (INIS)

Debiesse, J.

1958-01-01

The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' was created (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author) [fr

Nuclear program of Iran. Towards de-escalation of a nuclear crisis. Advisory letter; Nucleair programma van Iran. Naar de-escalatie van een nucleaire crisis. Briefadvies

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

The Dutch government, partly at the request of the House of Representatives (Second Chamber), the AIV asked to give an opinion about the position of Iran in the region and the role of the nuclear program of Iran in the geopolitical relations, in view of the most recent developments [Dutch] De Nederlandse regering heeft, mede op verzoek van de Tweede Kamer der Staten-Generaal, de AIV gevraagd advies uit te brengen over de positie van Iran in de regio en de rol van het nucleaire programma van Iran in de geopolitieke verhoudingen hierin, mede gelet op de meest recente ontwikkelingen.

Nuclear biological studies in France; Les etudes de biologie nucleaires en France

Energy Technology Data Exchange (ETDEWEB)

Coursaget, J. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1961-07-01

On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

Material movement of medium surrounding an underground nuclear explosion; Mouvement materiel du milieu environnant une explosion nucleaire souterraine

Energy Technology Data Exchange (ETDEWEB)

Guerrini, C; Garnier, J L [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

1969-07-01

The results of measurements of the mechanical effects in the, intermediate zone around underground nuclear explosions in Sahara granite are presented. After a description of the main characteristics of the equipment used, the laws drawn up using experimental results for the acceleration, the velocity, and the material displacement are presented. These laws are compared to those published in other countries for nuclear tests in granite, in tuff and in alluvial deposits. (authors) [French] Les resultats de mesures d'effets mecaniques en zone intermediaire autour d'essais nucleaires souterrains dans le granite du Sahara sont exposes. Apres avoir decrit, dans leurs grandes lignes, les materiels utilises, on presente les lois etablies avec les resultats experimentaux pour l'acceleration, la vitesse et le deplacement materiel. Ces lois sont comparees a celles publiees a l'etranger pour des essais nucleaires dans le granite, le tuf et les alluvions. (auteur)

Statistical pulses generator. Application to nuclear instrumentation (1962); Generateur d'impulsions aleatoires. Application a l'instrumentation nucleaire (1962)

Energy Technology Data Exchange (ETDEWEB)

Beranger, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1962-07-01

This report describes a random pulses generator adapted to nuclear instrumentation. After a short survey on the statistical nature of electronic signals, the different ways for generating pulses with a Poisson's time-distribution are studied. The final generator built from a gaseous thyratron in a magnetic field is then described. Several tests are indicated : counting-rate stability, Pearson's criterion, distribution of time-intervals. Applications of the generator in 'whole testing' of nuclear instrumentation are then indicated for sealers, dead time measurements, time analyzers. In this application, pulse-height spectrums have been made by Poissonian sampling of a recurrent or random low-frequency signal. (author) [French] Cette etude decrit un generateur d'impulsions aleatoires et ses applications a l'instrumentation nucleaire. Apres un bref rappel sur la nature statistique des signaux en electronique nucleaire, sont passes en revue les principaux moyens d'obtenir des impulsions distribuees en temps suivant une loi de Poisson. Le generateur utilisant un thyratron a gaz dans un champ magnetique est ensuite decrit; diverses methodes de test sont appliquees (stabilite du taux de comptage, criterium de Pearson, spectre des intervalles ds temps). Les applications du generateur a l'electronique nucleaire dans le domaine des 'essais globaux' sont indiques: test des echelles de comptage et mesure des temps morts, test des analyseurs en temps apres division du taux de comptage par une puissance de deux, test des analyseurs multicanaux en amplitude. Pour cette derniere application, on a realise des spectres d'amplitudes suivant une loi connue, par echantillonnage poissonien d'un signal basse frequence recurrent ou aleatoire. (auteur)

Post-Fukushima complementary safety assessments. Information note on the IRSN analysis and conclusions after the expertise of Complementary Safety Assessments (ECS) reports handed to the ASN by operators, on the request of the Prime Minister, after the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This note first states the three main conclusions of the analysis performed by the IRSN of ECS (complementary safety assessments) reports made after the Fukushima accident. The IRSN noticed some biases of conformity between installations, outlines the need to make installation safety referential evolve, and that the idea that an extreme natural phenomenon could not result in a severe accident must be put into question again. Then, the report describes why and how nuclear installation safety 'hard cores' must be created in order to avoid the occurrence of incidental or accidental situations, or to implement measures aimed at handling these situations. It finally outlines the outcomes of the ECSs for the IRSN

Radiological assessment of the French environment in 2008. Synthesis of the IRSN's surveillance networks

International Nuclear Information System (INIS)

Chaptal-Gradoz, N.; Chevreuil, M.; D'amico, D.; Debayle, Ch.; Leprieur, F.; Manificat, G.; Peres, J.M.; Pierrard, O.; Tournieux, D.; Veran-Viguie, M.P.; Renaud, Ph.; Roussel-Debet, S.; Masson, O.; Pourcelot, L.; Fayolle, C.; Loyen, J.; Robe, M.Ch.; Picolo, J.L.; Gallerand, M.O.

2009-01-01

While providing many maps, graphs and tables, this report presents and comments the very large amount of data acquired in 2008 within the frame of the control by the IRSN of radioactivity levels on the French national territory by means of its different surveillance networks. After a presentation of these networks (objectives, organization, sample collection, analysis, and preparation methodologies) and of the different radionuclides present in the French environment, results are presented by installation type (electricity production nuclear centres, nuclear fuel reprocessing centres, nuclear medicine centres, nuclear waste storage centres, research centres, nuclear naval bases, etc.) and environment component (air, water ways, rain waters, continental or coastal environment, biological media, etc.)

IRSN-ANCCLI partnership. Information day: Childhood leukaemia around French nuclear power plants - April 2012

International Nuclear Information System (INIS)

Clavel, Jacqueline; Laurier, Dominique; Sommelet, Daniele; Chantal Bardelay

2012-04-01

As an epidemiological study performed by the INSERM highlighted an excess of childhood leukaemia within 5 km around nuclear power plants during the 2002-2007 period, this meeting has been organised to discuss this issue. After a presentation of these results, a contribution discusses the context and research perspectives on the relationship between childhood leukaemia and nuclear sites. After the reported debate, a contribution presents the conclusion of a work-group on childhood leukaemia and ASN works, and a last one presents the activities of a work-group gathering the ANCCLI, IRSN and InVS on the health impact of nuclear installations. A debate on these issues is reported

Dialogue around industrial sites. Synthesis of a thinking method of I.R.S.N

International Nuclear Information System (INIS)

Sugier, A.; Oudiz, A.; Heriard Dubreuil, G.; Gadbois, S.; Schneider, Th.

2003-12-01

The present report gives an account of results on a research work about 'the stakes of the dialogue around the follow up of nuclear and non nuclear industrial facilities' and on conclusions of a seminar, on the same subject that stood at Ville D' Avray from the 21. to 22. of January 2003. This seminar has gathered different actors (administration, experts, associations, industrial operators) concerned by the dialogue around these installations. The work has been directed by I.R.S.N. and had for object to give the knowledge of the French and International experience in matter of dialogue around nuclear and non nuclear industrial sites. (N.C.)

IRSN's opinion on the partial activity resumption for the Plutonium Technology Workshop (ATPu - INB 32) of the Cadarache Centre

International Nuclear Information System (INIS)

2009-10-01

As operations had been suspended for stations where fissile materials were handled in the ATPu (Atelier de Technologie du Plutonium, Plutonium Technology Workshop) of the Cadarache Centre, this document briefly describes the concerned operations (waste treatment and evacuation, glove box dismantling, transfer section dismantling), specifies and comments the measures undertaken by the operator, and gives the IRSN opinion about the resumption of the concerned activities

Focus on the studies in support of fire safety analysis. IRSN modelling approach for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Espargilliere, Julien; Meyrand, Raphael; Vinot, Thierry [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France)

2015-12-15

For a fire safety analysis, in order to comply with nuclear safety goals, a nuclear fuel facility operator has to define the elements important for safety to be maintained, even in the case of a fire. One of the key points of this fire analysis is the assessment of possible fire scenarios in the facility. This paper presents the IRSN method applied to a case study to assess fire scenarios which have the most harmful effects on safety targets. The layout consists in a central room (fire cell) containing three glove boxes with radioactive material and three electrical cabinets. This room is linked to two connecting compartments (the fire cell and these two compartments define the containment cell) and then to two corridors. Each room is equipped with a mechanical ventilation system, and a pressure cascade is established from the corridors to the central room. A fire scenario was studied with fire ignition occurring in an electrical cabinet. This scenario has a set of safety goals (prevention of fire cell and containment device failure, propagation of the fire). This case study was conducted with the IRSN code SYLVIA based on two zones modelling. Safety goals were associated with key parameters and performance criteria to be fulfilled. Modelling assumptions were defined in order to maximize physical effects of the fire. Sensitivity studies were also conducted on key parameters such as oxygen limitation, equivalent-fuel definition. Eventually, a critical analysis of the code models was carried out.

A mathematical model for cost of maritime transport. Application to competitiveness of nuclear vessels; Modele mathematique du cout de transport maritime application a la competitivite du navire nucleaire

Energy Technology Data Exchange (ETDEWEB)

Dorval, C [Commissariat a l' Energie Atomique, 75 - Paris (France)

1966-05-01

In studying the competitiveness of a nuclear merchant vessel, economic assessments in terms of figures were discarded in favor of a simplified model, which gives a clearer idea of the mechanism of the comparison between alternative vessels and the particular influence of each parameter. An expression is formulated for the unit cost per ton carried over a given distance as a function of the variables (speed and deadweight tonnage) and is used to determine the optima for conventional and nuclear vessels. To represent the freight market involved in the optimization studies, and thus in the competitiveness computation, two cases are taken into account: the tonnage to be carried annually is limited, and the tonnage to be carried annually is not limited. In both cases the optima are calculated and compared for a conventional and a nuclear vessel. Competitiveness curves are plotted as a function of the ratios of nuclear and conventional fuel costs and nuclear and conventional marginal power costs. These curves express the limiting values of the above two ratios for which the transport costs of the nuclear and conventional vessels are equal. The competitiveness curves vary considerably according to the hypothesis adopted for the freight market and the limit of tonnage carried annually. (author) [French] Pour etudier la competitivite du navire marchand nucleaire, plutot que de nous livrer a des evaluations economiques chiffrees, discutables dans l'etat actuel des etudes, nous utilisons un modele simplifie permettant de mieux saisir le mecanisme de la comparaison des navires et l'influence particuliere de chaque parametre. Nous etablissons une expression du cout unitaire de la tonne transportee sur un parcours donne en fonction des variables vitesse et port en lourd. Et nous l'utilisons pour determiner les optima des navires classiques et nucleaires. Pour representer le marche du fret qui intervient dans les etudes d'optimisation, et donc dans la recherche de la

Contribution to the study of thermal mixing between nuclear spin systems; Contribution a l'etude du melange thermique entre systemes de spins nucleaires

Energy Technology Data Exchange (ETDEWEB)

Goldmann, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1967-02-15

This work describes methods of dynamic nuclear polarization in solids based on the thermal mixing between nuclear spin systems. The description of the thermal mixing processes involves most of the fundamental aspects of the spin temperature theory. The experiments, conducted with paradichlorobenzene and para-dibromobenzene, yield a detailed confirmation of the theoretical predictions. (author) [French] Ce travail decrit des methodes de polarisation dynamique nucleaire dans les solides basees sur le melange thermique entre systemes de spins nucleaires. La description des processus de melange thermique met en jeu la plupart des aspects fondamentaux de la theorie de la temperature de spin. Les experiences, realisees avec du paradichlorobenzene et du paradibromobenzene, apportent une confirmation detaillee des previsions theoriques. (auteur)

Quality of environment monitoring: which approach to build up with local actors? ANCLI/IRSN meeting on March 24, 2004

International Nuclear Information System (INIS)

2004-01-01

This report presents and discusses the main conclusions of a survey performed among the Information Local Commission (CLIs) and the French Radioprotection and Nuclear Safety Institute (IRSN) in order to know their expectations as far the control of the environment and the monitoring of releases by nuclear installations are concerned. It also reports discussions which occurred during the presentation of these results during a meeting at Ville d'Avray

French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

Energy Technology Data Exchange (ETDEWEB)

Guerin De Montgareuil, P [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

1964-07-01

, industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l'amidon, metabolisme glucidique des tubercules irradies, radioresistance des levures

Analytic catalog for the use of the nuclear physicists; Repertoire analytique a l'usage des physiciens nucleaires

Energy Technology Data Exchange (ETDEWEB)

Ballini, R; Barloutaud, R; Bernas, R; Chaminade, R; Cohen, R; Conjeaud, M; Cotton, E; Faraggi, H; Grjebine, T; Laboulaye, H de; Lehmann, P; Leveque, A; Levi, C; Moreau, J; Naggiar, V; Olkowsky, J; Papineau, L; Papineau, L; Prugne, P; Schuhl, C; Szteinsznaider, D; Tzara, C; Valladas, G [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires; Marty, N; Renard, G [College de France, Lab. de Chimie Nucleaire (France)

1952-07-01

The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of publications, always more numerous and more varied. To remedy to this problem, we tried, at the Nuclear Physics Services of the CEA, to give to the documentation the character of a collective and systematized work. The present report covers the literature appeared between January 1, 1950 and July 1, 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le 1 Janvier 1950 et le 1 Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

Methodology used in IRSN nuclear accident cost estimates in France

International Nuclear Information System (INIS)

2015-01-01

This report describes the methodology used by IRSN to estimate the cost of potential nuclear accidents in France. It concerns possible accidents involving pressurized water reactors leading to radioactive releases in the environment. These accidents have been grouped in two accident families called: severe accidents and major accidents. Two model scenarios have been selected to represent each of these families. The report discusses the general methodology of nuclear accident cost estimation. The crucial point is that all cost should be considered: if not, the cost is underestimated which can lead to negative consequences for the value attributed to safety and for crisis preparation. As a result, the overall cost comprises many components: the most well-known is offsite radiological costs, but there are many others. The proposed estimates have thus required using a diversity of methods which are described in this report. Figures are presented at the end of this report. Among other things, they show that purely radiological costs only represent a non-dominant part of foreseeable economic consequences. (authors)

First insights from common GRS and IRSN evaluations of operational experiences for the European Clearinghouse

International Nuclear Information System (INIS)

Maqua, M.; Bertrand, R.

2012-01-01

The European Clearinghouse on Operating Experience Feedback (OEF) for NPPs was established in 2008 by several European Nuclear Safety Regulators. The technical work on common operational experience evaluation was launched at the Joint Research Center of the European Union. Main goals of the European Clearinghouse include promotion of collaboration on OEF, dissemination of the lessons learnt from NPP operational experience and promoting advanced event assessment approaches and methods. The extended knowledge of both IRSN and GRS in the evaluation of the national operating experiences in France and Germany, respectively, is used by the European Clearinghouse with the objective of receiving detailed insights on safety related topics. IRSN and GRS develop common reports on safety issues upon request of the Clearinghouse that involve a detailed review of their national event databases, and that are combined afterwards in a European Clearinghouse report including also the review carried out by the JRC on the basis of the Incident Report System (IRS) database and the US NRC Licensee Event Reports (LERs) database. The aim is to perform in-depth analyses (causes, root causes, contributing factors, actual and potential consequences, and lessons learnt) of specific OEF topics. 3 topics have been already analyzed: -) external events (Serious accidents caused by external hazards were not found in the German and French operating experience), -) ageing of components (it can be concluded that ageing management in French and German NPP is basically effective), and -) component supply (the main cause for events related to the supply of components was insufficiency during manufacturing or testing). This paper is followed by the slides of the presentation

Nuclear safety in France in 2001; La surete nucleaire en France en 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

This press dossier summarizes the highlights of nuclear safety in France in 2001: the point-of-view of A.C. Lacoste, director of the French authority of nuclear safety (ASN), the new organisation of the control of nuclear safety and radiation protection, the ASN's policy of transparency, the evolutions of nuclear fuels and the consistency of the fuel cycle, the necessary evolutions of the nuclear crisis management, the harmonizing work of safety approaches carried out by the WENRA association. The following documents are attached in appendixes: the decrees relative to the reformation of the nuclear control in France, the missions of the ASN, the control of nuclear safety and radiation protection in France, the organization of ASN in March 2000, the incidents notified in 2001, the inspections performed in 2001, and the list of the main French nuclear sites. (J.S.)

The radiation protection of workers. I.R.S.N.activities in 2005 in the field of radiation protection management; La radioprotection des travailleurs. Activites de l'IRSN en 2005 dans le domaine de la gestion de la radioprotection

Energy Technology Data Exchange (ETDEWEB)

Rannou, A.; Ameon, R.; Boisson, P.; Clairand, I.; Couasnon, O.; Franck, D.; Scanff, P.; Rehel, J.L.; Thevenet, M

2005-07-01

This report presents the main work carried out by the Institute of radiation protection and nuclear safety (I.R.S.N.) in the year 2005 for the management of occupational radiological protection. it draws up an assessment for this same year of the occupational external exposures to ionizing radiation in France on the basis of passive dosimetry data transmitted to the I.R.S.N. by the approved dosimetry laboratories. (authors)

Proceedings (slides) of the ANCCLI-IRSN seminar: 'environment - health: what monitoring in territories by the different actors'

International Nuclear Information System (INIS)

2012-01-01

Relations between the operation of nuclear facilities and the health of populations are recurrent topics. For this reason, the national association of information committees and local commissions (ANCCLI), and the radiation protection and nuclear safety institute (IRSN) have jointly organized this seminar devoted to the monitoring of environment and public health. Its aim was to share the experience of the different actors in order to help the local commissions of information (CLI) in carrying out their own actions on these topics. The first day, the Golfech, Gravelines, Cadarache and Saint-Laurent-Des-Eaux CLIs presented their local environmental monitoring actions and their impact studies for facilities effluents. IRSN presented its methodology for the elaboration of its annual radiological status of the French environment. A round table permitted the different intervening parties to exchange about their monitoring goals. The second day, the Tricastin and Gravelines CLI, as well as the health care supervision institute InVS), presented different studies and attempts of answers to the health-impact questions coming from the surrounding communities. The contributions and limitations of public health studies were discussed through a presentation of the joint ANCCLI/IRSN/InVS methodological guidebook 'public health in the vicinity of nuclear facilities: how to approach the questions asked'. This document gathers the slides of the available presentations: 1 - Environmental monitoring by the Tarn-et-Garonne departmental laboratory in partnership with the Golfech's CLI (A. Calafat); 2 - Environmental monitoring by the Tarn-et-Garonne veterinary laboratory (V. Rossetto); 3 - Independent environmental monitoring by the Tarn-et-Garonne and occasional expertises around the Gravelines site (F. Cazier); 4 - Study of the impact on Durance river of the liquid radiological effluents of CEA-Cadarache site (C. Fourcaud); 5 - Study of the impact on Loire river of the chemical

Population around the French nuclear power plant sites: a key-parameter for crisis management and safety economics; La population autour des sites nucleaires francais: un parametre determinant pour la gestion de crise et l'analyse economique des accidents nucleaires

Energy Technology Data Exchange (ETDEWEB)

PASCAL, A. [IRSN, Laboratoire d' economie de la surete, DSDP/SPIIC/LAERN, BP 17, 92262 Fontenay-aux-Roses (France)

2012-01-15

This paper undertakes an analysis of population around the French nuclear power plant sites, tackles the problem of evacuation planning and provides a glimpse into ongoing research at the Laboratory of Nuclear Safety Economics of the IRSN, about the cost assessment of a nuclear accident and long-term land contamination. (author)

Considerations on the studies carried at I.R.S.N. for the estimation of Chernobylsk accident consequences in France; Reflexions sur les etudes menees a l'IRSN pour l'estimation des consequences de l'accident de Tchernobyl en France

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-15

The present document that limits the consideration to the action of one stakeholder, I.R.S.N., answers very partly to the public questioning on the Chernobylsk crisis management in France. The documents allow nevertheless to emphasize: a gap between the society expectations and the public information possibilities of I.R.S.N. that in the eighties was in the Cea in charge of research and expertise and not in charge of radiation monitoring in environment; an effort of this Institute since the tenth anniversary of the disaster to begin a dialogue with the civil society especially by answering, from a succession of studies and works on the field, to the questioning on the impact of the disaster in France. It can be understood, at the reading of questions and answers received by the public organism of research and expertise that there is a link between this judgement by the public opinion of the part played by the Institute in the crisis management and the evolutions that have been decided by the Public Authorities relative to the status and the place of I.P.S.N. (Institute of nuclear protection and safety) and O.P.R.I. (Organism of protection against ionizing radiation) in the system of nuclear control (first self government then independence). (N.C.)

Analytic catalog for the use of the nuclear physicists; Repertoire analytique a l'usage des physiciens nucleaires

Energy Technology Data Exchange (ETDEWEB)

Ballini, R.; Barloutaud, R.; Bernas, R.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Laboulaye, H. de; Lehmann, P.; Leveque, A.; Levi, C.; Moreau, J.; Naggiar, V.; Olkowsky, J.; Papineau, L.; Papineau, L.; Prugne, P.; Schuhl, C.; Szteinsznaider, D.; Tzara, C.; Valladas, G. [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

1952-07-01

The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of publications, always more numerous and more varied. To remedy to this problem, we tried, at the Nuclear Physics Services of the CEA, to give to the documentation the character of a collective and systematized work. The present report covers the literature appeared between January 1, 1950 and July 1, 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le 1 Janvier 1950 et le 1 Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

Assessment on 900–1300 MWe PWRs of the ASTEC-based simulation tool of SGTR thermal-hydraulics for the IRSN Emergency Technical Centre

Energy Technology Data Exchange (ETDEWEB)

Foucher, L., E-mail: laurent.foucher@irsn.fr [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES/SAG, Cadarache, Saint-Paul-lez-Durance 13115 (France); Cousin, F.; Fleurot, J. [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES/SAG, Cadarache, Saint-Paul-lez-Durance 13115 (France); Brethes, S. [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PRP-CRI/SESUC, Cadarache, Saint-Paul-lez-Durance 13115 (France)

2014-06-01

In the event of an accident occurring in a nuclear power plant (NPP), being able to predict the amount of released radioactive substances in the environment is of prime importance. Depending on the severity of the accident, it can be necessary to quickly and efficiently protect the population and the surrounding environment from the associated radiological consequences. In France, the IRSN Emergency Technical Centre provides a technical support in decision making in case of a nuclear accident. The main objectives are to evaluate and predict the plant behaviour and radioactive releases during the accident. Different types of complementary tools are used: expert assessments, pre-calculated databases, simulation tools, etc. In the case of Steam Generator Tube Rupture (SGTR) accidents that may lead to significant radioactive releases to the atmosphere through the steam generator relief valves, IRSN is currently improving the simulation tools for diagnosis in crisis management. The objective is to adapt the thermal-hydraulic and FP behaviour modules of the severe accident integral code ASTEC V2.0, jointly developed by IRSN and its German counterpart GRS, to crisis management requirements. These requirements impose a fast running, highly reliable (accurate physical results), flexible and simple tool. This paper summarizes the results of the benchmarks between the ASTEC V2.0 thermal-hydraulic module and the CATHARE 2 (V2.5) French reference thermal-hydraulics code on several SGTR scenarios both for PWR 900 and 1300 MWe, with a particular emphasis on the computational time and physical models assessment. The overall agreement between both codes is good on the primary and secondary circuit thermal-hydraulic parameters. Moreover, the reliability and fast computational time of the thermal-hydraulic module of ASTEC V2.0 code appeared very satisfactory and in accordance with the requirements of an emergency tool.

Assessment on 900–1300 MWe PWRs of the ASTEC-based simulation tool of SGTR thermal-hydraulics for the IRSN Emergency Technical Centre

International Nuclear Information System (INIS)

Foucher, L.; Cousin, F.; Fleurot, J.; Brethes, S.

2014-01-01

In the event of an accident occurring in a nuclear power plant (NPP), being able to predict the amount of released radioactive substances in the environment is of prime importance. Depending on the severity of the accident, it can be necessary to quickly and efficiently protect the population and the surrounding environment from the associated radiological consequences. In France, the IRSN Emergency Technical Centre provides a technical support in decision making in case of a nuclear accident. The main objectives are to evaluate and predict the plant behaviour and radioactive releases during the accident. Different types of complementary tools are used: expert assessments, pre-calculated databases, simulation tools, etc. In the case of Steam Generator Tube Rupture (SGTR) accidents that may lead to significant radioactive releases to the atmosphere through the steam generator relief valves, IRSN is currently improving the simulation tools for diagnosis in crisis management. The objective is to adapt the thermal-hydraulic and FP behaviour modules of the severe accident integral code ASTEC V2.0, jointly developed by IRSN and its German counterpart GRS, to crisis management requirements. These requirements impose a fast running, highly reliable (accurate physical results), flexible and simple tool. This paper summarizes the results of the benchmarks between the ASTEC V2.0 thermal-hydraulic module and the CATHARE 2 (V2.5) French reference thermal-hydraulics code on several SGTR scenarios both for PWR 900 and 1300 MWe, with a particular emphasis on the computational time and physical models assessment. The overall agreement between both codes is good on the primary and secondary circuit thermal-hydraulic parameters. Moreover, the reliability and fast computational time of the thermal-hydraulic module of ASTEC V2.0 code appeared very satisfactory and in accordance with the requirements of an emergency tool

Status and prospects of safety research about fuel cycle facilities in France

International Nuclear Information System (INIS)

Auchere, H.; Mercier, J.P.

1996-01-01

Although there is a good knowledge of the risks and no major accident occurred in France, as in other OECD countries, it remains useful to complete basic knowledge and to allow the quality of fuel cycle plants safety assessments to be improved further, particularly in countries equipped with a 'complete' nuclear fuel cycle (France, Japan and U.K.). The scope of the current and future IPSN ('Institut de Protection et de Surete Nucleaire': institute for protection and nuclear safety) research deals with the whole fuel cycle. The overview presented here in NUCEF'95 symposium contains a number of specific themes, some of which have already been started. Successful conclusion of the safety researches will allow the IPSN to have a more precise understanding about specific phenomena and notably to replace 'engineer judgements', though they may be based on a lot of experience and competence, by more scientifically established basic data. (J.P.N.)

Thermal-hydraulic analysis of total loss of steam generator feed water in WWER-440

International Nuclear Information System (INIS)

Sabotinov, L.; Cadet-Mercier, S.

2001-01-01

The analysis is carried out for a WWER-440/V270 with upgraded primary safety valves (replacement of the existing PRZ safety valves with Pilot Operated Relief Valves (PORV) of the type SEBIM (France)) The current analysis is focused on the scenario 'Total Loss of SGs Feed Water' with application of the operator action of primary system 'Feed and Bleed' in order to check the effectiveness of the installed pressurizer SEBIM valves and to verify that the operator can cool down the reactor system and cope with this accident. The calculations have been performed at the Institute of Protection and Nuclear Safety (IPSN) in Fontenay-aux-Roses with the computer code CATHARE 2 Version 1.3L1. CATHARE is a French best estimate thermal-hydraulic program for accident analysis in the light water nuclear reactors, developed with the participation of the IPSN (Institut de Protection et Surete Nucleaire), CEA (Commissariat a l'Energie Atomique), Framatome and EdF (Electricite de France). (author)

Technical safety Organisations (TSO) contribute to European Nuclear Safety; Les organismes techniques de surete (TSO) au service de la surete nucleaire europeenne

Energy Technology Data Exchange (ETDEWEB)

Repussard, J. [Institut de radioprotection et de surete nucleaire - IRSN, 92 - Clarmart (France)

2010-11-15

Nuclear safety and radiation protection rely on science to achieve high level prevention objectives, through the analysis of safety files proposed by the licensees. The necessary expertise needs to be exercised so as to ensure adequate independence from nuclear operators, appropriate implementation of state of the art knowledge, and a broad spectrum of analysis, adequately ranking the positive and negative points of the safety files. The absence of a Europe-wide nuclear safety regime is extremely costly for an industry which has to cope with a highly competitive and open international environment, but has to comply with fragmented national regulatory systems. Harmonization is therefore critical, but such a goal is difficult to achieve. Only a gradual policy, made up of planned steps in each of the three key dimensions of the problem (energy policy at EU level, regulatory harmonization, consolidation of Europe-wide technical expertise capability) can be successful to achieve the required integration on the basis of the highest safety levels. TSO's contribute to this consolidation, with the support of the EC, in the fields of research (EURATOM-Programmes), of experience feedback analysis (European Clearinghouse), of training and knowledge management (European Training and Tutoring Institute, EUROSAFE). The TSO's network, ETSON, is becoming a formal organisation, able to enter into formal dialogue with EU institutions. However, nuclear safety nevertheless remains a world wide issue, requiring intensive international cooperation, including on TSO issues. (author)

Considerations on the studies carried at I.R.S.N. for the estimation of Chernobylsk accident consequences in France

International Nuclear Information System (INIS)

2005-07-01

The present document that limits the consideration to the action of one stakeholder, I.R.S.N., answers very partly to the public questioning on the Chernobylsk crisis management in France. The documents allow nevertheless to emphasize: a gap between the society expectations and the public information possibilities of I.R.S.N. that in the eighties was in the Cea in charge of research and expertise and not in charge of radiation monitoring in environment; an effort of this Institute since the tenth anniversary of the disaster to begin a dialogue with the civil society especially by answering, from a succession of studies and works on the field, to the questioning on the impact of the disaster in France. It can be understood, at the reading of questions and answers received by the public organism of research and expertise that there is a link between this judgement by the public opinion of the part played by the Institute in the crisis management and the evolutions that have been decided by the Public Authorities relative to the status and the place of I.P.S.N. (Institute of nuclear protection and safety) and O.P.R.I. (Organism of protection against ionizing radiation) in the system of nuclear control (first self government then independence). (N.C.)

French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

Energy Technology Data Exchange (ETDEWEB)

Guerin De Montgareuil, P. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

1964-07-01

, industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l

Tritium in the environment. The IRSN's opinion on key issues and on research and development perspectives

International Nuclear Information System (INIS)

2010-01-01

This report states the opinion of the IRSN on issues related to the behaviour of tritium in the environment, and to the associated risks. This report is based on a set of studies and researches performed on this radionuclide. Thus, the authors address the status of knowledge on the evolution of tritium released by nuclear activities (measurement techniques), the risk of bioaccumulation of tritium by living organisms within ecosystems (behaviour of tritium in the atmosphere, in soils, in ground plants, in continental and sea aquatic media), and the knowledge of risks due to tritium absorbed by living organisms (dose assessment, knowledge of tritium harmful effects and relative biological effectiveness)

Synthesis of the IRSN report on additional safety assessments (ECS) for nuclear installations of 'Batch 2'

International Nuclear Information System (INIS)

2013-01-01

After having recalled how it has been decided to perform additional safety assessments of French nuclear installations after the Fukushima accident, and indicated the concerned operators (CEA, EDF, ITER, CISBIO) and their various installations, this report proposes a synthesis of an assessment made by the IRSN on the realization of these additional safety assessments. For each of these operators, comments are made about what is still to be done, demonstrated or improved as far as practical arrangements, strength of some key components, crisis management, exposure to some specific risks, and so on, are concerned

Methodology applied by IRSN for nuclear accident cost estimations in France

International Nuclear Information System (INIS)

2013-01-01

This report describes the methodology used by IRSN to estimate the cost of potential nuclear accidents in France. It concerns possible accidents involving pressurized water reactors leading to radioactive releases in the environment. These accidents have been grouped in two accident families called: severe accidents and major accidents. Two model scenarios have been selected to represent each of these families. The report discusses the general methodology of nuclear accident cost estimation. The crucial point is that all cost should be considered: if not, the cost is underestimated which can lead to negative consequences for the value attributed to safety and for crisis preparation. As a result, the overall cost comprises many components: the most well-known is offsite radiological costs, but there are many others. The proposed estimates have thus required using a diversity of methods which are described in this report. Figures are presented at the end of this report. Among other things, they show that purely radiological costs only represent a non-dominant part of foreseeable economic consequences

Measurement exercise at the Fort de Vaujours on 25 February 2014. Reading of measurements performed by the ACRO according to the requirements of the IRSN PRP-CRI/SIAR 14-00093 technical protocol

International Nuclear Information System (INIS)

Pigree, G.; Josset, M.; Barbey, P.

2014-01-01

This document reports radiological measurements performed on the request of the ASN Paris department on some singular points and according to a specific technical protocol elaborated by the IRSN. After a discussion of results, the report presents instruments used for radiological measurements, reference values issued from other sites, reference values at a point of entrance of the site and at the vicinity of singular points, and then measurements on singular points. Additional measurements have been performed on a radioactive fragment at the origin of some offsets. The text of the IRSN technical protocol for this specific study (scope, areas to be controlled, expected radioactive elements, technical protocol, result presentation) is provided in appendix

The decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R.

2008-01-01

,; the fifth part presents the external points of view on dismantling with: the decommissioning of Saint-Laurent A, as seen by the local information committee, decommissioning: the urge for a public consultation, an evaluation of the work of the 'conseil superieur de la surete et de linformation nucleaire' (C.S.S.I.N.) - a consultative body dealing with information in the field of nuclear safety) on the issue of decommissioning basic nuclear installations, monitoring the decommissioning of nuclear facilities and examining applications. (N.C.)

A new Recoil Proton Telescope for energy and fluence measurement of fast neutron fields

Energy Technology Data Exchange (ETDEWEB)

Lebreton, Lena; Bachaalany, Mario [IRSN / LMDN (Institut de Radioprotection et de Surete nucleaire / Laboratoire de Metrologie et de dosimetrie des neutrons), Cadarache Bat.159, 13115 Saint Paul-lez-Durance, (France); Husson, Daniel; Higueret, Stephane [IPHC / RaMsEs (Institut Pluridisciplinaire Hubert Curien / Radioprotection et Mesures Environnementales), 23 rue du loess - BP28, 67037 Strasbourg cedex 2, (France)

2015-07-01

The spectrometer ATHENA (Accurate Telescope for High Energy Neutron metrology Applications), is being developed at the IRSN / LMDN (Institut de Radioprotection et de Surete nucleaire / Laboratoire de Metrologie et de dosimetrie des neutrons) and aims at characterizing energy and fluence of fast neutron fields. The detector is a Recoil Proton Telescope and measures neutron fields in the range of 5 to 20 MeV. This telescope is intended to become a primary standard for both energy and fluence measurements. The neutron detection is achieved by a polyethylene radiator for n-p conversion, three 50{sub m} thick silicon sensors that use CMOS technology for the proton tracking and a 3 mm thick silicon diode to measure the residual proton energy. This first prototype used CMOS sensors called MIMOSTAR, initially developed for heavy ion physics. The use of CMOS sensors and silicon diode increases the intrinsic efficiency of the detector by a factor of ten compared with conventional designs. The first prototype has already been done and was a successful study giving the results it offered in terms of energy and fluence measurements. For mono energetic beams going from 5 to 19 MeV, the telescope offered an energy resolution between 5 and 11% and fluence difference going from 5 to 7% compared to other home standards. A second and final prototype of the detector is being designed. It will hold upgraded CMOS sensors called FastPixN. These CMOS sensors are supposed to run 400 times faster than the older version and therefore give the telescope the ability to support neutron flux in the order of 107 to 108cm{sup 2}:s{sup 1}. The first prototypes results showed that a 50 m pixel size is enough for a precise scattering angle reconstruction. Simulations using MCNPX and GEANT4 are already in place for further improvements. A DeltaE diode will replace the third CMOS sensor and will be installed right before the silicon diode for a better recoil proton selection. The final prototype with

The 'Pole Nucleaire Bourgogne' for developing the nuclear components industry

International Nuclear Information System (INIS)

Kottmann, G.

2012-01-01

The 'Pole Nucleaire Bourgogne' (PNB) is a high-technology and heavy industries cluster in Burgundy with an international calling. It aims at innovating, educating and federating in order to place the French nuclear industry in a leading position. PNB gathers 76 small-, and medium-sized enterprises, most of them operating in the metal sector, in design and in the control/measuring sector. The aim of PNB is to make enterprises work and cooperate on specific topics according to their sectors of activities and their skills. PNB has identified 3 domains of strategical innovations: -) ecological manufacturing and durability of heavy components, -) controls for high performance components, and -) maintenance and dismantling techniques in hostile environments. The various industry sectors represented in PNB allows a cross-fertilization between high-tech industries (aeronautics, energy, transportation)

The post-accident nuclear issue: the new crisis expertise challenges for the IRSN

International Nuclear Information System (INIS)

Champion, D.

2010-01-01

The author reports the work performed by two work groups conducted by the IRSN (the French Radioprotection and Nuclear Safety Institute), the first one on the issue of assessment of radiological and dosimetric consequences in a post-accident situation, and the second one on hypotheses to be used to perform predictive assessments of these consequences. First dealing with the end of the emergency phase, he describes how to anticipate actions of protection against immediate post-accident consequences: orientation of the expertise strategy based on the CODIRPA's doctrine, post-accident zoning based on predictive indicators, use of reasonably prudent hypotheses for the first predictive assessments, importance of initial radioactive deposits to perform predictive assessments. Then, the author presents an iterative method of assessment of post-accident consequences: organization of environment radioactivity measurement programmes, periodic update of mapping of initial deposit and of actual deposits at a given time

Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

Energy Technology Data Exchange (ETDEWEB)

Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

1966-02-15

insurance programme. (author) [French] L'uranium, combustible relativement nouveau et extremement interessant pour la production d'electricite, doit faire l'objet d'un controle tres strict depuis le moment ou l'exploitant de la centrale en devient financierement responsable jusqu'a celui oti, sous forme de combustible partiellement epuise, la matiere est transferee dans une autre installation et oti l'on recupere ce qui reste de sa valeur initiale. La plupart des exploitants de centrales nucleaires dirigeaient des centrales alimentees par des combustibles fossiles avant l'avenement de l'energie nucleaire et ils ont etabli depuis longtemps un controle etendu et efficace de ces combustibles fossiles. L'exploitant d'une centrale nucleaire doit exercer un controle non moins efficace sur les matieres nucleaires speciales utilisees dans son installation. La technique de l'exploitation des centrales nucleaires n'est pas ancienne et, au cours de, son existence relativement breve, les ingenieurs et hommes de science des Etats-Unis ont constamment ameliore les plans des centrales et les methodes d'exploitation afin de reduire les couts et de permettre aux centrales nucleaires de concurrencer les centrales classiques. La gestion des matieres nucleaires doit etre aussi moderne et efficace que possible pour assurer que les progres technologiques grace auxquels les prix on pu etre reduits ne soient pas mis en echec par des insuffisances dans la manipulation du combustible nucleaire et la tenue de la comptabilite des stocks. Pour assurer la gestion des matieres nucleaires, il faut que l'exploitant de la centrale etablisse et tienne a jour une comptabilite complete et detaillee, sans etre necessairement complexe pour autant; en fait, la simplicite est extremement souhaitable. Bien que le combustible nucleaire soit nouveau et qu'il n'ait rien de commun avec les combustibles classiques, aucun secret ne doit s'y attacher. Le controle des matieres nucleaires dans le cadre de la gestion des

Synthesis of the IRSN report on the control-command architecture of the Flamanville 3 EPR reactor and the associated platforms

International Nuclear Information System (INIS)

2009-06-01

This document briefly reports the IRSN's comments on the robustness of the control-command architecture of the Flamanville 3 EPR (European pressurized reactor), that is of the equipment which, to various extent, contribute to the installation safety. This report identifies the equipment the robustness of which should be improved, outlines the problems created by the complexity of computerized systems. Notably, the authors comment the ability of the off-the-shelf computer platforms acquired by EDF to deal with the nuclear context

The 1989 annual report of the Institut de Physique Nucleaire-Orsay

International Nuclear Information System (INIS)

1989-01-01

The activity report of the Institut de Physique Nucleaire (Orsay-France) from 1 Sep 1988 to 1 Aug 1989 is presented. Theoretical and experimental investigations were carried out in the following fields: light and medium exotic nuclei, on line spectroscopy, discrete high spin states, new radioactivities, thermal fission, detection systems, giant resonances, high excitation energy structure, reaction mechanisms at energies below 10 MeV/u and at 200 MeV/u and their evolution between 10 and 100 MeV/u, meson production, transfer reactions, spin modes in nuclei, dibaryonic resonances, inelastic scattering of polarized protons. Research programs in the field of radiochemistry and relating to inter-disciplinary fields are included. The activities involving teaching, the lists of publications conferences, seminars and theses are presented [fr

Calculation of the shock-wave in the region close to an underground nuclear explosion (method Cades); Calcul de l'onde de choc en zone proche d'une explosion nucleaire souterraine (methode cades)

Energy Technology Data Exchange (ETDEWEB)

Supiot, F; Brugies, J [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

1969-07-01

The outline of a method is presented for calculating the characteristics of a shock wave produced by an underground nuclear explosion (pressure, wave velocity, velocity of the medium, energy left in the medium by the shock, etc.). By means of an application to a granitic medium and of a comparison with results obtained during French nuclear explosions, it has been possible to show the good agreement existing between the calculations and the experimental results. The advantages of such a method for studying the industrial applications of underground nuclear explosions are stressed. (authors) [French] On expose les grandes lignes d'une methode de calcul des caracteristiques de l'onde de choc issue d'une explosion nucleaire souterraine (pression, vitesse de l'onde, vitesse du milieu, energie deposee par le choc dans le milieu...). Une application a un milieu granitique et une comparaison aux resultats obtenus au cours d'explosions nucleaires francaises permet de montrer la bonne concordance entre le calcul et les resultats experimentaux. On souligne l'interet d'une telle, methode pour l'etude d'applications industrielles des explosions nucleaires souterraines. (auteurs)

Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

Comparative approach between nuclear safety and security; Approche comparative entre surete et securite nucleaires

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-04-15

Adopting the definition of nuclear safety and nuclear security as they are specified by IAEA glossaries, this report first outlines that these both notions refer to similar risks but with causes of different nature. They discuss the notions of transparency and confidentiality and outline that security and safety both aims at the protection of population and of the environment. They discuss their organisational principles, notice that both have their own legal and regulatory framework, that authorities have expertise on both, that the responsibility is distributed among operators and the State, and that safety and security cultures are complementary. They analyse the design, exploitation and management principles of security and safety approaches: graded approach, defence-in-depth, synergy between security and safety, same daily monitoring requirement, same necessity to address the return on experience, same need to update a referential, a more constrained exchange of good practices in safety, a necessity to deal with their respective requirements, elaboration of emergency plans, performance of exercises

Detection of ruthenium 106 in France and in Europe. Results of IRSN's investigations. Information report (Update of report of 09/10/2017)

International Nuclear Information System (INIS)

2017-01-01

Ruthenium 106 has been detected in late September by several European networks involved in the monitoring of atmospheric radioactive contamination, at levels of a few milli-Becquerels per cubic meter of air. IRSN's investigations make it possible to provide information on the possible location of the source of the release as well as the order of magnitude of the quantities released

The French civilian nuclear: connections and stakes

International Nuclear Information System (INIS)

2010-01-01

This document (18 power point slides) gives an overview of the French civilian nuclear industry and research and development: importance of the nuclear power generation in France, excellence of the education in nuclear sciences, organization of the nuclear connection (CEA, Areva, EDF, IRSN), the role of the French International Nuclear Agency (AFNI), the requirements for a renewal of human resources (French and foreign engineers) in the field of nuclear energy, the degree course for a diploma, examples of engineer and university diplomas, the educational networks in various regions of France, presentation of the Institut National des Sciences et Techniques Nucleaires (Nuclear Sciences and Techniques National Institute) and its master degrees, organization of the French education system in nuclear sciences with strong relations with the research and development programs

Assessment of radioactivity controls performed by the IRSN on enamels pigmented by uranium and recommendations related to the use of radiation meters by the public; Bilan des controles de radioactivite effectues par l'IRSN sur des emaux pigmentes par de l'uranium et recommandations relatives a l'emploi de radiametres par des personnes du public

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-09-15

This information note reports the results of measurements performed by the IRSN on enamel pictures possessed by a Limoges inhabitant who bought a radiometer and measured an unusually high radioactivity level due to the presence of uranium-based yellow pigments. The performed measurements are described and the results are discussed in terms of radioactivity level and of radionuclide identification

Synthesis of the IRSN report related to the containment of double walled enclosures of the operated fleet

International Nuclear Information System (INIS)

2013-01-01

This report presents the IRSN's analysis on studies and modifications planned by EDF within the frame of the VD3-1300 safety re-examination which more particularly concern the third containment barrier of a reactor and of its extensions, as well as the containment of some surrounding buildings. The addressed topics are: the approach associated with the 'containment' safety function, the condition, behaviour and control of the double walled enclosure, the system of suction and filtration of the space between enclosures, the extension of the third containment barrier, the containment of building surrounding the reactor building, the risk of bypass containment, the EDF organisation with respect to the containment safety function

Joint scientific publication by the INSERM and IRSN concerning child leukaemia about French nuclear power stations on the Internet site of the 'International Journal of Cancer' the 4 January 2012

International Nuclear Information System (INIS)

2012-01-01

This document describes the cooperation between the INSERM and IRSN in the field of child leukaemia about nuclear power stations, and presents the published study: context and objectives, methodology (epidemiological data, geographical data), and obtained results (risks and comparison with a German study)

Study of the chimney produced by an underground nuclear explosion; Etude de la cheminee creee par une explosion nucleaire souterraine

Energy Technology Data Exchange (ETDEWEB)

Derlich, S [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

1969-07-01

Underground nuclear explosions lead to the formation of a cavity which is roughly of spherical shape. The roof of this cavity is unstable and collapses in most cases, leading to the formation of a chimney. The height and the diameter depend on the energy of the charge and on the nature of the surroundings. The chronology of the various stages can be determined by seismic observations. The interior of the chimney is filled, either partially or completely, with rubble earth. This phenomenon is of great importance as far as the use of nuclear explosions for industrial applications is concerned. (author) [French] Les explosions nucleaires souterraines creent une cavite de forme grossierement spherique. La voute de cette cavite est instable et s'effondre dans la plupart des cas, donnant lieu a la formation d'une cheminee. La hauteur et le diametre sont fonction de l'energie du tir et de la nature du milieu. La chronologie des evenements peut etre determinee par des observations seismiques. L'interieur des cheminees est occupe, en partie ou en totalite, par des eboulis. Ce phenomene presente un grand interet pour l'utilisation des explosions nucleaires a des fins industrielles. (auteur)

Safety in transports of civil radioactive substances on the French territory. Lessons learned by the IRSN from the analysis of significant events declared in 2012 and 2013. Safety of transports of civil radioactive substances in France

International Nuclear Information System (INIS)

2016-11-01

After a presentation of some general elements regarding transports of radioactive substances in France, this report proposes a synthetic overview of the main lessons learned by the IRSN from the analysis of transport-related events in 2012 and 2013. Then, the body of this report presents the context of transports of radioactive substances: legal framework, main safety elements, nature and flows of these transports in France, transports per activity sector. It proposes a global analysis of significant events, with a comparison with previous years. The four main significant events are described. Some transverse issues are finally addressed: return on experience on crisis management in relationship with transport events, IRSN study on the behaviour of packagings during long duration fire

Risk of radiation-induced cancer at low doses and low dose rates for radiation protection purposes

International Nuclear Information System (INIS)

1995-01-01

The aim of this report is to provide an updated, comprehensive review of the data available for assessing the risk of radiation-induced cancer for radiation protection purposes. Particular emphasis is placed on assessing risks at low doses and low dose rates. The review brings together the results of epidemiological investigations and fundamental studies on the molecular and cellular mechanisms involved in radiation damage. Additionally, this information is supplemented by studies with experimental animals which provide further guidance on the form of the dose-response relationship for cancer induction, as well as on the effect of dose rate on the tumour yield. The emphasis of the report is on cancer induction resulting from exposure to radiations with a low linear energy transfer (LET). The work was performed under contract for the Institut de Protection et de Surete Nucleaire, Fontenay-aux-Roses, Paris, France, whose agreement to publish is gratefully ackowledged. It extends the advice on radiation risks given in Documents of the NRPB, 4 No. 4 (1993). (Author)

The control equipment of the Melusine II reactor; L'equipement de controle du reacteur Melusine II

Energy Technology Data Exchange (ETDEWEB)

Cordelle, M; Delcroix, V; Denis, P; Gariod, R

1963-07-01

Melusine II, low-power reactor, used for the study of Siloe core has diverged at the CEA Grenoble, the 23. May 1962; its monitoring board studied and carried out in this center is the first in France to be entirely transistorized. The first months of running have justified the hope put in the new electronics to improve the stability and the safety of running. The article describes the design of the control and gives the main characteristics of the measurement chains and of the actions on reactivity. (O.M.) [French] Melusine II, reacteur de faible puissance destine a l'etude du coeur de Siloe a diverge au Centre d'Etudes Nucleaires de Grenoble, le 23 mai 1962, son tableau de controle etudie et realise dans ce Centre est le premier en France a etre entierement transistorise. Les premiers mois de fonctionnement ont justifie l'espoir mis dans la nouvelle electronique pour ameliorer la stabilite et la surete de fonctionnement. L'article decrit la conception du controle et donne les principales caracteristiques des chaines de mesure et des actions sur la reactivite. (auteurs)

Evaluation of ductile tearing in a cracked component with a simple method (Js)

International Nuclear Information System (INIS)

Moulin, D.; Drubay, B.; Clement, G.; Nedelec, M.

1995-01-01

In the nuclear industry, it is more and more usual to perform fracture assessment on detective structures made of ductile material with the help of elastoplastic' fracture mechanics relying on the parameter J. Several engineering methods have been developed in the past to calculate this parameter. These results were used to develop a practical procedure noted Js method which simply gives J as function of elastically calculated Je and a plastic correction factor. This method has been introduced in the A16 rule developed jointly by CEA-EdF and Novatome for fast breeder reactors in particular in order to evaluate the loading at crack instability taking into a account ductile tearing. The determination of initiation has already been presented. This determination of the loading at crack instability is examined through two simple but representative examples using the simplified estimation of J. Predicted loadings at crack instability are compared with experimental results. This study was carried out a part of cooperative program with the Institut de Protection et de Surete Nucleaire of the CEA. (author) 12 refs., 10 figs

Investigations concerning fire-induced accidents in nuclear facilities

International Nuclear Information System (INIS)

Lamuth, P.; Lernout, L.A.; Bonneval, F.; Cottaz, M.

1996-01-01

In the context of fire protection in technical buildings of French nuclear facilities, three principles have been adopted: prevention, detection and fire-fighting. Their implementation makes it possible on the one hand to limit the fire ignition and the fire growth, and on the other hand to prevent fire extent which would lead to unavailability of several safety related equipment. Although progress has been made in this direction, the fire risks have still not been eliminated. It is therefore essential to evaluate the fire effects and to assess their consequences. To this end, three main R and D programs have been conducted into fires. Part I sets out the fire PSA methodology used for a 900 MWe PWR. Part II gives an outline of two fire and ventilation computer codes useful for the fire PSA. Finally, part III gives an outline of the tests already performed and those currently under way in the two laboratories of the Institut de Protection et de Surete Nucleaire (IPSN) in order to qualify the codes and provide useful information for the safety assessment. (author)

Safety at civil basic nuclear installations other than nuclear power plants in France. Lessons learned by IRSN from significant events reported in 2013 and 2014

International Nuclear Information System (INIS)

2016-01-01

IRSN publishes the lessons learned from its analysis of significant events which have occurred in 2013 and 2014 at 82 civil basic nuclear installations (INBs) other than nuclear power plants (NPPs). Produced every two year since 2009, this report concerns 73 facilities such as plants, laboratories, facilities for the treatment, disposal and storage of waste, and facilities which have been decommissioned, and 9 research reactors, operated by around twenty different licensees in France. 210 and 227 significant events were respectively reported in 2013 and 2014 to the French Nuclear Safety Authority (ASN). This number remains similar to previous years and tends to 'stabilize' at around 200 to 220. On the one hand, among the improvements observed in 2013 and 2014, IRSN found two subjects of particular interest: - Efforts made by the licensees to increase reliability of organisational and human measures related to handling operations, in particular at the spent fuel reprocessing plant of AREVA NC La Hague and in the radioactive waste storage facilities operated by the CEA. - Important improvement program deployed by the licensee of the FBFC plant in Romans-sur-Isere (Drome) to enhance operating practices, particularly regarding management of criticality risks (prevention of uncontrolled chain reactions). On the other hand, three subjects still require special vigilance by licensees: - Ensuring full control over the safety documentation of facilities. IRSN's cross-cutting analysis of events reveal a large number of cases for which parts of the safety documentation are not fully understood at the facilities, are not applied, are inaccurate or not applicable to the situation. - Ensuring in-depth and comprehensive planning of installation clean-up and dismantling operations. Risks of worker exposure to ionising radiation are higher during these operations which may require personnel to work in close proximity to radioactive materials. - Ensuring more

Synthesis of the IRSN report of the management of effluents in operating nuclear plants, and of associated radioactive and chemical rejections

International Nuclear Information System (INIS)

2009-05-01

This report discusses the various improvements proposed by the IRSN to EDF for a better management of effluents and rejections in nuclear plants. These improvements should bear on a better understanding of the production, of the behaviour and of the treatment of radioactive compounds and of associated chemical compounds. They should also bear on the design of the installations and their inspection, operation practices, the use of local good practices, the organisation, the control of rejections, the control of underground waters of nuclear sites, experience feedback, the documentation on effluents and rejections

Nuclear study of Melusine; Etude nucleaire de Melusine

Energy Technology Data Exchange (ETDEWEB)

Cherot, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1959-07-01

In this report are reviewed - with respect to starting of experiments - the main nuclear characteristics of a 20 per cent enriched uranium lattice, with light water as moderator and reflector. The reactor is to operate at 1 MW. 1) Study of various critical masses. 2) Control. Effectiveness of cadmium. Control rods and of a stainless steel regulating rod. 3) Study of the effect on reactivity of disturbances in the core center. 4) Study of xenon and samarium poisoning. 5) Temperature factor. 6) Heat exchanges in a fuel element. (author) [French] On etudie, dans ce rapport, les principales proprietes nucleaires d'un reseau a uranium enrichi (20 pour cent), dont le moderateur et le reflecteur sont l'eau legere en vue des experiences de demarrage. Ce reacteur devra fonctionner a 1 MW. 1) Etude de diverses masses critiques. 2) Controle. Efficacite des barres de controle en cadmium et d'une barre de reglage en acier inoxydable. 3) Etude de l'effet sur la reactivite de perturbation au centre du coeur. 4) Etude de l'empoisonnement xenon et samarium. 5) Coefficient de temperature. 6) Echanges thermiques dans un element. (auteur)

Enhancing co-operation between AVN, IRSN and GRS: the junior staff pilot project on the comparative testing of IPA codes

International Nuclear Information System (INIS)

Hoyos, A. de; Keesmann, S.; Smidts, O.

2006-01-01

- Objectives: The project takes place within the framework of the Junior Staff Program of AVN, GRS and IRSN which aims at creating a junior staff network among European TSOs. The objective of this project is to apply integrated performance assessment (IPA) tools used by AVN, IRSN and GRS to two generic and simplified models (Bure site in France and Mol site in Belgium) for disposal systems in argillaceous formations. The comparison of the results from different codes applied to the disposal systems of the two mentioned sites aims at a better understanding of the confinement capabilities of the considered geological formations and of the IPA methodology in general. The incentive is a common understanding of approaches developed by each partner and the improvement of this expertise. More specifically, this pilot project aims at enhancing exchanges of views and mutual experiences in the field of understanding major safety functions. - Tools and Methods: A new code for the assessment of barrier systems in argillaceous formations has only recently been developed at GRS, as in the past such formations played a minor role as a possible hosting environment for a repository in Germany. The project also serves as a test case for this code. The considered disposal systems are defined on the basis of the concepts and data available for Mol and Bure. The program packages used for the performance assessment calculations are: HYDRUS-1D with source term module (AVN), GoldSim (IRSN) and EMOS-modules CLAYPOS and CHET (GRS). While the coupling of HYDRUS-1D with a source term module and the EMOS-modules are FORTRAN77- coded programs specifically developed for the simulation of parts of a barrier system of a final repository, GoldSim is a general purpose simulation environment with an integrated graphical user interface for modelling and data output. Models realized in GoldSim are flexible and can be easily adapted to new requirements. The software also offers an intrinsic

Neutron noise in nuclear reactors; Le bruit neutronique des reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Blaquiere, A. [Institut National des Sciences et Techniques Nucleaires (France); Pachowska, R. [Universite Technique de Varsovie (Poland)

1961-06-15

The power of a nuclear reactor, in the operating conditions, presents fluctuations due to various causes. This random behaviour can be included in the study of 'noises'. Among other sources of noise, we analyse hereafter the fluctuations due: a) to the discontinuous emissions of neutrons from an independent source; b) to the multiplication of neutrons inside the reactor. The method which we present makes use of the analogies between the rules governing a nuclear reactor in operation and a number of radio-electrical systems, in particular the feed-back loops. The reactor can be characterized by its 'passing band' and is described as a system submitted to a sequence of random pulses. In non linear operating condition, the effect of neutron noise is defined by means of a non-linear functional, this theory is thus related to previous works the references of which are given at the end of the present report. This leads us in particular in the case of nuclear reactors to some results given by A. Blaquiere in the case of radio-electrical loops. (author) [French] La puissance d'un reacteur nucleaire, dans les conditions du regime, est affectee de fluctuations dont les causes sont tres diverses. Ce comportement aleatoire rentre dans le cadre general de l'etude des 'bruits'. Entre autres sources ce bruit, nous analysons ici les fluctuations dues: a) a l'emission discontinue des neutrons provenant d'une source autonome; b) a la multiplication des neutrons au sein du reacteur. La methode que nous introduisons exploite les analogies entre les lois qui regissent un reacteur nucleaire au regime et certains systemes radioelectriques, en particulier les circuits a boucle de reaction. Le reacteur est caracterise par sa 'bande passante' et est decrit comme un systeme soumis a une succession d'impulsions aleatoires. Dans les conditions de fonctionnement non lineaires, l'effet du bruit neutronique est precise en utilisant une fonctionnelle non lineaire, ce qui relie cette theorie a

Safety of transport of radioactive substances for civil use on the French territory. Lessons learned by the IRSN from the analysis of significant events reported in 2012 and 2013

International Nuclear Information System (INIS)

2014-01-01

The first part of this report proposes an overview of significant aspects and events related to the transport of radioactive substances in France, and a comment on lessons learned by the IRSN. The second and main part first presents some aspects of this specific transport: regulatory framework, main safety issues, nature and flow of these transports, transports of radioactive substances per sector. The second part proposes an analysis of significant events: elements related to the reporting of an event, assessment of events and analysis of main trends noticed in 2012 and 2013 with respect to previous years, analysis of the main types of events which occurred in 2013 and 2013 with respect with those which occurred during the previous years. The next chapter describes significant events: damage of a parcel during its handling, a non conformal content, loss of a parcel on a public road, derailment of a car in Le Bourget. Some transverse topics are finally addressed: return on experience of crisis management in relationship with events in radioactive substance transport, IRSN study on the behaviour of packaging during long duration fires

Evolution of nuclear chemical industry in France; Evolution de l'industrie chimique nucleaire en France

Energy Technology Data Exchange (ETDEWEB)

Fould, M H [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1959-07-01

'impulsion du CEA, mais aussi de maitres d'oeuvres tels qu'Electricite de France et la Marine Marchande, l'effort nucleaire fran is atteint pour les annees 1957-1961, environ 600 milliards de francs: plus de la moitie de cette somme sera depensee par l'industrie chimique en recherches, installations pilotes, constructions d'usines et livraisons. Faire bien, vite et rentable sont les buts recherches. Ces objectifs sont atteints grace a une collaboration intime des grands services de l'etat et de l'industrie privee. Ce gros effort s'exerce principalement dans les voies suivantes: - Un traitement chimique pousse de tonnages croissants des minerais de l'Union fran ise, visant a produire un uranium pur, abondant et bon marche. - Une preparation soigneuse de combustibles nucleaires economiques et parfaitement adaptes aux divers types de reacteurs en fonctionnement ou en construction. - Un retraitement des combustibles irradies pour en extraire le plutonium de facon complete ainsi que l'uranium et certains produits de fission. - Une fabrication industrielle des materiaux nucleairement purs ou resistants a la corrosion exiges par la technologie des reacteurs producteurs d'energie et de recherches. - La fourniture aux multiples utilisateurs etrangers et fran is d'isotopes et de traceurs radioactifs reclames par la medecine, l'industrie et l'agriculture en nombre toujours croissant. - Un traitement chimique meticuleux des effluents gazeux ou liquides dans des stations au controle rigoureux afin de rendre les reacteurs et leurs annexes parfaitement surs d'emploi. Cet expose aura montre l'ampleur de l'effort deploye par une industrie chimique nucleaire jeune, dynamique et en plein essor. Ayant assure ses techniques, realise de nombreuses installations, elle est largement en etat de faire face au programme atomique fran is. En outre, elle est capable et desireuse d'etre associee aux developpements de l'industrie atomique etrangere notamment dans te cadre de l'Euratom et d

The IRSN has appraised the security of the TN 117 parcel model loaded with new or irradiated fuels

International Nuclear Information System (INIS)

2009-10-01

This document reports the examination made by the IRSN on the security of a parcel design which is to be used for the transportation of new or irradiated nuclear fuels and more precisely for the transportation of fissile radionuclides with a high radioactivity. According to this content, this packaging must therefore comply with some radioactive material transport security regulations which correspond to specific mechanical, thermal and immersion requirements. After a description of the parcel design, this report comments the experimental and numerical results of the parcel structural analysis, and recommends some further investigations. It also briefly comments the results of a thermal analysis, and of a security-criticality analysis. The parcel security appears to depend on the fuel pencil watertightness

Radiation protection of the environment. State of the art and recommendations by the IRSN

International Nuclear Information System (INIS)

Beaugelin-Seiller, K.; Garnier-Laplace, J.; Gilbin, R.; Simon-Cornu, M.; Baudry, M.; Deschamps, P.; Gariel, J.C.; Lecomte, J.F.; Paquet, F.; Renaud, P.; Schuler, M.

2016-01-01

This report notably aims at helping the GPRADE (Groupe permanent d'experts en radioprotection, pour les applications industrielles et de recherche des rayonnements ionisants, et en environnement - Permanent group of experts in radiation protection for industrial and research applications of ionizing radiations, and in environment) to build up its opinion on the French management of methods and technical regulations for the assessment of the radiological risk for the environment, or for the national transposition of the 2013/59/Euratom European directive. After a brief overview of the international, European and French legal context, the report proposes an overview of the state of the art: history, definitions, principles, regulation of radiation protection of the environment in different countries. It presents the main approaches and compares them: the CIPR approach, the Erica approach (the most used in Europe). It also discusses the compatibility of main approaches to the assessment of the radiological risk for ecosystems. It reports applications and returns on experience at the international level and within the frame of the IRSN commitment in planned, existing or emergency situations. Recommendations are formulated

I.R.S.N. formulates the conclusions of the French-German initiatives for Chernobylsk; L'IRSN presente les conclusions de l'initiative Franco-Allemande (IFA) pour Tchernobyl

Energy Technology Data Exchange (ETDEWEB)

Repussard, J.; Deville-Cavelin, G.; Tirmarche, M

2005-09-15

The principle objective of this work were: to collect, to gather and validate the existing radioecological data; to use these data for the evaluations, the follow up of consequences and modeling; to provide elements to integrate in the tools used by the decision-makers to manage the post accidental situations; to inform the public and the media of the radiological consequences of the accident; to help the laboratories and institutes of countries concerned by the accident. Three groups of common interests have been defined by I.R.S.N. and G.R.S. in collaboration with Ukraine, Belarus and Russia: transfers in terrestrial environment, from terrestrial environment to the aquatic medium, in the aquatic medium and the urban medium. wastes: inventory and characterisation of waste storages, characterisation of waste (nature and quantity), evaluation of impact and management strategy. Counter measures in urban medium and agricultural medium (natural and semi natural). The programme includes ten sub projects: ecological picture, environment contamination, waste storage and management, soil-plants transfer, plants-animals transfers, transfer by surface runoff, transfer in aquatic medium, urban environment and countermeasures, counter measures for natural or agricultural areas, data base with light integration called R.E.D.A.C. (radioecological database after Chernobyl). (N.C.)

Direct interaction in nuclear reactions: a theory; L'interaction directe dans les reactions nucleaires: theorie

Energy Technology Data Exchange (ETDEWEB)

Dominicis, C.T. de [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1959-07-01

General treatment of the foundations of direct interaction in nuclear reactions; representation of the instantaneous elastic scattering amplitude by the scattering amplitude due to a complex potential; expansion of the instantaneous inelastic scattering amplitude and discussion of the 1. Bohr approximation (distorted waves) contribution to individual and collective states of excitation. (author) [French] Expose general sur les fondements de l'interaction directe dans les reactions nucleaires; representation de l'amplitude de diffusion instantanee elastique par celle due a un potentiel complexe; developpement de l'amplitude de diffusion instantanee inelastique et discussion de la contribution de la premiere approximation de Bohr (sur des distendues) a l'excitation d'etats individuels et collectifs. (auteur)

Global rainbow refractometry for droplet temperature measurement

Energy Technology Data Exchange (ETDEWEB)

Pascal Lemaitre; Emmanuel Porcheron; Amandine Nuboer; Philippe Brun; Pierre Cornet; Jeanne Malet; Jacques Vendel; Laurent Bouilloux [Institut de Radioprotection et de Surete Nucleaire DSU/SERAC, BP 68, 91192 Gif-sur-Yvette Cedex (France); Gerard Grehan [UMR 6614 CORIA, Laboratoire d' Electromagnetisme et Systemes Particulaires Site Universitaire du Madrillet, Avenue de l' universite BP 12, 76 801 Saint Etienne du Rouvray Cedex, (France)

2005-07-01

Full text of publication follows: In order to establish an accurate database to characterize the heat and mass transfers between a spray and the atmosphere with thermal-hydraulic conditions representative of a hypothetical nuclear reactor accident in the containment enclosure of a pressurized water reactor (PWR), the French Institut de Radioprotection et de Surete Nucleaire (IRSN) has developed the TOSQAN experimental facility. This experiment is highly instrumented with non-intrusive diagnostics allowing to measure droplet size and velocity and gas concentrations [1]. The aim of this work is to present the Global Rainbow Thermometry (GRT), which is an advanced non-intrusive optical diagnostic, developed to measure the mean temperature of a set of falling droplets, in a measurement volume of 1 cm{sup 3}. The final paper will be divided in three parts. In the first one, we will explain the principle of the rainbow formation and how droplet temperature can be deduced from the rainbow analysis [2]. This part will be illustrated with the theoretical background on the rainbow and numerical simulations of the global rainbow. The second part will be devoted to present the global rainbow experimental set-up we have developed on optical table, its experimental qualification and finally its implementation on the TOSQAN facility [3]. Finally, we will present the temperature measurements achieved in TOSQAN for thermal-hydraulic conditions representative of a hypothetical nuclear reactor accident. These measurements are useful to characterize the heat and mass transfers between the spraying droplets and the air-steam mixture composing the atmosphere. This analysis will be exposed in a two companion papers. References: [1] E. Porcheron, P. Brun, P. Cornet, J. Malet, J. Vendel. Optical diagnostics applied for single and multi-phase flow characterization in the TOSQAN facility dedicated for thermal hydraulic containment studies. NURETH-10 Seoul, Korea, October 5-9, 2003. [2] P

Global rainbow refractometry for droplet temperature measurement

International Nuclear Information System (INIS)

Pascal Lemaitre; Emmanuel Porcheron; Amandine Nuboer; Philippe Brun; Pierre Cornet; Jeanne Malet; Jacques Vendel; Laurent Bouilloux; Gerard Grehan

2005-01-01

Full text of publication follows: In order to establish an accurate database to characterize the heat and mass transfers between a spray and the atmosphere with thermal-hydraulic conditions representative of a hypothetical nuclear reactor accident in the containment enclosure of a pressurized water reactor (PWR), the French Institut de Radioprotection et de Surete Nucleaire (IRSN) has developed the TOSQAN experimental facility. This experiment is highly instrumented with non-intrusive diagnostics allowing to measure droplet size and velocity and gas concentrations [1]. The aim of this work is to present the Global Rainbow Thermometry (GRT), which is an advanced non-intrusive optical diagnostic, developed to measure the mean temperature of a set of falling droplets, in a measurement volume of 1 cm 3 . The final paper will be divided in three parts. In the first one, we will explain the principle of the rainbow formation and how droplet temperature can be deduced from the rainbow analysis [2]. This part will be illustrated with the theoretical background on the rainbow and numerical simulations of the global rainbow. The second part will be devoted to present the global rainbow experimental set-up we have developed on optical table, its experimental qualification and finally its implementation on the TOSQAN facility [3]. Finally, we will present the temperature measurements achieved in TOSQAN for thermal-hydraulic conditions representative of a hypothetical nuclear reactor accident. These measurements are useful to characterize the heat and mass transfers between the spraying droplets and the air-steam mixture composing the atmosphere. This analysis will be exposed in a two companion papers. References: [1] E. Porcheron, P. Brun, P. Cornet, J. Malet, J. Vendel. Optical diagnostics applied for single and multi-phase flow characterization in the TOSQAN facility dedicated for thermal hydraulic containment studies. NURETH-10 Seoul, Korea, October 5-9, 2003. [2] P

Containment response to a severe accident (TMLB sequence) with and without mitigation strategies

International Nuclear Information System (INIS)

Passalacqua, R.

2004-01-01

A loss of SG feed-water (TMLB sequence) for a prototypic PWR 900 MWe with a multi-compartment configuration (with 11 and 16 cells nodalization) has been calculated by the author using the ASTEC code in the frame of the EVITA project (5th Framework Programme, FWP). A variety of hypothesis (e.g. activation of sprays and hydrogen recombiners) and possible consequences of these assumptions (cavity flooding, hydrogen combustion, etc.) have been made in order to evaluate the global reactor containment building response (pressure, aerosol/FP concentration, etc.). The need to dispose of severe accident management guidelines (SAMGs) is increasing. These guidelines are meant for nuclear plants' operators in order to allow them to apply mitigation strategies all along a severe accident, which, only in its initial phase, may last several days. The purpose of this paper is to outline the influence on the containment load of most common accident occurrences and operators actions, which is essential in establishing SAMGs. ASTEC (Accident Source Term Evaluation Code) is a computer code for the evaluation of the consequences of a postulated nuclear plant severe accident sequence. ASTEC is a computer tool currently under joint development by the Institut de Radioprotection et de Surete Nucleaire (IRSN), France, and Gesellschaft fuer Anlagen-und Reaktorsicherheit (GRS), Germany. The aim of the development is to create a fast running integral code package, reliable in all simulations of a severe accident, to be used for level-2 PSA analysis. It must be said that several recent developments have significantly improved the best-estimate models of ASTEC and a new version (ASTEC V1.0) has been released mid-2002. Nevertheless, the somehow obsolete ASTECv0.3 version here used, has given results very useful for the estimation of the global risk of a nuclear plant. Moreover, under the current 6th FWP (Sustainable Integration of EU Research on Severe Accident Phenomenology and Management), the

Assessment of the French environment radiological status in 2009. Synthesis of the results obtained by the IRSN survey networks

International Nuclear Information System (INIS)

2009-01-01

After a brief recall of the IRSN's missions, this report describes why and how radioactivity is controlled in France. It presents the national network for environment radioactivity measurements, and indicates the objectives of this radiological survey. It comments the status and levels of the natural and artificial radioactivity in France, discusses the results of the territory general survey (atmosphere, inland, coast, regions), the results of fuel cycle related sites (nuclear sites, old mining sites, front end industries, electricity production plants, back end industries, waste storage sites), the results concerning the nuclear medicine radioactive releases, the results obtained during selective expertises, and discusses the assessment of the exposure of the French population to ionizing radiations. It finally indicates how those data are published

Information Synthesis in Uncertainty Studies: Application to the Analysis of the BEMUSE Results

International Nuclear Information System (INIS)

Baccou, J.; Chojnacki, E.; Destercke, S.

2013-01-01

To demonstrate that the nuclear power plants are designed to respond safely at numerous postulated accidents computer codes are used. The models of these computer codes are an approximation of the real physical behaviour occurring during an accident. Moreover the data used to run these codes are also known with a limited accuracy. Therefore the code predictions are not exact but uncertain. To deal with these uncertainties, 'best estimate' codes with 'best estimate' input data are used to obtain a best estimate calculation and it is necessary to derive the uncertainty associated to their estimations. For this reason, regulatory authorities demand in particular to technical safety organization such as the French Institut de Radioprotection et de Surete Nucleaire (IRSN) to provide results taking into account all the uncertainty sources to assess safety quantities are below critical values. Uncertainty analysis can be seen as a problem of information treatment and a special effort on four methodological key issues has to be done. The first one is related to information modelling. In safety studies, one can distinguish two kinds of uncertainty. The first type, called aleatory uncertainty, is due to the natural variability of an observed phenomenon and cannot be reduced by the arrival of new information. The second type, called epistemic uncertainty, can arise from imprecision. Contrary to the previous one, this uncertainty can be reduced by increasing the state of knowledge. Performing a relevant information modelling therefore requires to work with a mathematical formalism flexible enough to faithfully treat both types of uncertainties. The second one deals with information propagation through a computer code. It requires to run the codes several times and it is usually achieved thanks to a coupling to a statistical software. The complexity of the propagation is strongly connected to the mathematical framework used for the information modelling. The more general the

Safety of the Transport of Radioactive Materials for Civilian Use in France. Lessons learned by IRSN from analysis of significant events reported in 2014 and 2015. Mission report 2016

International Nuclear Information System (INIS)

2017-01-01

IRSN publishes its report on the safety of transport of radioactive materials for civilian use in France for the years 2014 and 2015. It is based on an overall review of the significant events that occurred during this period during transport operations in France by road, railway, inland waterway, sea and air of 980 000 parcels loaded with radioactive substances. In 2014 and 2015, respectively 139 and 122 events were reported, which is about one event reported for 7,500 packages carried. While these figures are up significantly compared to 2013 (93 reported events, or 1 in 10,000 packages carried), IRSN believes that this trend should not however be interpreted as a deterioration of the safety level of the transport of radioactive materials. Indeed, it is largely explained by better detection of events relevant to safety by the actors concerned and therefore their declaration to the authorities. None of these events had significant radiological consequences for the workers, the population or the environment. As part of progress made, IRSN notes a sharp decrease, in 2015, in the number of damage of packages intended for medical activities during their handling in airport areas. This decrease is linked to awareness actions conducted for airlines companies and staff involved in the handling of packages. Finally, three themes must be the subject of particular vigilance of the actors concerned and of corrective actions: - Compliance with the requirements for the transport of gamma radiography devices, in particular those associated with the locking of the source; events related to the transport of gamma radiography devices appeared as remarkable events over the period (3 level 1 events and 1 level 2 events); - The tie-down of packages on their means of transport, given the risks of fall of the package during transport, as well as tie-down of the objects in their transport container; - The operations of filling and closing of drums containing uranium ore in order to

The IRES electronic seal

International Nuclear Information System (INIS)

Autrusson, B.; Brochard, D.; Moreau, J.F.; Martin, J.C.

2001-01-01

In the framework of the French Support Program for the IAEA Safeguards, the 'Institut de Protection et de Surete Nucleaire' (IPSN), developed an electronic seal called Integrated and Reusable Electronic Seal (IRES) that enables independent verification by different inspectorates (IAEA, Euratom, and National Inspectorate). The seal can be remotely interrogated by radio frequency and integrated to other Containment/surveillance systems by serial line RS 485. Data are authenticated and the IRESMAG software manages in the seal reader all functionalities of the seal and records inspection data compatible with the IAEA's Seal Database. To perform this development, IPSN relies on industrial partners: SAPHYMO for the general architecture of the seal and the electronics, THALES for the authentication of data and the security of transmission. The main features of the IRES seal are the following: Interrogation by different inspectorate, allowing independent conclusions; Recording of events, including tampering, in a non-volatile memory; Authentication of data and enhanced security of the communication between the seal and the seal reader; Remote interrogation by an inspector or/and automatic for unattended systems or remote monitoring; Reusable after erasing the seal memory and replacement of the batteries

Contributions to the European workshop on investigation of strong motion processing procedures

International Nuclear Information System (INIS)

Mohammadioun, B.; Goula, X.; Hamaide, D.

1985-11-01

The first paper is one contribution to a joint study program in the numerical processing of accelerograms from strong earthquakes. A method is proposed for generating an analytic signal having characteristics similar to those of an actual ground displacement. From this signal, a simulated accelerogram is obtained analytically. Various numerical processing techniques are to be tested using this signal: the ground displacements they yield will be compared with the original analytic signal. The second contribution deals with a high-performance digitization complex, custom-designed to stringent technical criteria by the CISI Petrole Services, which has recently been put into service at the Bureau d'Evaluation des Risques Sismiques pour la Surete des Installations Nucleaires. Specially tailored to cope with the problems raised by the sampling of Strong-Motion photographic recordings, it offers considerable flexibility, due to its self-teaching conception, constant monitoring of the work ongoing, and numerous preprocessing options. In the third contribution, a critical examination of several processing techniques applicable to photographic recordings of SMA-1 type accelerometers is conducted. The basis for comparison was a set of two accelerograms drawn from synthetic signals, the characteristics of which were already well known

Probabilistic analysis of 900 MWe PWR. Shutdown technical specifications

International Nuclear Information System (INIS)

Mattei, J.M.; Bars, G.

1987-11-01

During annual shutdown, preventive maintenance and modifications which are made on PWRs cause scheduled unavailabilities of equipment or systems which might harm the safety of the installation, in spite of the low level of decay heat during this period. The pumps in the auxiliary feedwater system, component cooling water system, service water system, the water injection arrays (LPIS, HPIS, CVCS), and the containment spray system may have scheduled unavailability, as well as the power supply of the electricity boards. The EDF utility is aware of the risks related to these situations for which accident procedures have been set up and hence has proposed limiting downtime for this equipment during the shutdown period, through technical specifications. The project defines the equipment required to ensure the functions important for safety during the various shutdown phases (criticality, water inventory, evacuation of decay heat, containment). In order to be able to judge the acceptability of these specifications, the IPSN, the technical support of the Service Central de Surete des Installations Nucleaires, has used probabilistic methodology to analyse the impact on the core melt probability of these specifications, for a French 900 MWe PWR

HTC Experimental Program: Validation and Calculational Analysis

Energy Technology Data Exchange (ETDEWEB)

Fernex, F.; Ivanova, T.; Bernard, F.; Letang, E. [Inst Radioprotect and Surete Nucl, F-92262 Fontenay Aux Roses (France); Fouillaud, P. [CEA Valduc, Serv Rech Neutron and Critcite, 21 - Is-sur-Tille (France); Thro, J. F. [AREVA NC, F-78000 Versailles (France)

2009-05-15

In the 1980's a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a water-moderated lattice was conducted at the Apparatus B experimental facility in Valduc (Commissariat a I'Energie Atomique, France) with the support of the Institut de Radioprotection et de Surete Nucleaire and AREVA NC. Four series of experiments were designed to assess profit associated with actinide-only burnup credit in the criticality safety evaluation for fuel handling, pool storage, and spent-fuel cask conditions. The HTC rods, specifically fabricated for the experiments, simulated typical pressurized water reactor uranium oxide spent fuel that had an initial enrichment of 4. 5 wt% {sup 235}U and was burned to 37.5 GWd/tonne U. The configurations have been modeled with the CRISTAL criticality package and SCALE 5.1 code system. Sensitivity/uncertainty analysis has been employed to evaluate the HTC experiments and to study their applicability for validation of burnup credit calculations. This paper presents the experimental program, the principal results of the experiment evaluation, and modeling. The HTC data applicability to burnup credit validation is demonstrated with an example of spent-fuel storage models. (authors)

One decade after Chernobyl: Environmental impact and prospects for the future. Working material

International Nuclear Information System (INIS)

1996-01-01

One decade after the accident at the Chernobyl nuclear power plant, the levels of radioactive contamination of the affected territories are generally well known. Through the impetus from national and international organizations, scientific and technical studies are being undertaken in order to reach a better understanding of the circumstances of the accident, the behavior of radioactive materials in different environmental media and the most efficient ways of decontamination. Doses received by populations have been and continue to be assessed. Taking into account the completed and ongoing studies by other organizations as well as the results of the International Chernobyl Project completed in 1991, the IAEA formulated, in co-operation with the Institut de Protection et de Surete Nucleaire (IPSN) in France, a project focusing on the environmental impact of the Chernobyl accident. The project aimed to make the findings of the scientists understandable to and relevant for the decision makers, who form the target group. Thus the study focused on the environmental impact in the future and was complementary to the other studies performed. It was a synthesis of available material and reports. Refs, figs, tabs

One decade after Chernobyl: Environmental impact and prospects for the future. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

One decade after the accident at the Chernobyl nuclear power plant, the levels of radioactive contamination of the affected territories are generally well known. Through the impetus from national and international organizations, scientific and technical studies are being undertaken in order to reach a better understanding of the circumstances of the accident, the behavior of radioactive materials in different environmental media and the most efficient ways of decontamination. Doses received by populations have been and continue to be assessed. Taking into account the completed and ongoing studies by other organizations as well as the results of the International Chernobyl Project completed in 1991, the IAEA formulated, in co-operation with the Institut de Protection et de Surete Nucleaire (IPSN) in France, a project focusing on the environmental impact of the Chernobyl accident. The project aimed to make the findings of the scientists understandable to and relevant for the decision makers, who form the target group. Thus the study focused on the environmental impact in the future and was complementary to the other studies performed. It was a synthesis of available material and reports. Refs, figs, tabs.

Communications in case of radiological emergency: expertise exchange between IPSN and two agricultural branches of the region Provence-Alpes-Cote d'Azur

International Nuclear Information System (INIS)

Berthier, Laure; Pupin, Vincent

1997-01-01

A patrimonial audit organized by the 'Institut de Protection et de Surete Nucleaire' (IPSN) has mobilized the expertise of specialists in the nuclear sector and two sensible agricultural branches (salads and sheep) in Province-Alpes-Cote d'Azur (PACA) on the topic of communications among them in case of contamination of region (radiological emergency situation). Having in view their offers and requests of information we have identified the common fields of action involving the four concerned high-ranking actors of different culture: agricultural Administration, agricultural professionals, nuclear sector authorities and elected persons. We have analyzed the actions already completed in this field and established that the Chernobyl accident was a graveyard from the point of view of mobilization and awareness of actors. A project in the future allowed the determination of the stake implied in the relation between IPSN and the two branches and thus to establish the conditions of reaction in case of radiological emergency. Hence, we were able to make propositions to IPSN for building a French agro-nuclear expertise based upon a relation network covering (and even surpassing) the studied agricultural branches

Report on the IRSN's investigations following the widespread detection of 106Ru in Europe early October 2017

International Nuclear Information System (INIS)

2018-01-01

Ruthenium-106 ( 106 Ru) is an anthropogenic radionuclide which is usually not observed in the atmosphere. Early October 2017, it was detected in almost all European countries. Observed activities ranged from a few μBq/m 3 to about 150 mBq/m 3 . Although, these concentrations did not pose any health or environmental issues, this widespread detection suggested that the source-term must have been quite high. Taken into account all these elements, IRSN decided to perform further investigations in order (1) to identify the possible location of the source, 2) to assess the total activity released and the release duration and 3) to understand the process that could be at the origin of the release of 106 Ru alone. The present report summarizes the main results of these investigations

The transport safety of radioactive matters; La surete des transports des matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

Landier, D.; Louet, Ch.A.; Robert, Ch. [Autorite de Surete Nucleaire, 75 - Paris (France); Binet, J. [Commission europeenne, DG Energie et transports, Bruxelles (Belgium); Malesys, P. [TN International, 75 - Paris (France); Pourade, C. [Societe Dangexpress, 78 - St Remy l' Honore (France); Le Meur, A.; Robert, M. [Societe Nationale des Chemins de fer Francais, 75 - Paris (France); Turquet de Beauregard, G.Y.; Hello, E. [CIS bio, 91 - Gif sur Yvette (France); Laumond, A. [Electricite de France (EDF), 75 - Paris (France); Regnault, Ph.; Gourlay, M. [AREVA NC, 78 - Velizy Villacoublay (France); Bruhl, G. [CEA Fontenay-aux-Roses, Dir. de la Protection et de la Surete Nucleaire, 92 (France); Malvache, P.; Dumesnil, J. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Cohen, B. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France); Sert, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Pain, M. [Ministere de l' Interieur, et de l' Amenagement du Territoire, Dir. de la Defense et la Securite Civiles, 75 - Paris (France); Green, L.; Hartenstein, M. [World Nuclear Transport Institute, London (United Kingdom); Stewart, J. [Ministere des Transport, Royaume Uni (United Kingdom); Cottens, E.; Liebens, M. [Agence Federale de Controle Nucleaire (Belgium); Marignac, Y. [Wise, 75 - Paris (France)

2007-02-15

Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

Modernization of the french early warning network in IRSN, experience feedback and perspectives

Energy Technology Data Exchange (ETDEWEB)

Debayle, C.; Bardet, A.; Beguin-Leprieur, M.; Chevreuil, M.; Malfait, V.; Mechenet, V. [PRP-ENV/SESURE/LS2A (France)

2014-07-01

Developed few years after the Chernobyl accident in 1991, the French early warning network, Teleray, composed by 160 ambient dose equivalent rate probes, had operated for 15 years. It was decided in 2007 to modernize this facility in order to keep the infrastructure up-to-date. The sensors, the data transmission network and the supervising system were considered separately, but each development took care about the modularity of the final IT system. After a benchmarking period and technical choices, a five years project started with the aim to increase the number of probes to 420, especially around the French nuclear facilities, to change the technology and the IT system including a new data transmission network. The project kick-off was planned in june 2011, but due to the Fukushima accident, the French government asked IRSN to implement a probe on the roof of the French embassy in Tokyo on March 18, 2011. Results and feedback will be discussed, focusing on new approach about data analysis purpose. In 2014, the modernization of this network will be finished one year before it was expected and with significant cost savings. All the relevant phase of the project will be described, including time schedule and economical aspects, with the aim to describe how it is now considered fundamental to have complementary mobile systems in case of nuclear crisis. Document available in abstract form only. (authors)

Synthesis of the IRSN report on the management activities subcontracted by EDF in currently exploited pressurized water reactors. Opinion related to the management of activities subcontracted by EDF in currently exploited PWRs

International Nuclear Information System (INIS)

2015-01-01

A first document proposes a synthesis of an assessment performed by the IRSN which more particularly addressed how the client (EDF) takes up nuclear safety challenges, and its ability to transmit them to the subcontractor and assess the way he takes them up, how the subcontractor adopts these safety issues and translate them into an adapted technical action, the efficiency of information transmission from the subcontractor to the operator, and the way EDF takes the evolution and increase of activities into account in its subcontracting management strategy on the medium and long terms in relationship with modifications generated by recent measures (additional safety assessments, project of lifetime extension). Another document states the opinion of the permanent group of experts for nuclear reactors on these issues, and outlines some specific aspects (unit outage and maintenance planning, risk analysis, intervention preparation and monitoring, return on experience and improvement of the management of subcontracted activities, evolution and increase of activities). Some recommendations are also stated. A third document is a letter sent by the ASN on the same issues which discusses problems and issues related to subcontracting and has been the basis of the IRSN assessment

Factors and uncertainties in the profitability of using nuclear energy in desalination of water; Facteurs et incertitudes de la rentabilite du recours a l'energie nucleaire dans le dessalement des eaux

Energy Technology Data Exchange (ETDEWEB)

Thiriet, L; Lievre, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1969-07-01

One of the economic advantages of nuclear energy consists of the small proportional element in its cost structure. Economies of scale favour the nuclear station as compared with the conventional thermal one, and when the demand for electricity and heat, in particular for desalination, are sufficient, nuclear energy may, subject to certain conditions, prove advantageous. The object of this paper is to discuss the validity of the conclusions reached according to the hypotheses adopted. In the first part, the different kind of uncertainties connected with technical, economic and financial data (the various transmission coefficients, the life of equipment according to the choice of materials, changes in prices, the form of price functions and interest rates), and with the various constraints, are examined and discussed. In the second part the uncertainties connected with the method of optimisation used and the criterion of selection adopted are examined and discussed. It is shown thereby that it is usually extremely difficult to assume absolutely the competitiveness, or conversely the non-competitiveness, of using nuclear energy in the desalination of water, and that a large number of aspects have to be carefully examined. (author) [French] On sait que l'un des avantages economiques de l'energie nucleaire reside dans la faible part proportionnelle dans la structure de son cout. Les economies d'echelle favorisent le nucleaire par rapport au thermique classique, et lorsque les demandes d'electricite et de chaleur, notamment pour le dessalement, sont suffisantes on peut envisager favorablement, sous certaines hypotheses, le recours a l'energie nucleaire. L'objet de cette communication est de discuter la validite des conclusions auxquelles on parvient selon les hypotheses envisagees. Dans une premiere partie, on etudie et on discute les differentes sortes d'incertitudes, liees aux donnees techniques, economiques et financieres (les divers coefficients de transmission, les

Study of some continuous spectra produced by nuclear reactions with light nuclei; Etude de quelques spectres continus produits par reactions nucleaires avec des noyaux legers

Energy Technology Data Exchange (ETDEWEB)

Marquez, L

1966-07-01

The continuous spectra coming from several nuclear reactions with light nuclei were measured. The spectra can be explained by a two-step reaction mechanism; however, the reactions produced by {sup 6}Li are different. A mechanism was proposed to explain their spectra based on the following assumptions: {sup 6}Li makes a nuclear molecule with the target which subsequently breaks up in such a way that an {alpha} particle comes out with the kinetic energy that it has in the molecule. The calculated spectra and those measured are in good agreement. (author) [French] Nous avons mesure les spectres continus produits dans plusieurs reactions nucleaires avec des noyaux legers. A l'exception des spectres produits par {sup 6}Li, on a trouve qu'on pouvait expliquer ces spectres par le mecanisme des reactions en deux etapes. Nous avons propose un mecanisme pour expliquer les spectres produits par {sup 6}Li. On suppose que {sup 6}Li forme une molecule nucleaire avec la cible qui eclate ensuite de facon telle qu'une particule alpha de la molecule sort avec l'energie cinetique de son mouvement propre dans la molecule. Les spectres calcules avec ces hypotheses et les spectres mesures sont en bon accord. (auteur)

Molten salts in nuclear reactors; Les sels fondus dans les reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Dirian, J; Saint-James, [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1959-07-01

Collection of references dealing with the physicochemical studies of fused salts, in particular the alkali and alkali earth halides. Numerous binary, ternary and quaternary systems of these halides with those of uranium and thorium are examined, and the physical properties, density, viscosity, vapour pressure etc... going from the halides to the mixtures are also considered. References relating to the corrosion of materials by these salts are included and the treatment of the salts with a view to recuperation after irradiation in a nuclear reactor is discussed. (author) [French] Bibliographie regroupant l'etude physico-chimique des sels fondus, en particulier des halogenures alcalins et alcalino-terreux. On etudie de nombreux systemes binaires, ternaires et quaternaires de ces halogenures avec des halogenures d'uranium, et de thorium. On etudie egalement les proprietes physiques des halogenures ou des melanges d'halogenures (densite, viscosite, tension de vapeur, etc...). On donne egalement des references quant a la corrosion des materiaux par ces sels, et le traitement de ceux-ci en vue de recuperation, apres irradiation dans un reacteur nucleaire. (auteur)

Production of nuclear graphite in France; Production de graphite nucleaire en France

Energy Technology Data Exchange (ETDEWEB)

Legendre, P; Mondet, L [Societe Pechiney, 74 - Chedde (France); Arragon, Ph; Cornuault, P; Gueron, J; Hering, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

The graphite intended for the construction of the reactors is obtained by the usual process: confection of a cake from coke of oil and tar, cooked (in a electric oven) then the product of cook is graphitized, also by electric heating. The use of the air transportation and the control of conditions cooking and graphitization have permitted to increase the nuclear graphite production as well as to better control their physical and mechanical properties and to reduce to the minimum the unwanted stains. (M.B.) [French] Le graphite destine a la construction des reacteurs est obtenu par le procede usuel: confection d'une pate a partir de coke de petrole et de brai, cuisson de cette pate (au four electrique) puis graphitation du produit cuit, egalement par chauffage electrique. L'usage du transport pneumatique et le controle des conditions cuisson et de graphitation ont permit d'augmenter la production de graphite nucleaire ainsi que de mieux controler ses proprietes physiques et mecaniques et de reduire au minimum les souillures accidentelles. (M.B.)

The pulsed neutron method applied to the determination of the nuclear constants of graphite (1961); La methode des neutrons pulses appliquee a la determination des constantes nucleaires du graphite (1961)

Energy Technology Data Exchange (ETDEWEB)

Lalande, J [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1961-07-01

A method for determining the nuclear constants {sigma}{sub a} and {lambda}{sub t} of a moderator is described. The disappearance of a burst of neutrons introduced into a finite medium is studied as a function of time. This decrease in the thermal neutron density is the product of two exponentials; one representing the absorption, the other the leakage. By varying one or other of these factors, the constants of the factor left unvaried can be determined, and from this the nuclear constant values are deduced. (author) [French] On decrit une methode permettant de determiner les constantes nucleaires {sigma}{sub a} et {lambda}{sub t} d'un moderateur. On etudie la decroissance dans le temps d'une bouffee de neutrons introduite dans un milieu fini. Cette decroissance de la densite en neutrons thermiques est le produit de deux exponentielles; l'une represente l'absorption, l'autre les fuites. Par variation de l'un ou l'autre de ces facteurs, on determine les constantes du facteur laisse invariant dont on deduit les valeurs des constantes nucleaires. (auteur)

Organizing a complex transport while guaranteeing safety and transparency: the example of vitrified wastes sent back to Germany

International Nuclear Information System (INIS)

Krochmaluk, Julie; Lebrun, Marc; Delmestre, Alain; Barbey, Pierre; Bonvalot, Vanessa; Belleville, Didier; Rollinger, Patrice; Alter, Ulrich

2012-01-01

This chapter is made of several small articles entitled: - 'Les controles avant le depart du convoi franco-allemand' (Controls before the departure of the French-German convoy); - 'La supervision des transports de matieres radioactives: une approche extensive de la surete des operations' (The supervision of radioactive material transports: an extended approach of operation safety); - 'Le dispositif d'information du public sur le transport des substances radioactives mis en place par l'ASN' (The plan implemented by the ASN for public information on nuclear materials transport); - 'Le recours de l'ASN a l'expertise de l'ACRO sur le convoi de colis de dechets vitrifies vers l'Allemagne' (The appeal of the ASN to the ACRO's expertise on the vitrified parcel convoy to Germany); - 'La participation du collectif STOP-EPR a l'inspection de l'ASN du convoi de colis de dechets vitrifies vers l'Allemagne' (The participation of the STOP-EPR collective to the control by the ASN of the vitrified parcel convoy to Germany); - 'La securite et la surete: des valeurs que le Groupe SNCF partage' (Security and safety: values which are shared by the SNCF Group); - 'Le transport de matieres nucleaires entre la France et l'Allemagne au cours des 40 dernieres annees' (Transport of nuclear materials between France and Germany during the last 40 years). Addressing the case of vitrified wastes transported back to Germany, the articles indicate the controls performed in France before convoy departure, discuss the approach adopted for the safety of radioactive material transport, comment the management of public information by the ASN for such transports, comment the intervention of the ACRO (Association for the control of radioactivity in western France) on the request of the ASN and the participation of a collective group (STOP-EPR) to the inspection of a convoy, outline the commitment of the French Railways (SNCF) in terms of security and safety, and give a qualitative and quantitative

CO{sub 2} direct cycles suitable for AGR type reactors; Cycles directs de gaz carbonique applicables aux reacteurs du genre AGR

Energy Technology Data Exchange (ETDEWEB)

Maillet, E [Commissariat a l' Energie Atomique. Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

1967-10-01

The perspectives given by the gas turbines under pressure, to build simple nuclear power plants and acieving significantly high yield, are specified. The CO{sub 2} is characterised by by good efficiency under moderate temperature (500 to 750 Celsius degrees), compactness and the simpleness of machines and the safe exploitation (supply, storage, relief cooling, thermosyphon). The revision of thermal properties of the CO{sub 2} and loss elements show that several direct cycles would fit in particular to the AGR type reactors. Cycles that would diverge a little from classical models and able to lead to power and heat generation can lead by simple means to the best results. Several satisfying solutions present for the starting up, the power regulation and the stopping. The nuclear power plant components and the functioning safety are equally considered in the present report. The conclusions stimulate the studies and realizations of carbon dioxide gas turbines in when approprite. [French] Les perspectives offertes par la turbine a gaz sous pression, pour construire des centrales nucleaires simples et de rendement progressivement eleve, se precisent actuellement. le CO{sub 2} se distingue par sa bonne efficacite a temperature moderee (500 a 750 degres celsius), la compacite et la simplicite des machines, et la surete qu'il apporte a l'exploitation ( approvisionnement, stockage, refroidissement de secours, thermosiphon). La revision des proprietes thermophysiques du CO{sub 2} et des elements de pertes montre que divers cycles directs conviendraient en particulier aux reacteurs agr ou derives. Des cycles s'ecartant peu des modeles classiques, et se pretant ulterieurement a la production simultanee d'electricite et de chaleur, peuvent conduire par des moyens simples aux meilleurs resultats d'ensemble. Plusieurs solutions satisfaisantes se presentent pour le demarrage, le reglage de la puissance et l'arret. Les composants de la centrale et la surete de fonctionnement sont

Safety of the Transport of Radioactive Materials for Civilian Use in France. Lessons learned by IRSN from analysis of significant events reported in 2012 and 2013

International Nuclear Information System (INIS)

2015-01-01

Every two years since 2008, IRSN has published in a report the lessons learnt from its analysis of significant events involving the transport of radioactive materials for civilian purposes in France. Each year in France, some 770,000 shipments of radioactive materials for civilian use are done by road, railway, inland waterway, sea and air. For 2012 and 2013, the report did not find evidence of degradation compared with previous years, particularly for industrial activities in the nuclear power industry, which raise the most significant safety issues. Since 1999, approximately a hundred events are reported each year, which represents, on average, one event per 10,000 packages transported. IRSN notes that none of the events that occurred over the two years had an impact on public health or environmental protection. Events involving a defect in the closure of spent fuel shipping packages and deviations concerning the content of the packages, which had increased in 2010 and 2011, are now down. It would seem to confirm that the organizational measures implemented by those sending the packages have had a positive impact. Previous trends which brought to light failures in the preparation of packages and their handling, in particular in the medical sector, have been confirmed. Even if most of the packages concerned contain low levels of radioactivity, recurrence of these events confirms the value of implementing appropriate preventive actions on the part of the companies involved. Lastly, descriptions of several typical events that occurred in 2012 and 2013 provide illustrations of the analyses that were performed on actual cases

Characterisation of the IRSN CANEL/T400 facility producing realistic neutron fields for calibration and test purposes

International Nuclear Information System (INIS)

Gressier, V.; Lacoste, V.; Lebreton, L.; Muller, H.; Pelcot, G.; Bakali, M.; Fernandez, F.; Tomas, M.; Roberts, N. J.; Thomas, D. J.; Reginatto, M.; Wiegel, B.; Wittstock, J.

2004-01-01

The new CANEL/T400 facility has been set-up at the Inst. for Radiological Protection and Nuclear Safety (IRSN) to produce a realistic neutron field. The accurate characterisation of this neutron field is mandatory since this facility will be used as a reference neutron source. For this reason an international measuring campaign, involving four laboratories with extensive expertise in neutron metrology and spectrometry, was organised through a concerted EUROMET project. Measurements were performed with Bonner sphere (BS) systems to determine the energy distribution of the emitted neutrons over the whole energy range (from thermal energy up to a few MeV). Additional measurements were performed with proton recoil detectors to provide detailed information in the energy region above 90 keV. The results obtained by the four laboratories are in agreement with each other and are compared with a calculation performed with the MCNP4C Monte-Carlo code. As a conclusion of this exercise, a reliable characterisation of the CANEL/T400 neutron field is obtained. (authors)

Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

Energy Technology Data Exchange (ETDEWEB)

Le Coroller, Y. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-09-01

A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux

Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

Energy Technology Data Exchange (ETDEWEB)

Le Coroller, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-09-01

A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux millimetres fonctionnent

IRSN statement of four studies presented within the frame of the radioactive material and waste management national plan (PNGMDR)

International Nuclear Information System (INIS)

2009-01-01

This document contains the comments and assessments by the IRSN (the French Institute for radioprotection and nuclear safety) on studies which were respectively dealing with: the warehousing of tritiated waste, the sustainable management of used sealed radioactive sources and the possibility of storing other types of wastes with graphite and radiferous wastes, studies of valorization of radioactive materials without any present use. For the first one (tritiated wastes), this report describes the context, specifies the various considered wastes and their characteristics and properties, specifies the storage requirements, and outlines the environmental impacts of such a warehousing. For the second one (sealed radioactive sources and other graphite and radiferous wastes) it specifies and comments the considered wastes and the storage technical options in both cases. For the third one (valorization of radioactive materials) it reviews the available processes for uranium, plutonium, and thorium, and gives a brief assessment of the experience performed by the Rhodia company in La Rochelle

Assessment of the radiological status of the French environment in 2008: synthesis of the results of the IRSN's watch networks

International Nuclear Information System (INIS)

2009-01-01

This report presents the data obtained in 2008 within the frame of the follow-up by the IRSN of the levels of radioactivity on the French national territory. After having recalled the objectives of this radiological watch of the environment and its organization, the report describes the methodology adopted for the choice of the watch stations, the choice of the environmental matrices, the analysis plans, the sample preparation and packing. It presents the various radionuclides which are naturally or artificially present in the French environment. Then, it presents the results obtained by the different station networks by watching the atmosphere, rivers and soils, or coasts. The report recalls and comments the different radiological events which occurred in 2008, i.e. the detection of different radionuclides in different environments: nuclear plants, nuclear research centres, nuclear sites, nuclear industries, nuclear waste storage sites, nuclear marine bases, rivers

Simulation of the Phebus FPT1 experiment

International Nuclear Information System (INIS)

Amador G, R.; Nunez C, A.; Angel M, E. Del

2003-01-01

The present work describes the pattern of the denominated installation Phebus developed and used by the National Commission of Nuclear Security and Safeguards for their participation in the International Standard Problem ISP-46, organized by the Nuclear Energy Agency (NEA). The exercise consisted on the simulation of the denominated experiment Phebus FPT1 carried out in the experimental installation Phebus located in the Institut de Protection et de Surete Nucleaire of France. The experiment Phebus FP1 had as objective to evaluate the capacity of different computer codes to model in integral form the physical processes that are carried out during a severe accident in a pressurized water reactor (PWR), from the degradation of the core until the late stage with the formation of a pool of fused material, hydrogen production, liberation and transport of fission products, phenomena in the contention and chemistry of the iodine. The CNSNS uses the version bi of the SCDAPSIM code developed by the company Innovative Software Systems to simulate the International Standard Problem 46. The obtained results showed that the code is able to predict the thermohydraulic part of the experiment, however the same thing doesn't happen to the parameters related with the one fused of the fuel. (Author)

Simulation of the Phebus FPT1 experiment; Simulacion del experimento Phebus FPT1

Energy Technology Data Exchange (ETDEWEB)

Amador G, R.; Nunez C, A.; Angel M, E. Del [CNSNS, Dr. Barragan No. 779, 03020 Mexico D.F. (Mexico)]. E-mail: ragarcia@cnsns.gob.mx

2003-07-01

The present work describes the pattern of the denominated installation Phebus developed and used by the National Commission of Nuclear Security and Safeguards for their participation in the International Standard Problem ISP-46, organized by the Nuclear Energy Agency (NEA). The exercise consisted on the simulation of the denominated experiment Phebus FPT1 carried out in the experimental installation Phebus located in the Institut de Protection et de Surete Nucleaire of France. The experiment Phebus FP1 had as objective to evaluate the capacity of different computer codes to model in integral form the physical processes that are carried out during a severe accident in a pressurized water reactor (PWR), from the degradation of the core until the late stage with the formation of a pool of fused material, hydrogen production, liberation and transport of fission products, phenomena in the contention and chemistry of the iodine. The CNSNS uses the version bi of the SCDAPSIM code developed by the company Innovative Software Systems to simulate the International Standard Problem 46. The obtained results showed that the code is able to predict the thermohydraulic part of the experiment, however the same thing doesn't happen to the parameters related with the one fused of the fuel. (Author)

Safety of the pressure vessels of water reactors. Prevention of sudden failure

International Nuclear Information System (INIS)

Petrequin, P.; Barrachin, B.

1975-01-01

From the safety view point the primary circuit is considered as the essential barrier against the diffusion of radioactive products in the event of fuel element failure. The safety of the vessel itself, the failure of which is not accounted for in accident analyses, is based chiefly on a series of preventive measures such as the suitable choice of materials and manufacturing process, compliances with detailed specifications concerning tests and defect tolerances, supervision in service. All these points are examined in detail when the safety analysis is performed. In this context the Service de Recherches Metallurgiques Appliquees assists the Department de Surete Nucleaire in the study of special problems such as the prevention of sudden failure and the characterisation of steels as a function of working conditions, particularly neutron irradiation. The report is thus devoted mainly to the presentation of methods to prevent sudden failure, with special emphasis on the limits of application. Some results obtained at the Service de Recherches Metallurgiques Appliquees on steels typical of those used for water reactor vessels (A533 and A508Cl.3) are given by way of example. Part two concentrates on the role of various factors influencing embrittlement by irradiation [fr

System to forecast health effects in order to determine necessary counter-measures in case an accidental atmospheric release

International Nuclear Information System (INIS)

Merchant, T.E.; Parmentier, N.

1985-01-01

In most accident situations involving radioactivity, the required data are the quantitative evaluation of the relevant constituents of the release and the dose factors applicable for these constituents. In the problem of an atmospheric release of radioactivity a third group of data also comes into play, the meteorological conditions at the site and time of the accident. The solution to this problem is the construction of a computer code which, by employing acquired compositions of the release as well as physical accident conditions (at the time of the incident), can be effectively run to calculate and present useful dosimetric data. To meet this need, an interactive computer program has been constructed by the Institut de Protection et de Surete Nucleaire of the Commissariat a l'Energie Atomique which calculates the gamut of dosimetric and statistical information for a region of accidental radiological concern. Application of the program is such that it outputs dosimetric information and other important data in a form independent of the site under consideration, allowing, at the same time, the computation of the same information for areas where demographics show them to be of the highest radiological concern. All this is done after requiring minimal user input

Criticality accident studies and research performed in the Valduc criticality laboratory, France

International Nuclear Information System (INIS)

Barbry, F.; Fouillaud, P.

2001-01-01

In 1967, the IPSN (Institut de Protection et de Surete Nucleaire - Nuclear Protection and Safety Institute) started studies and research in France on criticality accidents, with the objective of improving knowledge and modelling of accidents in order to limit consequences to the public, the environment and installations. The criticality accident is accompanied by an intense emission of neutronic and gamma radiation and releases of radioactive products in the form of gas and aerosols, generating irradiation and contamination risks. The main objectives of the studies carried out, particularly using the CRAC installation and the SILENE reactor at Valduc (France), were to model the physics of criticality accidents, to estimate the risks of irradiation and radioactive releases, to elaborate an accident detection system and to provide information for intervention plans. This document summarizes the state of knowledge in the various fields mentioned above. The results of experiments carried out in the Valduc criticality laboratory are used internationally as reference data for the qualification of calculation codes and the assessment of the consequences of a criticality accident. The SILENE installation, that reproduces the various conditions encountered during a criticality accident, is also a unique international research tool for studies and training on those matters. (author)

Scientific and technical report, 2000 of the IPSN

International Nuclear Information System (INIS)

2001-01-01

IPSN (Institut de Protection et de Surete Nucleaire) is responsible for dealing with all aspects in the evaluation of safety of nuclear installations involving the human factors. To achieve its objectives, it conducts its own research and development activities on these themes. This report highlights the most significant scientific and technical achievements of the Institut in 2000. Twenty eight reports are presented, grouped in eight sessions, each ones opened by a review paper: the reactors safety, the installations safety, the radioactive materials and transport safety, the public health, the environment protection, the radioactive wastes safety, the crisis management and the IPSN installations. The international research program Phebus PF is detailed, technical progresses concerning the steam generators nondestructive testing or the impact of automation on operator performance are also presented. One session deals with the criticality studies and risk assessment. The control and surveillance of nuclear materials form the subject of research programs and experiments as well as the transport safety. Concerning the public and environment protection inspections, epidemiological studies, radionuclides transportation and radio-contaminant behavior are reported. In the domain of the radioactive wastes safety, the deep underground storage and the model MELODIE are presented. Examples of accidents or the INEX2 exercise are also discussed. (A.L.B.)

The action of the project coordinator with respect to reactor safety

International Nuclear Information System (INIS)

Leclercq, Jacques

1981-01-01

Before describing the various actions of the project coordinator (EDF) entrusted with the building of nuclear power stations, with respect to reactor safety in France, the definition of reactor safety and the various participants are mentioned first. These participants are: the Government Departments and the Experts involved (the Department of Nuclear Safety of the 'Institut de Protection et de Surete Nucleaire' forming the first technical support) and the applicant, namely the EDF. The reactor safety actions of the project coordinator are defined as from the following components: 1 - The targets laid down with respect to safety, the final objective being the protection of workers and the public against the potential dangers of the installations, principally against radiation. 2 - The safety methodology at the design stage of the power station: 'barrier' method, defence method in depth at three levels, lines of assurance method, and probabilistic method. 3 - Safety actions at the construction stage within the context of an assurance of quality programe. 4 - Safety at the trials, commissioning and operating stage, with the backing of the 'Groupe Operationnel de Demarrage (G.O.D.)' and the 'Commission d'Essais sur Site (C.E.S.)'. An initial balance sheet of the reactor safety actions for the PWR units built by the EDF is presented [fr

Scientific and technical report, 2000 of the IPSN; Rapport scientifique et technique 2000 de l'IPSN

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

IPSN (Institut de Protection et de Surete Nucleaire) is responsible for dealing with all aspects in the evaluation of safety of nuclear installations involving the human factors. To achieve its objectives, it conducts its own research and development activities on these themes. This report highlights the most significant scientific and technical achievements of the Institut in 2000. Twenty eight reports are presented, grouped in eight sessions, each ones opened by a review paper: the reactors safety, the installations safety, the radioactive materials and transport safety, the public health, the environment protection, the radioactive wastes safety, the crisis management and the IPSN installations. The international research program Phebus PF is detailed, technical progresses concerning the steam generators nondestructive testing or the impact of automation on operator performance are also presented. One session deals with the criticality studies and risk assessment. The control and surveillance of nuclear materials form the subject of research programs and experiments as well as the transport safety. Concerning the public and environment protection inspections, epidemiological studies, radionuclides transportation and radio-contaminant behavior are reported. In the domain of the radioactive wastes safety, the deep underground storage and the model MELODIE are presented. Examples of accidents or the INEX2 exercise are also discussed. (A.L.B.)

Scientific and technical report, 2000 of the IPSN; Rapport scientifique et technique 2000 de l'IPSN

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

IPSN (Institut de Protection et de Surete Nucleaire) is responsible for dealing with all aspects in the evaluation of safety of nuclear installations involving the human factors. To achieve its objectives, it conducts its own research and development activities on these themes. This report highlights the most significant scientific and technical achievements of the Institut in 2000. Twenty eight reports are presented, grouped in eight sessions, each ones opened by a review paper: the reactors safety, the installations safety, the radioactive materials and transport safety, the public health, the environment protection, the radioactive wastes safety, the crisis management and the IPSN installations. The international research program Phebus PF is detailed, technical progresses concerning the steam generators nondestructive testing or the impact of automation on operator performance are also presented. One session deals with the criticality studies and risk assessment. The control and surveillance of nuclear materials form the subject of research programs and experiments as well as the transport safety. Concerning the public and environment protection inspections, epidemiological studies, radionuclides transportation and radio-contaminant behavior are reported. In the domain of the radioactive wastes safety, the deep underground storage and the model MELODIE are presented. Examples of accidents or the INEX2 exercise are also discussed. (A.L.B.)

Modelling of atmosphere mixing and stratification in the Tosqan experimental facility with the CFX code

International Nuclear Information System (INIS)

Kljenak, I.; Babic, M.; Mavko, B.; Bajsic, I.

2005-01-01

Full text of publication follows: During the course of a severe accident in a Light Water Reactor nuclear power plant, large amounts of hydrogen would presumably be generated and released into the containment. The integrity of the containment could be threatened due to hydrogen combustion. The prediction of hydrogen behaviour at severe accident conditions is thus important for devising adequate accident management procedures. Lately, investigations about the possible application of so-called Computational Fluid Dynamics (CFD) codes for this purpose have been started within the nuclear community. These investigations are complemented by adequate experiments. In the proposed work, the CFD code CFX4.4 was used to simulate an experiment in the TOSQAN facility, which is located at the Institut de Radioprotection et de Surete Nucleaire (IRSN) in Saclay (France). The facility consists of a cylindrical vessel (volume: 7 m3), in which gases are injected. The temperature of the vessel walls may be controlled. Steam may condense on some parts of the walls, where the controlled temperature is maintained at sufficiently low levels. In the considered experiment, which was also proposed for the OECD/NEA International Standard Problem No.47, air was initially present in the vessel, and steam, air and helium were injected during different phases of the experiment at various mass flow rates. The thermal-hydraulic behaviour was determined by the dominant physical phenomena: gas injection, steam condensation, heat transfer and buoyant flow. During certain phases of the experiment, steady states were reached when the steam condensation rate became equal to the steam injection rate, with all boundary conditions (wall temperatures and injection rates) remaining constant. In the proposed work, three intermediate steady states, which were obtained with different boundary conditions, were simulated independently. The main purpose was to reproduce the non-homogeneous temperature, species

Dismantling of Evaporators by Laser Cutting Measurement of Secondary Emissions

International Nuclear Information System (INIS)

Pilot, Guy; Fauvel, Sylvain; Gosse, Xavier; De Dinechin, Guillaume

2006-01-01

In order to dismantle the evaporators of an obsolete reprocessing plant in Marcoule, studies were carried out by IRSN (Institut de Radioprotection et de Surete Nucleaire) / DSU/SERAC in cooperation with CEA (power laser group) on the laser cutting of steel structures, on the request of COGEMA (now AREVA NC) /Marcoule (UP1 dismantling project manager) and CEA/UMODD (UP1 dismantling owner). The aim of these studies was: - to quantify and to characterize the secondary emissions produced by Nd-YAG laser cutting of Uranus 65 steel pieces representative of UP1 evaporator elements and to examine the influence of different parameters, - to qualify a pre-filtration technique and particularly an electrostatic precipitator, - to compare the Nd-YAG used with other cutting tools previously studied. The experiments, which took place in a 35 m 3 ventilated cutting cell, allow to underline the following points: for the Uranus 65 steel, the sedimented dross, the deposits on the walls of the cutting cell and the aerosols drawn in the ventilation exhaust duct (∼ 275 m 3 /h), represent respectively between 92% and 99%, between 0.01% and 0.25% and between 1% and 8% of the total collected mass, the attached slag varies much from one configuration to the other and can sometimes amount to a relatively important fraction of the total mass, the kerves vary from 2 mm up to 7 mm for the Uranus 65 steel plates (thickness: 13.8 mm for the single plate and 12.8 + 3.5 mm for the double plate), the exhausted aerosol mass per cut length (g/m) decreases with the cutting speed, varies neither with the stand-off nor with the gas pressure, is dependent upon the gas nature (for the double plate), increases with the laser power, is strongly affected by the nature of the steel (stainless steel or mild steel) and is independent upon the plate position, the size distribution of aerosols is multimodal with a main mode often around 0.45 μm, the electrostatic precipitator has been a satisfactory prefilter

Iodine behaviour under LWR accident conditions: Lessons learnt from analyses of the first two Phebus FP tests

International Nuclear Information System (INIS)

Girault, N.; Dickinson, S.; Funke, F.; Auvinen, A.; Herranz, L.; Krausmann, E.

2006-01-01

The International Phebus Fission Product programme, initiated in 1988 and performed by the French 'Institut de Radioprotection et de Surete Nucleaire' (IRSN), investigates through a series of in-pile integral experiments, key phenomena involved in light water reactor (LWR) severe accidents. The tests cover fuel rod degradation and the behaviour of fission products released via the primary coolant circuit into the containment building. The results of the first two tests, called FPT0 and Ftp, carried out under low pressure, in a steam rich atmosphere and using fresh fuel for Ftp and fuel burned in a reactor at 23 GWdt -1 for Ftp, were immensely challenging, especially with regard to the iodine radiochemistry. Some of the most important observed phenomena with regard to the chemistry of iodine were indeed neither predicted nor pre-calculated, which clearly shows the interest and the need for carrying out integral experiments to study the complex phenomena governing fission product behaviour in a PWR in accident conditions. The three most unexpected results in the iodine behaviour related to early detection during fuel degradation of a weak but significant fraction of volatile iodine in the containment, the key role played by silver rapidly binding iodine to form insoluble AgI in the containment sump and the importance of painted surfaces in the containment atmosphere for the formation of a large quantity of volatile organic iodides. To support the Phebus test interpretation small-scale analytical experiments and computer code analyses were carried out. The former, helping towards a better understanding of overall iodine behaviour, were used to develop or improve models while the latter mainly aimed at identifying relevant key phenomena and at modelling weaknesses. Specific efforts were devoted to exploring the potential origins of the early-detected volatile iodine in the containment building. If a clear explanation has not yet been found, the non-equilibrium chemical

Radon exposure and mortality among the French cohort of uranium miners: 1946-1999

International Nuclear Information System (INIS)

Vacquier, B.; Tirmarche, M.; Laurier, D.; Caer, S.; Quesne, B.

2006-01-01

Full text of publication follows: The French cohort of uranium miners aims at evaluating the mortality risk of miners exposed to low levels of radon and its decay products and to other occupational hazards. Its primary aim is the quantification of the relationship between cumulated radon exposure and the risk of lung cancer death. However this study also allows to analyse risks for causes of death other than lung cancer. We present a new analysis of the mortality based on an extended follow-up of the cohort to end of 1999. Materials and methods: The French cohort of uranium miners has been followed by the Institut de Radioprotection et de Surete Nucleaire (I.R.S.N.) since the 1980's, in collaboration with the Occupational Medical Service of Compagnie Generale des Matieres Nucleaires (Cogema). The cohort was recently enlarged and the follow-up extended up to 1999. It includes men employed as miners for at least 1 year since 1946 at the Commissariat a l Energie Atomique (Cea) or at the Cogema. Individual vital status was ascertained through a national database and causes of death were determined according to death certificates. For each miner, yearly radon exposures was reconstructed and expressed in working level month (W.L.M.). Risk of death was estimated relatively to external reference rates from the general French male population. The classical method of standardized mortality ratios (S.M.R.s) was used to adjust for age and calendar year. Exposure-risk relationships have been estimated by Poisson regression, using a linear excess relative risk (E.R.R.) model with a lag time of 5 years. Results: The cohort comprises 5,098 miners. The mean duration of follow -up is 30.1 years (total of 153,272 person-years). The number of radon exposed miners is 4,134 with an average cumulative radon exposure of 36.5 W.L.M.. Miners lost to follow-up represent 1.4% of the cohort. A total of 1,471 deaths before age 85 is observed up to 1999. The analysis shows no excess for all

Synthesis of tritium measurement results performed by IRSN and CEA from November 5, 2010, to February 1, 2012, in the environment of the 2M Process company building at Saint-Maur-des-Fosses; Synthese des resultats des mesures de tritium effectuees par l'IRSN et le CEA du 5 novembre 2010 au 1er fevrier 2012 dans l'environnement de l'entreprise 2M Process a Saint-Maur-des-Fosses

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-02-22

A building of 2M Process company at Saint-Maur-des-Fosses (France) has been accidentally contaminated after the handling of a tritium contaminated device. The consequence has been a tritium release inside and in the close environment of the building. Since November 5, on request of the French nuclear safety authority (ASN), the French institute of radiation protection and nuclear safety (IRSN) has performed tritium measurements in water, air and plants sampled in the vicinity of the building in order to delimit the contaminated area and to follow its decay during and after the cleansing of the building. From March 16, 2011 onward, the IRSN's monitoring has been lightened as an answer to the complementary monitoring implemented by the CEA in the framework of the environment monitoring plan ordered by the Prefecture. The results published in previous reports have shown a strong contamination of the building and the presence of significant amounts of tritium in plant leaves and superficial waters in a 50 m radius around the 2M Process building. This note makes a synthesis of the tritium concentrations measured in plant leaves, surface waters, air, and rainwater sampled near the 2M Process building since November 5, 2010, and up to February 1, 2012. (J.S.)

Generalities on nuclear accidents and their short-dated and middle-dated management; Generalites sur les accidents nucleaires et leur gestion a court terme et a long terme

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

All the nuclear activities present a radiation risk. The radiation exposure of the employees or the public, may occur during normal activity or during an accident. The IRSN realized a document on this radiation risk and the actions of protection. The sanitary and medical aspects of a radiation accident are detailed. The actions of the population protection during an accident and the post accident management are also discussed. (A.L.B.)

Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Chooz - 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-06-15

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Flamanville - 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-06-15

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Assessment at the 66. day of projected external doses for populations living in the North-West fallout zone of the Fukushima nuclear accident. Impact of population evacuation measures; Evaluation au 66. jour des doses externes projetees pour les populations vivant dans la zone de retombee Nord-Ouest de l'accident nucleaire de Fukushima. Impact des mesures d'evacuation des populations

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This document reports a dose assessment study performed by the IRSN (the French Radioprotection and Safety Nuclear Institute) 66 days after the Fukushima nuclear accident. A new dose assessment was carried out by IRSN to estimate projected doses due to external exposure from radioactive deposits, for exposure durations of 3 months, 1 year and 4 years before evacuation. The purpose of this report is to provide insight on all radiological assessments performed to the knowledge of the IRSN (the French Radioprotection and Safety Nuclear Institute) to date and the impact of population evacuation measures to be taken to minimize the medium and long-term risks of developing leukaemia or other radiation-induced cancers. This report only considers the external doses already received as well as the doses that may be received in the future from fallout deposits, regardless of doses received previously from the radioactive plume

Nuclear developments at the international inter govern mental level (1961); Developpements nucleaires sur le plan international intergouvernemental (1961)

Energy Technology Data Exchange (ETDEWEB)

Waynbaum, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1961-07-01

The United Nations organisation and nuclear energy rose simultaneously, in 1945, to occupy an important place in the public eye. The spiritual succession of the League of Nations which had foundered during the war was taken up by the new organisation which sought to implant its political ideal in a more tangible reality, so that it might thereby be inspired by concrete and substantial objectives. This is one of the reasons for the existence of the dozen specialized agencies created by the family of the United Nations and dealing with Health, Culture, Agriculture, Finance, etc. Nuclear energy is one of these techniques. Becoming suddenly an important power factor and exploiting for itself the prestige of Science, it became the favorite domain for the growth of this new spirit, as much in its universal form in 1945 as in its more regional form which it was later to adopt. The achievements are numerous and of varying importance; they deserve te be studied carefully. (author) [French] L'organisation des Nations Unies et le nucleaire ont ete places simultanement, en 1945, au premier plan de la scene mondiale. La Societe des Nations ayant sombre pendant la guerre, son heritage spirituel fut recueilli par la nouvelle organisation qui chercha a enraciner son ideal politique dans une realite plus materielle, de facon a y puiser une nourriture concrete et substantielle. C'est une des raisons d'existence de la douzaine d'institutions specialisees gravitant dans la famille des Nations Unies et s'occupant de Sante, de Culture, d'Agriculture, de Finances, etc. Le nucleaire est l'une de ces techniques. Devenu soudainement un facteur primordial de puissance, Cristallisant a son benefice le prestige de la Science, c'etait un terrain de predilection pour le developpement du nouvel esprit, aussi bien sous la forme universelle de 1945, que sous les formes regionales qui ont vu le jour ensuite. Les travaux realises que nombreux, d'importance tres inegale. Ils meritent qu'on les examine

Nuclear developments at the international inter govern mental level (1961); Developpements nucleaires sur le plan international intergouvernemental (1961)

Energy Technology Data Exchange (ETDEWEB)

Waynbaum, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1961-07-01

The United Nations organisation and nuclear energy rose simultaneously, in 1945, to occupy an important place in the public eye. The spiritual succession of the League of Nations which had foundered during the war was taken up by the new organisation which sought to implant its political ideal in a more tangible reality, so that it might thereby be inspired by concrete and substantial objectives. This is one of the reasons for the existence of the dozen specialized agencies created by the family of the United Nations and dealing with Health, Culture, Agriculture, Finance, etc. Nuclear energy is one of these techniques. Becoming suddenly an important power factor and exploiting for itself the prestige of Science, it became the favorite domain for the growth of this new spirit, as much in its universal form in 1945 as in its more regional form which it was later to adopt. The achievements are numerous and of varying importance; they deserve te be studied carefully. (author) [French] L'organisation des Nations Unies et le nucleaire ont ete places simultanement, en 1945, au premier plan de la scene mondiale. La Societe des Nations ayant sombre pendant la guerre, son heritage spirituel fut recueilli par la nouvelle organisation qui chercha a enraciner son ideal politique dans une realite plus materielle, de facon a y puiser une nourriture concrete et substantielle. C'est une des raisons d'existence de la douzaine d'institutions specialisees gravitant dans la famille des Nations Unies et s'occupant de Sante, de Culture, d'Agriculture, de Finances, etc. Le nucleaire est l'une de ces techniques. Devenu soudainement un facteur primordial de puissance, Cristallisant a son benefice le prestige de la Science, c'etait un terrain de predilection pour le developpement du nouvel esprit, aussi bien sous la forme universelle de 1945, que sous les formes regionales qui ont vu le jour ensuite. Les travaux realises que nombreux, d

More than 30 years of opinion of French people on nuclear risks - Special release of the 2012 IRSN opinion survey

International Nuclear Information System (INIS)

El Jammal, Marie-Helene; Rollinger, Francois; Mur, Emmanuelle; Schuler, Matthieu; Tchernia, Jean-Francois

2013-01-01

Illustrated by many graphs and tables, this report comments and discusses the evolution of opinion surveys performed in France on the perception of nuclear risks through thirty annual IRSN opinion surveys. It appears that the opinion on nuclear is rather steady, and that French people have a rather rational perception of risk hierarchy. The first part outlines that unemployment is the main concern for French people, and that environmental concerns depend on current events. The second part analyses the perception of the nuclear risk with respect to other societal concerns and to other risks, and discusses the evolution of opinion from a quantitative to a qualitative sensitivity. The third part addresses the representations people have of nuclear activities and how they challenge the reality: perception of nuclear plants and of radioactive wastes, fear of a serious accident. The last part deals with issues related to responsibilities, abilities and governance: how actors of nuclear risk management are perceived, and expectations in terms of transparency and opinion plurality

Safety and Radiation Protection at Nuclear Power Plants in France in 2014. IRSN's position - Report 2015

International Nuclear Information System (INIS)

2016-01-01

In 2014, none of the significant events reported affected reactor safety. The number of significant radiation protection events fell by 8% compared to 2013 and few of them had any impact on the plants' workers' health, the public's health or the environment. IRSN's point on view on safety and radiation protection of the 58 French nuclear power reactors currently operated by electric utility company EDF. This report is based on the Institute's scientific and technical expertise of significant events, and its analysis of several events that it found to be the most noteworthy for the year. In 2014, the number of significant safety events reported by EDF dropped by 8% compared with 2013, confirming the decrease already observed in 2013 compared with 2012. Early detection by EDF teams of anomalies may have contributed to the fact that none of the events reported in 2014 had a very significant impact on safety. In 2014, ASN did not class any of the events reported on Level 2 on the INES Scale. IRSN points out organisational improvements made by EDF regarding maintenance activities and equipment changes. Nevertheless, half the significant safety events reported by EDF were caused by maintenance errors. Noteworthy, the number of anomalies affecting safety-related equipment in reactors was generally lower in 2014 than in 2013. In 2014, the number of significant radiation protection events fell by 8% compared to 2013, and was just below the number of similar events reported in 2012. Among the factors contributing to this decrease: - the number of events related to gamma radiography inspections for checking welds was halved, despite a nearly identical number of interventions; - the number of non-compliancies related to the access to or time spent in radiologically controlled areas is falling, although these non-compliancies still represent the largest number of reported events. The most notable trend compared to previous years concern worker dosimetry

Nuclear explosion and internal contamination; Explosion nucleaire et contamination interne

Energy Technology Data Exchange (ETDEWEB)

Aeberhardt, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1956-07-01

By the study of the conditions of internal contamination due to the radioactive mixture produced by a nuclear explosion, the parts played by the relative weights of the different elements and the mode of expression of the doses are considered. Only the knowledge of the weight composition of the contamination mixture and of its evolution as a function of time can provide the required basis for the study of its metabolism in the organism. The curves which give the composition of the fission product mixture - in number of nuclei - - as a function of time - have been established. These curves are applied to some practical examples, particularly relative to the nature of contamination, radiotoxicity of some elements and assessment of hazards. (author) [French] Etudiant les modalites de la contamination interne par les elements radioactifs apparus lors d'une explosion nucleaire, le role de la 'masse' et le mode d'expression des doses sont envisages. La connaissance de la composition en 'masse' du melange contaminant et de son evolution en fonction du temps peut seule apporter les bases necessaires a l'etude de son comportement dans l'organisme. Les courbes donnant la composition du melange de produits de fission - en nombre de noyaux - - en fonction du temps - ont ete etablies. Quelques applications pratiques, relatives en particulier a la nature de la contamination, a la radiotoxicite de certains elements et a l'evaluation de risque, sont envisagees a titre d'exemple. (auteur)

Applicability of ICRP principles for safety analysis of radioactive waste geological storage; Etude de l'applicabilite des principes de la CIPR a l'analyse de surete du stockage geologique des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Lombard, J; Hubert, P; Pages, P

1987-07-01

modalites de stockage) doit etre determine par un processus comparatif visant a selectionner le niveau conduisant au meilleur compromis entre es depenses de protection et les risques residuels. Ces recommandations, particulierement Ia seconde, s'ecartent des principes des analyses de surete suivis jusqu'a present en France et a l'etranger; cette etude envisage les avantages et inconvenients potentiels lies a l'introduction de ce second principe. Dans ce but on se base sur differentes analyses realisees au niveau international integrant partiellement au moms ces principes. II ressort de cet examen que ces principes sont applicables mais que leur mise en oeuvre necessite une reorientation de modeles d'evaluation en particulier pour s'affranchir d'hypotheses trop conservatrices. Cette mise en oeuvre necessite par ailleurs davantage d'informations que dans le cas d'une approche deterministe de Ia surete puisqu'il faut estimer les consequences et les probabilites de I'ensemble des evenements possibles et ce pour es diverses modalites de stockage que l'on se propose de comparer. L'integration d'evaluation de ce type est cependant plus riche d'enseignements et constitue de ce fait une aide a Ia decision qui peut etre feconde. On peut enfin souligner que cette approche permet un meilleur dialogue entre les differentes instances decisionnelles et plus generalement entre les acteurs du debat, dans Ia mesure ou elle apporte un langage de discussion commun. On notera d'ailleurs que ce souci de clarification s'exprime quelle que soit I'optique de surete adopte (deterministe ou probabiliste), comme en temoignent les interrogations sur le sens du 'scenario central' de I'etude KBS. Par ailleurs, ii semble que ces principes seront vraisemblablement suivis au plan international afin d'uniformiser en outre les modes de gestion de Ia radioprotection dans ses diff?rentes composantes. (author)

Order of 24 October 2011 related to diagnosis reference levels in radiology and nuclear medicine; Arrete du 24 octobre 2011 relatif aux niveaux de reference diagnostiques en radiologie et en medecine nucleaire

Energy Technology Data Exchange (ETDEWEB)

Grall, J.Y. [Ministere du travail, de l' emploi et de la sante, Direction generale de la sante, 14, avenue Duquesne, 75350 PARIS 07 SP (France)

2012-01-14

This order defines diagnosis reference levels for examinations exposing to the most common or irradiating ionizing radiations in the case of radiology and nuclear medicine. It also specifies the role of the person authorized to use nuclear medicine equipment, the role of the IRSN in collecting and analysing data. Doses are specified in appendix for different types of examinations

Analysis by the IRSN of the Japanese study of the biological impact of the Fukushima accident published in the Nature releases of the 9 August 2012

International Nuclear Information System (INIS)

2012-01-01

This note briefly analyses a Japanese investigation which addressed the biological impacts of the Fukushima nuclear accident on the pale grass blue butterfly (a rather common butterfly in this region), and highlighted physiological and genetic damages on several generations of this butterfly in the surroundings of the Fukushima Daiichi power station. The authors of this study aimed at assessing the causality relationship between the irradiation level and the physiological status of this butterfly. The IRSN considers this investigation as original and serious, but also that the assessment of radiological exposures is only made in terms of measured external dose rate whereas the contribution of internal contamination (related to ingestion of contaminated vegetal) is not taken into account

IRSN global process for leading a comprehensive fire safety analysis for nuclear installations

International Nuclear Information System (INIS)

Ormieres, Yannick; Lacoue, Jocelyne

2013-01-01

A fire safety analysis (FSA) is requested to justify the adequacy of fire protection measures set by the operator. A recent document written by IRSN outlines a global process for such a comprehensive fire safety analysis. Thanks to the French nuclear fire safety regulation evolutions, from prescriptive requirements to objective requirements, the proposed fire safety justification process focuses on compliance with performance criteria for fire protection measures. These performance criteria are related to the vulnerability of targets to effects of fire, and not only based upon radiological consequences out side the installation caused by a fire. In his FSA, the operator has to define the safety functions that should continue to ensure its mission even in the case of fire in order to be in compliance with nuclear safety objectives. Then, in order to maintain these safety functions, the operator has to justify the adequacy of fire protection measures, defined according to defence in depth principles. To reach the objective, the analysis process is based on the identification of targets to be protected in order to maintain safety functions, taken into account facility characteristics. These targets include structures, systems, components and personal important to safety. Facility characteristics include, for all operating conditions, potential ignition sources and fire protections systems. One of the key points of the fire analysis is the assessment of possible fire scenarios in the facility. Given the large number of possible fire scenarios, it is then necessary to evaluate 'reference fires' which are the worst case scenarios of all possible fire scenarios and which are used by the operator for the design of fire protection measures. (authors)

Post-Fukushima additional safety assessments: behaviour of French nuclear installations in case of extreme situations and relevance of propositions of improvement. Summary of the IRSN report Nr 679 which has been used as a reference for the permanent Group of experts for reactors and plants held on the 8, 9 and 10 November

International Nuclear Information System (INIS)

2011-01-01

This document summarizes the content of a report made by the IRSN and analysing the additional safety assessments performed and transmitted by operators in September 2011. It evokes the international context after the Fukushima-accident, addresses the analysis approach followed by the IRSN, discusses and comments the installation conditions, the robustness of installations with respect to high level risks and to those retained for their sizing, the behaviour of installations in the case of a total loss of cooling sources or of a long duration loss of energy supplies affecting several installations within a same site (case of EDF reactors, of the high flux reactor of the Laue Langevin Institute, CEA installations, Areva laboratories and plants), the capacity of operators to handle a crisis situation in such conditions, appeal to subcontracting

The Nuclear Safety Authority: statement and perspectives; L'Autorite de Surete Nucleaire: constats et perspectives en radiologie

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This Power Point presentation gives the distribution of exposure sources among different sectors and origins, the level of medical exposures in the USA in 1983 and 2006, an assessment of the evolution of patient exposure in the world, the number of scanners in some countries and the corresponding average dose per inhabitant, the importance of the use of a scanner in diagnosis examinations. It comments the increase of the average efficient dose per inhabitant in radiology, shows that a major part of it is due to scanners. Other data are presented regarding patient age and gender. The contributions of radiography and scanner are compared for several western countries. Then the author addresses several issues: the value of the actual dose, and the associated risks. He outlines how to control the observed dose increase

Analysis by the IRSN of the Tritium concentration measured by the ACRO in a seawater sampling from the Ecalgrain bay on the 17 October 2012

International Nuclear Information System (INIS)

2013-01-01

As the ACRO published a result of seawater analysis performed on a sample taken in the Ecalgrain bay at the vicinity of the La Hague plant (this analysis revealed a very high level of Tritium in seawater), this document reports and comments the results obtained by the nearest IRSN measurement station since 1997. The authors outline the complex influence of numerous factors (meteorological conditions, sea currents, tides, and so on). They present the results obtained by a computation code which has been developed to predict the dispersion of La Hague releases. They compare the levels thus computed and the results published by the ACRO, and state that important differences may exist between two relatively close sites due to meteorological and sea conditions

Synthesis of the IRSN report on the topic of water way answers to implement in case of accident with core meltdown occurring on operating pressurized water nuclear reactors

International Nuclear Information System (INIS)

2009-06-01

This report briefly discusses the efficiency of technical measures adopted for the implementation of water ways as answers to an accident with core meltdown in operating pressurized water nuclear reactors. While mentioning the importance of the hydro-geological characteristics of the various sites, the IRSN asks EDF to plan and implement means to prevent any rejection through water ways for some of these sites, to investigate the possibility of building a geotechnical enclosure, to define a storing-control-treatment-rejection chain which would guarantee an efficient management of the water to be pumped, to study retention phenomena for strontium and caesium isotopes in sands and gravels

Installation and testing of the 150keV high current pulsed accelerator installed at the Service de Physique Nucleaire in Bruyeres-le-Chatel

International Nuclear Information System (INIS)

Dandine, Andre; Sinopoli, Louis.

1976-01-01

A 150keV accelerator installed at the Service de Physique Nucleaires in Bruyeres-le-Chatel is described which has been equipped especially for the preparation of the nuclear experiments carried out with the EN 7MV tandem Van de Graaff, and for the completion of totally independent experiments. Details of the ion optical arrangement and the pulsing system are presented; unanalysed beams of intensity 1 to 2mA are obtained accelerating either protons or deuterons. In the pulsed mode, at 1.25 MHz or 2.5MHz, the average intensity of the analysed beam is 8 to 10μA and the pulse length is 2ns [fr

General problems arising from the analogical resolution of the kinetic equations of nuclear reactors (1961); Problemes generaux poses par la resolution analogique des equations cinetiques des reacteurs nucleaires (1961)

Energy Technology Data Exchange (ETDEWEB)

Caillet, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1961-07-01

The author reviews precisely the analogical techniques used for the resolution of the kinetic equations of nuclear reactors. Prior to this, he recalls the reasons which oblige physicians and engineers, even today, to use electronic machines in this domain. The author then considers the technological problems posed by the range of values which the various nuclear parameters adopt. In each case, he shows that a compromise is possible allowing an optimum precision. He compares the results to those obtained by arithmetic calculation and uses the examples chosen in a critical analysis of the present possibilities of the two methods of calculation. (author) [French] L'auteur cherche a faire un point aussi exact que possible des techniques analogiques utilisees pour resoudre les equations cinetiques des reacteurs nucleaires. Il rappelle auparavant les raisons pour lesquelles physiciens et ingenieurs sont obliges, encore aujourd'hui, de faire appel aux machines electroniques dans ce domaine. Puis il etudie les problemes technologiques que souleve le champ des valeurs prises par les differents parametres nucleaires. Dans chacun des cas, il montre l'existence d'un compromis qui permet d'atteindre une precision optimum. Il compare les resultats obtenus a ceux provenant de calculateurs arithmetiques et profite des exemples choisis pour faire une analyse critique des possibilites actuelles offertes par les deux modes de calcul. (auteur)

France's nuclear power programme; Le programme nucleaire francais

Energy Technology Data Exchange (ETDEWEB)

Cabanius, J [Electricite de France (EDF), 75 - Paris (France); Horowitz, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-07-01

-increasing importance, by using the country's resources of natural uranium, and later plutonium, to the best ends. (authors) [French] Les perspectives d'evolution de la consommation d'energie electrique francaise confirment l'aggravation du deficit des ressources energetiques metropolitaines. Les centrales nucleaires doivent permettre de diminuer ce deficit si un certain nombre d'incertitudes actuelles sont levees. Le premier programme presente par MM AILLERET et TARANGER a la Conference de Geneve en 1955 visait la mise en service pour 1965 de 850 MWe; il a ete consacre au developpement de la filiere uranium naturel - graphite - gaz et s'acheve avec la realisation d'EDF 3, premiere unite capable de 500 MWe engagee dans le monde. Avant de passer du stade des prototypes a celui des duplications, ELECTRICITE DE FRANCE a decide, en accord avec le COMMISSARIAT A L'ENERGIE ATOMIQUE, la realisation d'EDF 4 qui, en reprenant la partie reacteur d'EDF 3 ainsi que l'appareil de chargement et de dechargement, l'ensemble de controle et divers materiels, apporte une innovation importante en incorporant les echangeurs et les soufflantes a l'interieur du caisson en beton precontraint contenant le coeur. En meme temps, les etudes se poursuivent dans cette meme filiere et laissent entrevoir les possibilites d'utiliser un nouvel element combustible annulaire dont l'emploi ameliorerait notablement les performances d'EDF 5. Dans la filiere eau lourde, la realisation d'EL 4 a Brennilis par le COMMISSARIAT A L'ENERGIE ATOMIQUE et ELECTRICITE DE FRANCE se poursuit. Les etudes d'un reacteur de 500 MWe de cette filiere ont deja commence. Dans la filiere a eau pressurisee, la centrale de CHOOZ est realisee en association par ELECTRICITE DE FRANCE et les Producteurs Belges. Enfin, le COMMISSARIAT A L'ENERGIE ATOMIQUE poursuit a Cadarache la realisation du surgenerateur 'Rapsodie' et les etudes d'un reacteur de puissance plus important. Ainsi, les connaissances techniques et economiques acquises dans ces diverses

Opinion of the IRSN on serviceability of the 900 MWe reactor vessel - Answers to demands of the Nuclear Permanent Department of December 2005 - Mechanical aspect

International Nuclear Information System (INIS)

2010-05-01

As three demands had been made to EDF in December 2005 regarding the serviceability and more particularly the mechanical behaviour of the 900 MWe reactor vessels, this report discusses the evolution brought to models and proposed by EDF to correct the defect plasticity and take residual stresses into account. This discussion notably concerns the defect height and length range, and the admissible residual stress, but also the use of safety coefficients, transient application, fluence and the brittle-ductile transition temperature. This report from the French Nuclear Safety and Radioprotection Institute (IRSN) outlines the failure risks associated to the vessel in some specific nuclear power stations. Recommendations are made regarding the residual stress amplitude, the risk of fracture by cleavage, and actions to correct fracture risk margins on vessels which do not comply with regulatory criteria

Dosimeter calibration facilities and methods at the Radiation Measurement Laboratory of the Centre d'etudes nucleaires, Grenoble

International Nuclear Information System (INIS)

Choudens, H. de; Herbaut, Y.; Haddad, A.; Giroux, J.; Rouillon, J.; CEA Centre d'Etudes Nucleaires de Grenoble, 38

1975-01-01

At the Centre d'etudes nucleaires, Grenoble, the Radiation Measurement Laboratory, which forms part of the Environmental Protection and Research Department, serves the entire Centre for purposes of dosimetry and the calibration of dose meters. The needs of radiation protection are such that one must have facilities for checking periodically the calibration of radiation-monitoring instruments and developing special dosimetry techniques. It was thought a good idea to arrange for the dosimetry and radiation protection team to assist other groups working at the Centre - in particular, the staff of the biology and radiobiology laboratories - and also bodies outside the framework of the French Commissariat a l'energie atomique. Thus, technical collaboration has been established with, for example, Grenoble's Centre hospitalier universitaire (university clinic), which makes use of the facilities and skills available at the Radiation Measurement Laboratory for solving special dosimetry problems. With the Laboratory's facilities it is possible to calibrate dose meters for gamma, beta and neutron measurements

History of nuclear power plants safety in France (1945-2000) - Engineer techniques, expert evaluation, topical issue

International Nuclear Information System (INIS)

Foasso, Cyrille

2003-01-01

This doctoral dissertation relates the history of the mastery of risks in civil nuclear plants in France. Since 1960, it's known as the 'surete nucleaire'. Over a fifty-year period separating the discovery or the atomic fission and its industrial application on a large scale this PhD shows which technical means were used over the years by engineers to handle this risk which is said to be huge. It also studies the various processes in expert evaluation and in decision making elaborated to evaluate if the risk was acceptable or not. Beyond the conflicts between nuclear advocates and opponents, this thesis shows how ever among nuclear engineer the growing distinction between roles (promoters, experts and controlling authorities) and the various jobs (designers, builders and plant operators) triggered different estimations as far as the methods to obtain a satisfactory safety. Thanks to the progress of knowledge through research programs, thanks to the lessons drawn from the functioning or dysfunction of nuclear plants, thanks to the reinforcement of regulations (which more or less reflects the public's opinion concerning this industry) the safety has progressively improved. Thus, this historical study is multiple: a technical history of technology, a history of scientific, industrial and administrative organization, a social history and finally an international and comparative history since the nuclear energy history quickly developed beyond national boundaries. (author) [fr

In situ and laboratory measurements of very low permeability in the Tournemine argilites (Aveyron). Comparison of methodologies and scale effect

International Nuclear Information System (INIS)

Boisson, J.Y.; Cabrera, J.

1998-01-01

At the request of the Institut de Protection et de Surete Nucleaire (IPSN - Institute of Nuclear Safety and Protection), ANTEA visited the Tournemire site (Aveyron) to carry out an hydraulic characterization of the 200 m-thick Toarcian and Domerian formations accessible by tunnel. Permeability measurements were made using the borehole pulse-test method either in the global hole or perpendicular to more permeable fractured zones. The tests yielded an approximate value for the hydraulic head and an order of magnitude for the permeability at 1 to 10 metre scale (10 -11 to 10 -13 m/s). A borehole was then equipped for a long-duration (6 months) measurement of the hydraulic head in the rock body. Laboratory measurements were made on 4 cm-diameter core samples taken from different boreholes. The tests, carried out under triaxial stress, required preliminary saturation-consolidation of the test samples. Through applying steady-state flow or hydraulic pulse, it was possible to measure a permeability in order of 10 -14 m/s for the matrix of the clayey material. The difference between laboratory and in situ values is explained by the presence of fractures in the rock body. Moreover, it seems that the hydraulic conditions of measurement in the field around the hole could have an influence on the final result. (authors)

Safety and Radiation Protection at Nuclear Power Plants in France in 2015. IRSN's position - Mission Report 2016

International Nuclear Information System (INIS)

2017-01-01

IRSN publishes its report on the operation, in 2015, of the 58 nuclear reactors of EDF in France. It is based on an overall review of significant events, which brings out global lessons as well as trends in evolution and identifies topics requiring special attention. Safety: a decrease in the number of events but still a significant number of non-compliance with the technical operating specifications 604 significant safety-related events in 2015: the decline observed since 2013 in the number of events continued. This decrease is 7% compared to 2014 and 18% compared to 2012. Also, for the third consecutive year, no event was rated at or above 2. In 2015, half of the safety-related events originated from non-compliance with technical specifications. In addition, the quality of maintenance activities was not at the expected level, due in particular to a risk analysis that was often incomplete. Improving the control of these activities remains an important objective for EDF. Finally, the inspections carried out in 2015 showed a habituation to deviation which requires a rigorous response from EDF to keep the plants in compliance. Radiation protection: a decrease in the number of events but three events of workers' skin contamination After a first decline of 8% in 2014, the number of significant events concerning radiation protection of workers decreased by 5% in 2015. However, in 2015, three cases of skin contamination of plant workers led to exceedances of the regulatory limits for skin-equivalent dose. They were responsible for the three events described as incidents on the INES scale: an event classified at level 2 and two events classified at level 1. The setting up by EDF of organizational measures, particularly during the phases of undressing, could reduce the risk of skin contamination. Moreover, the number of events linked to failures in the application of basic rules of radiation protection has increased strongly over the last two years. This is

Status of safety at Areva group facilities. 2006 annual report; Etat de surete des installations nucleaires. Rapport annuel 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

This report presents a snapshot of nuclear safety and radiation protection conditions in the AREVA group's nuclear installations in France and abroad, as well as of radiation protection aspects in service activities, as identified over the course of the annual inspections and analyses program carried out by the General Inspectorate in 2006. This report is presented to the AREVA Supervisory Board, communicated to the labor representation bodies concerned, and made public. In light of the inspections, appraisals and coordination missions it has performed, the General Inspectorate considers that the nuclear safety level of the AREVA group's nuclear installations is satisfactory. It particularly noted positive changes on numerous sites and efforts in the field of continuous improvement that have helped to strengthen nuclear safety. This has been possible through the full involvement of management teams, an improvement effort initiated by upper management, actions to increase personnel awareness of nuclear safety culture, and supervisors' heightened presence around operators. However, the occurrence of certain events in facilities has led us to question the nuclear safety repercussions that the changes to activities or organization on some sites have had. In these times of change, drifts in nuclear safety culture have been identified. The General Inspectorate considers that a preliminary analysis of the human and organizational factors of these changes, sized to match the impact the change has on nuclear safety, should be made to ensure that a guaranteed level of nuclear safety is maintained (allowance for changes to references, availability of the necessary skills, resources of the operating and support structures, etc.). Preparations should also be made to monitor the changes and spot any telltale signs of drift in the application phase. Managers should be extra vigilant and the occurrence of any drift should be systematically dealt with ahead of implementing corrective actions. The level 2 INES event that occurred in the ATPu facility in Cadarache was therefore considered particularly significant by the General Inspectorate. The activities being carried out within the entity at the time of the event were singular and the identified causes numerous, but were fundamentally the product of human and organizational factors. The lessons learnt from this event need to be shared with all other entities. Like many other less significant events that took place in 2005 and 2006, this event led the General Inspectorate to focus particularly on criticality risk control on sites where fissile material is used. It considers that internal criticality control actions must be carried out on these sites in order to make sure the required provisions are known and applied by all operators. In-service fire risk control hinges on - among other things - the application of fire prevention, protection and preparation rules, which must be a constant concern of site managers. The General Inspectorate noted numerous positive developments on most sites in this field in 2006, as well as the production entities' full cooperation with the risk analysis services and fire-fighting services. On most sites, fire risk control is organized clearly and in a structured manner.

Economic consequences of the Swiss 'Sortir du nucleaire' and 'Moratoire-plus' popular initiatives - Analysis using a balanced model

International Nuclear Information System (INIS)

Mueller, A.; Wickart, M.; Van Nieuwkoop, R.

2001-01-01

This article is a short version of the ENET number 210359. This report for the Swiss Federal Office of Energy (SFOE) presents the results of a study made to assess the economic consequences of two models for the opting out of nuclear energy in Switzerland, as proposed in two popular initiatives. The 'Sortir du nucleaire' (electricity without atomic power) initiative calls for the shutting down of the existing nuclear power stations and the 'Moratoire-plus' initiative calls for a stop on the building of new atomic power stations for 10 years. The method used for assessing the costs and benefits resulting if the initiatives were accepted in a public vote is described. Basic assumptions made on further factors concerning the electricity and energy markets are discussed. Results of analyses made for various scenarios with respect to CO 2 emissions are presented and include discussions on risk costs, effects on employment and welfare aspects

Possibilities and limitations of analogue methods for studying the dynamics of nuclear power stations; Possibilites et limitations du calcul analogique pour les etudes dynamiques de centrales nucleaires

Energy Technology Data Exchange (ETDEWEB)

Caillet, C; Deat, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

1. Introduction: the present paper is devoted to analog simulation of problems related to nuclear reactors other than the simulation of the kinetic equations which is well known. 2. Thermodynamic problems: various problems relative to temperature evolution in a reactor, in a pipe, in an exchanger, in a turbine, are studied, and simulation techniques used by earlier authors are critically reviewed. 3. Pipe simulators: it is shown that this problem can be solved by the use of specialized simulators which will be described and analysed. 4. Rotating machine simulators: the particular aspect of rotating machine calculations introducing frequent use of diagrams is emphasized. A simulator requiring both digital and analogue methods is described. 5. The study of a nuclear power station: as an example it is proposed to discuss problems a rising in connection with the preceding elements (a, b, c, d) when simulating the behaviour of large nuclear plants. The part played by ordinary computing elements for the simulation of the different servomechanism transfer functions is considered and process of regulation is outlined. 6. Conclusion: the necessity of the use of high quality simulators and computers is underlined and the accuracy of the solutions is discussed. (author)Fren. [French] 1. Cinetique des reacteurs: la simulation des equations cinetiques d'un reacteur nucleaire ne pose desormais plus de probleme. II est donc possible de faire le point des differentes applications de la technique analogique dans ce domaine. 2. Les problemes thermodynamiques: on discute les differents problemes poses par l'evolution des temperatures dans un reacteur, dans une tuyauterie, dans un echangeur, dans une turbine, et on passe en revue les techniques de simulation proposees jusqu'a ce jour. 3s simulateurs de tuyauteries: on montre comment les differents problemes poses ci-dessus peuvent etre resolus, pour une classe tres vaste de reacteurs par l'emploi de simulateurs speciaux que l

Radiolytic oxidation of iodine in the containment at high temperature and dose rate

International Nuclear Information System (INIS)

Guilbert, S.; Bosland, L.; Jacquemain, D.; Clement, B.; Andreo, F.; Ducros, G.; Dickinson, S.; Herranz, L.; Ball, J.

2007-01-01

Iodine Chemistry is one of the areas of top interest in the field of nuclear power plants (NPP) severe accidents studies. The strong radiological impact of iodine on man health and environment, mostly through its isotope I-131, has made it a key point to get an accurate prediction of the potential iodine release from the NPP containment to the environment in the low probable event of an accident leading to core melt. Released from the fuel as a gaseous form, iodine enters the containment in gaseous or particulate form and undergoes deposition processes that eventually take it to the containment surfaces and sump. Once in the sump, iodine, when present as soluble compounds, gets dissolved as non volatile iodide (I-). Nonetheless, in the presence of radiation and particularly in acidic sumps, iodine can be oxidized to volatile forms such as molecular iodine (I 2 ) and can escape from the sump to the containment atmosphere (sump radiolysis process), thus increasing its potential contribution to the iodine source term. Iodine sump radiolysis has been extensively studied experimentally in the past decades. Experiments have revealed that parameters such as pH, temperature and total iodine concentration have a large impact on iodine volatility. However, experimental data at elevated temperatures (> 80 O C) and elevated dose rates (> 1 kGy.h -1 ) anticipated in containment during a postulated severe accident are too scarce to provide for these relevant conditions an accurate determination of the volatile iodine fractions. Furthermore, some data were obtained from post-irradiation analysis and iodine concentration may be underestimated at the time of measurements compared with that during irradiation, due to post-irradiation reactions. To complete the existing database, the EPICUR program was launched by IRSN (Institut de Radioprotection et de Surete Nucleaire) and experiments have been performed in the frame of the International Source Term Program (ISTP) to provide on

Modelling of nonhomogeneous atmosphere in NPP containment using lumped-parameter model based on CFD calculations

International Nuclear Information System (INIS)

Kljenak, I.; Mavko, B.; Babic, M.

2005-01-01

Full text of publication follows: The modelling and simulation of atmosphere mixing and stratification in nuclear power plant containments is a topic, which is currently being intensely investigated. With the increase of computer power, it has now become possible to model these phenomena with a local instantaneous description, using so-called Computational Fluid Dynamics (CFD) codes. However, calculations with these codes still take relatively long times. An alternative faster approach, which is also being applied, is to model nonhomogeneous atmosphere with lumped-parameter codes by dividing larger control volumes into smaller volumes, in which conditions are modelled as homogeneous. The flow between smaller volumes is modelled using one-dimensional approaches, which includes the prescription of flow loss coefficients. However, some authors have questioned this approach, as it appears that atmosphere stratification may sometimes be well simulated only by adjusting flow loss coefficients to adequate 'artificial' values that are case-dependent. To start the resolution of this issue, a modelling of nonhomogeneous atmosphere with a lumped-parameter code is proposed, where the subdivision of a large volume into smaller volumes is based on results of CFD simulations. The basic idea is to use the results of a CFD simulation to define regions, in which the flow velocities have roughly the same direction. These regions are then modelled as control volumes in a lumped-parameter model. In the proposed work, this procedure was applied to a simulation of an experiment of atmosphere mixing and stratification, which was performed in the TOSQAN facility. The facility is located at the Institut de Radioprotection et de Surete Nucleaire (IRSN) in Saclay (France) and consists of a cylindrical vessel (volume: 7 m3), in which gases are injected. In the experiment, which was also proposed for the OECD/NEA International Standard Problem No.47, air was initially present in the vessel, and

Statistical treatment of data. Application to nuclear electronics; Traitement des informations en regime statistique. Applications a l'electronique nucleaire

Energy Technology Data Exchange (ETDEWEB)

Sicard, F [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

In this report the data of probability calculations are applied to the analyses of counting losses in experiments on chance events encountered in nuclear physics. The distribution of time intervals according to Poisson's law is studied and various applications of this are given: calculation of counting losses on a scale preceded by a fast de-multiplying circuit, decrease of the counting rate on the multichannel selectors, recording of statistical distribution phenomena on magnetic bands. (author) [French] Ce rapport applique les donnees du calcul des probabilites a l'analyse des pertes de comptage dans les experiences sur des evenements aleatoires rencontres en physique nucleaire. La distribution des intervalles de temps suivant une loi de Poisson est etudiee et differentes applications en sont donnees: calcul des pertes de comptage sur une echelle precedee d'un circuit de demultiplication rapide, diminution du taux de comptage sur les selecteurs multicanaux, enregistrement de phenomenes a distribution statistique sur bandes magnetiques. (auteur)

Situation of Fukushima Dai-ichi power plant in Japan - May 25, 2011 status; Situation de la centrale nucleaire de Fukushima Dai-ichi au Japon - Point de situation du 25 mai 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on May 25, 2011 by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the cores of reactors 1, 2 and 3 of the Fukushima I site (Dai-ichi) and of the different spent fuel pools is briefly presented as well as the actions in progress for the control of environmental radioactive releases and for the progressive recovery of the facilities control. (J.S.)

Reperes, the information magazine of the Institute for Radiation Protection and Nuclear Safety - IRSN, No. 12 - January 2012, Special issue Fukushima - First lessons from the accident; Reperes, le magazine d'information de l'Institut de radioprotection et de surete nucleaire - IRSN, No. 12 - janvier 2012, Special Fukushima - Premieres lecons de l'accident

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-01-15

A first set of articles addresses the nuclear crisis in Japan (description of the accident, information mission sent by France, and support actions undertaken by France in Japan in the fields of education, civilian security, culture, sailing, media, dosimeters, robotics). A second set discusses lessons learned in terms of nuclear safety (complementary safety assessments, stress test in Gravelines), radiological consequences (impact on Japanese population, the Symbiose software, the Teleray network), crisis management, and research

Piles used for the nuclear control of materials; Empilements pour le controle nucleaire des materiaux

Energy Technology Data Exchange (ETDEWEB)

Raievski, V; Sautiez, B; Bailly du Bois, B; Tretiakoff, O; Thome, P; Vidal, R; Koppel Martelly, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

The devices which make it possible to check on the nuclear qualities of the materials used in reactor construction are described. These verifications bear on substantial masses of materials, following the last stage of their machining. The components found in all these are a graphite pile into which the material to be investigated is inserted, a source of neutrons made up of an Ra-Be system, and a proportional BF{sub 3} counter. The devices described here bear on checking graphite, beryllium oxide and uranium absorption, as well as on a verification of the {sup 235}U content of fuel elements. (author)Fren. [French] On decrit des dispositifs permettant de controler les qualites nucleaires de materiaux utilises dans la construction des piles. Ce controle s'effectue sur des masses importantes de materiaux apres la phase finale d'usinage. Ces dispositifs ont en commun un empilement de graphite recevant le materiau a etudier, une source de neutrons de Ra-Be et un compteur proportionnel a BF{sub 3}. Les dispositifs decrits concernent le controle de l'absorption du graphite, de la glucine et de l'uranium, ainsi que le controle de la teneur en {sup 235}U des elements de combustion. (auteur)

Situation of Fukushima Dai-ichi power plant in Japan - June 1, 2011 status; Situation de la centrale nucleaire de Fukushima Dai-ichi au Japon - Point de situation du 1er juin 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on June 1, 2011 by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the cores of reactors 1, 2 and 3 of the Fukushima I site (Dai-ichi) and of the different spent fuel pools is briefly presented as well as the actions in progress for the control of environmental radioactive releases and for the progressive recovery of the facilities control. (J.S.)

Status of radioactivity monitoring in French Polynesia in 2012. Synthesis of IRSN's monitoring network results

International Nuclear Information System (INIS)

Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; De Vismes, P.A.

2013-01-01

Exercised in Polynesia since 1962, the radiological monitoring of the French environment, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagos, and consists of taking regular samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, from the lagoon environment and from the terrestrial environment. Almost all the samples are measured at the Laboratory for the Study and Monitoring of the Environment (LESE) IRSN, based in Vairao on the island of Tahiti. During the year 2012, were stable and typical of the regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates primarily to the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-sieverts per year). This value corresponds to less than 0,5 % of exposure due to natural radioactivity in Polynesia (approximately 1 000 μSv.y -1 ). Enhanced radiological monitoring of the environment set up in the wake of the Fukushima disaster, continued in 2012 in the marine field. The measurements carried out throughout the year confirm the lack of impact of the contamination of Japanese marine area in Polynesian waters. Samples of pelagic fish (tuna, swordfish, dolphin fish, wahoo...) were made in the vicinity of five Polynesian archipelagos: no increase of 137 Cs compared to previous years was observed and 134 Cs was never detected. (authors) [fr

The dangers of irradiate uranium in nuclear reactors; Les dangers de l'uranium irradie dans les reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Jammet, H; Joffre, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

The danger of the uranium cans sur-activated by the use in the nuclear reactors is triple: - Irradiation from afar, during manipulations of the cans. - Contamination of air when decladding. - Contamination of air by fire of uranium in a reactor in function The first two dangers are usual and can be treated thanks to the rules of security in use in the atomic industry. The third has an accidental character and claimed for the use of special and exceptional rules, overflowing the industrial setting, to reach the surrounding populations. (authors) [French] Le danger des cartouches d'uranium suractive par utilisation dans les reacteurs nucleaires est triple: - Irradiation a distance, lors des manipulations des cartouches. - Contamination de l'air au moment de leur degainage. - Contamination de l'air par incendie d'uranium dans un reacteur en fonctionnement. Les deux premiers dangers sont habituels et peuvent etre traites grace aux regles de securite en usage dans l'industrie atomique. Le troisieme revet un caractere accidentel et reclame l'emploi de regles speciales et exceptionnelles, debordant le cadre industriel, pour atteindre celui des populations environnantes. (auteurs)

Ethical aspects of radiological risks management

International Nuclear Information System (INIS)

Surgier, A.

1996-01-01

The complexity of the decisions to be taken by the radiation protection and safety authorities in the nuclear, medical, and industrial fields, as well as the importance of the risks involved, require consideration of the confidence that the public can have in the procedures and institutions associated with these decisions. The Technical Support Organisations that advise these authorities play an essential role in risk evaluation. They participate both in defining the scientific bases of the regulations and analysing the authorization request from the operators. The credibility of these bodies implies a clear separation between their function and that of the regulatory authorities and the operators. It also requires a guarantee of competence which is based on a high level research program and contacts with other similar organisations. The quality of the work carried out by the Technical Support Organisations must be regularly evaluated. One of the most important of the other conditions for ensuring the effectiveness of the expertise is its integration in a well defined decision-making procedure. The author has based this article on his experience as director of radiation protection in the IPSN (Institut de Protection et de Surete Nucleaire), an organisation formed in 1976, with a staff of 1,200 whose functions are to carry out research and provide expertise in health physics radioecology and nuclear safety. To reinforce its operating autonomy and authority, the status of the IPSN was thoroughly revised as strengthened in 1990. (Author)

Survey of International Rules and Practices Regarding Delineation of and Access to Regulated Areas for Radiation Protection - Final report

International Nuclear Information System (INIS)

Schieber, C.; Crouail, P.; Beltrami, L.-A.; Reaud, C.; Lehtinen, Maaret; Stritt, Nicolas; Thomas, Gareth

2013-06-01

European requirements for radiological protection, especially work on transposing the new EURATOM Directive on the basic radiological protection standards, are currently being revised. The Direction generale du travail (DGT - General Directorate of Labour) and the Autorite de Surete Nucleaire (ASN - Nuclear Safety Authority) therefore commissioned the Radiological Protection Standing Groups of experts (GPRAD and GPMED)1 to engage in a forward-looking debate on the delimitation of and access to regulated areas, within an ad hoc working group (called hereafter 'Classification of Area WG'). To fuel its debates, the 'Classification of Area WG' sought elements on international regulations and practices focusing on problem exposure situations in various areas of activity (nuclear, industrial, research, medical, transport and natural boosted). CEPN was entrusted with this study. This report presents a summary of rules applicable in seven countries in terms of delimitation of and access to regulated radiological protection areas. The countries are: Belgium, Spain, United States, Finland, United Kingdom, Sweden and Switzerland. Detailed sheets for each country can be found in the Annex. Based on these summaries, three countries have been selected to apply their rules and practices in force to a dozen or so particular cases put together by the 'Classification of Area WG' that are representative of exposure situations. The three countries are Finland, United Kingdom and Switzerland. The case studies applied to each country are presented in the second part of this report

Visual observations of a degraded bundle of irradiated fuel: the Phebus FPT1 test

International Nuclear Information System (INIS)

Barrachin, M.; Bottomley, P.D.

1999-01-01

The international Phebus-FP (Fission Product) project is managed by the Institut de Protection et Surete Nucleaire in collaboration with Electricite de France (EDF), the European Commission (EC), the USNRC (USA), COG (Canada), NUPEC and JAERI (Japan), KAERI (South Korea), PSI and HSK (Switzerland). It is designed to measure the source-term and to study the degradation of irradiated UO 2 fuel in conditions typical of a severe loss of coolant accident in a pressurised water reactor (PWR). In the first test (FPT0), performed in December '93, a bundle of 20 fresh fuel rods and a central Ag-In-Cd control rod underwent a short 15-day irradiation to generate fission products before testing in the Phebus reactor in Cadarache. The second test (FPT1) was performed in July '96, in the same conditions and geometry, but using irradiated fuel (-23 GWd/tU). In the FPT1 test, the bundle was heated to an estimated 3000 K over a period of 30 minutes in order to induce a substantial liquefaction of the bundle. After the test, the bundle was embedded in epoxy and cut at different levels to investigate the mechanisms of the core degradation. This paper reports the visual observations of the degraded FPT1 bundle, very preliminary interpretations about the scenario of degradation and a comparison between the behaviour of the fuel in the FPT0 and FPT1 tests. (author)

Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.

Is it possible to recycle nuclear wastes? Costs, risks and stakes of the plutonium industry; Peut-on recycler les dechets nucleaires? Couts, risques et enjeux de l'industrie du plutonium

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on the chain reaction from uranium to plutonium, the difference between reprocessing (which does not reduce waste volumes but multiply waste types) and recycling, the high risks associated with plutonium transport, La Hague as the most dangerous nuclear site in France, reprocessing as the alibi for the French nuclear industry, Areva as an expert in propaganda, reprocessing as an absurd world strategy, plutonium as a fuel for proliferation, the myth of unlimited energy with the breeder reactors, and so on

Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The project of building of he EPR reactor at Flamanville (Manche, France) has been submitted to the public debate. This document includes a presentation of the project and of the rules of the public debate, a synthesis of the file made by the prime contractor (EDF), a synthesis of the collective book of national actors concerned by the project (a group of associations for environment protection, Areva company, the ministries of economy and ecology, Global Chance, association of pro-nuclear ecologists (AEPN), 'Sortir du Nucleaire' (out-of nuclear) network, group of scientists for the information about nuclear (GSIEN), association for the promotion of the Flamanville site (Proflam), French nuclear energy society (SFEN) in association with 'Sauvons le Climat' (let's save climate), regional collective association 'EPR non merci, ni ailleurs, ni ici' (EPR, no thanks, neither elsewhere, nor here), NegaWatt), and 5 detailed books of actors: ACRO (association for the control of radioactivity in Western France), CFDT and CGT syndicates, the economic and social council of Basse Normandie region, and Proflam. (J.S.)

Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The project of building of he EPR reactor at Flamanville (Manche, France) has been submitted to the public debate. This document includes a presentation of the project and of the rules of the public debate, a synthesis of the file made by the prime contractor (EDF), a synthesis of the collective book of national actors concerned by the project (a group of associations for environment protection, Areva company, the ministries of economy and ecology, Global Chance, association of pro-nuclear ecologists (AEPN), 'Sortir du Nucleaire' (out-of nuclear) network, group of scientists for the information about nuclear (GSIEN), association for the promotion of the Flamanville site (Proflam), French nuclear energy society (SFEN) in association with 'Sauvons le Climat' (let's save climate), regional collective association 'EPR non merci, ni ailleurs, ni ici' (EPR, no thanks, neither elsewhere, nor here), NegaWatt), and 5 detailed books of actors: ACRO (association for the control of radioactivity in Western France), CFDT and CGT syndicates, the economic and social council of Basse Normandie region, and Proflam. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 13, 2011, 7:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011 (13 mars 2011 - Point a 7h)

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 13, 2011, at 7:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2 and 3 of the Fukushima I site is briefly presented with the progress of the accident management actions. (J.S.)

Prevention of the causes and consequences of a criticality accident - measures adopted in France; Prevention des causes et des consequences d'un accident de criticite - solutions adoptees en France

Energy Technology Data Exchange (ETDEWEB)

Fruchard, Y.; Lavie, J.M

1966-07-01

The question of safety in regard to criticality accident risks has two aspects: prevention of the cause and limitation of the consequences. These two aspects are closely connected. The effort devoted to prevention of the causes depends on the seriousness of the possible human psychologic and economic consequences of the accident. The criticality accidents which have occurred in the nuclear industry, though few in number, do reveal the imperfect nature of the techniques adopted to prevent the causes, and also constitute the only available realistic basis for evaluating the consequences and developing measures to limit them. The authors give a analysis of the known causes and consequences of past criticality accidents and on this basis make a number of comments concerning: the validity of traditional safety criteria, the probability of accidents for different types of operations, characteristic accidents which can serve as models, and the extent of possible radiological consequences. The measures adopted in France to limit the consequences of a possible criticality accident under the headings: location, design and lay-out of the installations, accident detection, and dosimetry for the exposed personnel, are briefly described after a short account of the criteria used in deciding on them. (author) [French] La surete relative aux risques d'accidents de criticite presente deux aspects: la prevention des causes et les parades aux consequences. Ces deux aspects sont tres lies. L'effort consenti a la prevention des causes decoule de l'importance des consequences humaines economiques et psychologiques possibles d'un eventuel accident. Les accidents de criticite survenus dans l'industrie nucleaire, malgre leur rarete, d'une part devoilent les imperfections des techniques de prevention des causes, d'autre part constituent la seule base realiste disponible d'evaluation des consequences et de mise au point des parades a ces consequences

Prevention of the causes and consequences of a criticality accident - measures adopted in France; Prevention des causes et des consequences d'un accident de criticite - solutions adoptees en France

Energy Technology Data Exchange (ETDEWEB)

Fruchard, Y; Lavie, J M

1966-07-01

The question of safety in regard to criticality accident risks has two aspects: prevention of the cause and limitation of the consequences. These two aspects are closely connected. The effort devoted to prevention of the causes depends on the seriousness of the possible human psychologic and economic consequences of the accident. The criticality accidents which have occurred in the nuclear industry, though few in number, do reveal the imperfect nature of the techniques adopted to prevent the causes, and also constitute the only available realistic basis for evaluating the consequences and developing measures to limit them. The authors give a analysis of the known causes and consequences of past criticality accidents and on this basis make a number of comments concerning: the validity of traditional safety criteria, the probability of accidents for different types of operations, characteristic accidents which can serve as models, and the extent of possible radiological consequences. The measures adopted in France to limit the consequences of a possible criticality accident under the headings: location, design and lay-out of the installations, accident detection, and dosimetry for the exposed personnel, are briefly described after a short account of the criteria used in deciding on them. (author) [French] La surete relative aux risques d'accidents de criticite presente deux aspects: la prevention des causes et les parades aux consequences. Ces deux aspects sont tres lies. L'effort consenti a la prevention des causes decoule de l'importance des consequences humaines economiques et psychologiques possibles d'un eventuel accident. Les accidents de criticite survenus dans l'industrie nucleaire, malgre leur rarete, d'une part devoilent les imperfections des techniques de prevention des causes, d'autre part constituent la seule base realiste disponible d'evaluation des consequences et de mise au point des parades a ces consequences. Les auteurs presentent une analyse des

Nuclear purity and the production of uranium (1962); La purete nucleaire et la fabrication de l'uranium (1962)

Energy Technology Data Exchange (ETDEWEB)

Verte, P [Commissariat a l' Energie Atomique, Centre du Bouchet, Saclay (France). Centre d' Etudes Nucleaires

1962-07-01

When the production of 'nuclear grade' uranium is dealt with, it is difficult, the author of this study points out, to separate its chemical, technical, and economical bearings. While recalling the evolution of chemical processes in various countries and describing the technic of uranium manufacture in the plant of the French 'Commissariat a l'Energie Atomique' at Le Bouchet, the author outlines the effect of economical contingencies on the problems the chemists and engineer are faced with. The question of cost price is also considered here with particular attention. (author) [French] Lorsqu'il s'agit de la production d'uranium de 'qualite nucleaire', il est difficile, souligne l'auteur de cette etude, de separer les aspects chimique, technique et economique. Aussi, en retracant l'evolution des procedes chimiques dans divers pays et decrivant les techniques de fabrication de l'uranium a l'usine du Bouchet du Commissariat a l'Energie Atomique, l'auteur ne manque-t-il pas de rappeler les incidences de la conjoncture economique sur les problemes posees au chimiste et a l'ingenieur. La question du prix de revient, egalement, est traitee ici avec une attention particuliere. (auteur)

Nuclear Materials Management and its Relationship to Nuclear Safety and Criticality Control; La Gestion des Matieres Nucleaires et ses Rapports avec la Securite Nucleaire et le Controle de la Criticite; Obrashchenie s yadernymi materialami i ego svyaz' s yadernoj bezopasnost'yu i kontrolem nad kritichnost'yu; La Administracion de Materiales Nucleares y sus Relaciones con la Seguridad Nuclear y el Control de la Criticidad

Energy Technology Data Exchange (ETDEWEB)

Tingey, F. H. [Phillips Petroleum Company, Idaho Falls, ID (United States)

1966-02-15

dictated by the technical considerations and familiar with the operational limitations. The administrative problems are solved through procedural restrictions placed by the supervisor. The NMM office can be most valuable in further support to the supervisor in these activities. The primary responsibility of this office is to alert responsible supervision to potentially hazardous situations as indicated either from information made available through the routine processing of accountability data or from material balance calculations. Any information pertaining to criticality studies as requested from the NMM office must be accurate and precise. A vigorous inventory management policy must be pursued to lessen the problems presented by accumulation of fissile materials. Internal audit by the NMM staff of inventory holdings can also serve to verify adherence to safeguard procedures. A vigorous orientation programme can be implemented by the NMM staff in its dealing with those individuals handling nuclear materials to make them more aware of the hazards involved. The integration of the NMM group into the general criticality safeguard problems at the NRT and has provided an effective system for assisting the line supervision in discharging this very important responsibility. (author) [French] Il est essentiel pour tous ceux qui travaillent dans l'industrie nucleaire de savoir comment eviter que des matieres nucleaires ne se trouvent rassemblees en quantites, selon une geometrie ou dans un milieu tels qu'elles puissent donner lieu a une reaction neutronique en chaine. Ceci interesse tout particulierement ceux qui, dans l'exercice de leurs fonctions, sont responsables de la manipulation, du transfert et de l'entreposage des matieres fissiles. Ces memes personnes participent au systeme de gestion des matieres nucleaires. Elles ont au premier chef la responsabilite de fournir et de recevoir les donnees comptables par l'intermediaire du service de gestion des matieres nucleaires

Situation of radioactivity monitoring in French Polynesia in 2014. Synthesis of results from the IRSN's monitoring network

International Nuclear Information System (INIS)

Bouisset, P.; Nohl, M.; Leclerc, G.; Rua, J.; Bernagout, S.; Delabbaye, P.; Vismes, A. de

2015-01-01

Exercised in Polynesia since 1962, the radiological monitoring of the environment, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagos, and consists in taking regular samples of various kinds from the different environmental compartments (air, water, soil) with which the population may be in contact and foods. For the first time in 2014, IRSN have participating to the TURBO DGA and CEA program, in charge of the military atoll radiological monitoring, and have collecting ocean samples at Moruroa. Regarding food, the samples analysed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, from the lagoon environment and from the terrestrial environment. Almost all samples are measured at the Laboratory for the Study and Monitoring of the Environment IRSN, based in Vairao on the island of Tahiti. After a steady fall in radioactivity levels since the French atmospheric tests come to an end in 1974, the radiological level observed in 2014 has been stable in the recent year and is now very low. This residual radioactivity relates primarily to the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-sieverts per year). This value corresponds to less than 0.5 % of exposure due to natural radioactivity in Polynesia (approximately 1,000 μSv.y -1 ). From 2010, monitoring of natural radioactivity was performed in several islands. Dose rates are very low, below 1,000 μSv.y -1 . However, highest results were observed when soils come from volcanoes rocks, like on the 'marae'. The highest value, 6,000 μSv.y -1 , was detected on the Taiata mount at Tubuai. In 2014, these maps concerned Tahiti, Moorea, Hao and Gambier islands. Enhanced radiological monitoring of the environment set up in the wake of the Fukushima disaster, continued in 2014

General phenomenology of underground nuclear explosions; Phenomenologie generale des explosions nucleaires souterraines

Energy Technology Data Exchange (ETDEWEB)

Derlich, S; Supiot, F [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

1969-07-01

An essentially qualitatively description is given of the phenomena related to underground nuclear explosions (explosion of a single unit, of several units in line, and simultaneous explosions). In the first chapter are described the phenomena which are common to contained explosions and to explosions forming craters (formation and propagation of a shock-wave causing the vaporization, the fusion and the fracturing of the medium). The second chapter describes the phenomena related to contained explosions (formation of a cavity with a chimney). The third chapter is devoted to the phenomenology of test explosions which form a crater; it describes in particular the mechanism of formation and the different types of craters as a function of the depth of the explosion and of the nature of the ground. The aerial phenomena connected with explosions which form a crater: shock wave in the air and focussing at a large distance, and dust clouds, are also dealt with. (authors) [French] On donne une description essentiellement qualitative des phenomenes lies aux explosions nucleaires souterraines (explosion d'un seul engin, d'engins en ligne et explosions simultanees). Dans un premier chapitre sont decrits les phenomenes communs aux explosions contenues et aux explosions formant un cratere (formation et propagation d'une onde de choc provoquant la vaporisation, la fusion et la fracturation du milieu). Le deuxieme chapitre decrit les phenomenes lies aux tirs contenus (formation d'une cavite et d'une cheminee). Le troisieme chapitre est consacre a la phenomenologie des tirs formant un cratere et decrit notamment le mecanisme de formation et les differents types de crateres en fonction de la profondeur d'explosion et de la nature du terrain. Les phenomenes aeriens lies aux explosions formant un cratere: onde de pression aerienne et focalisation a grande distance, nuages de poussieres, sont egalement abordes. (auteurs)

Relationship between the nuclear resonance of cobalt metal and its ferromagnetic properties; Relations entre la resonance nucleaire du cobalt metallique et ses proprietes ferromagnetiques

Energy Technology Data Exchange (ETDEWEB)

Aubrun, J.N. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-05-15

Theoretical study of nuclear magnetic resonance in ferromagnetic metals shows the near dependence of ferromagnetic properties and unusual feature of this nuclear resonance. This results from a strong interaction between nuclei and magnetic electrons. They excite the nuclei, and, in Bloch walls, submit them to a RF field much stronger than those directly applied. The parameters of the resonance are determined from wall movement and depend consequently of ferromagnetic constants. The theory is enable to provide quantitatively some peculiar effects, specially those of a continuous magnetic field and of temperature. Experimental study was made on cobalt powders, and is in good agreement with theory. However one must take the skin-effect into consideration and accordingly adjust, the theory. This can explain some observed divergences, as well as the influence at particles size and magnetic field over the line shape. Original informations have been obtained about some typical ferromagnetic properties of cobalt, when studying magnetic field effect, and it has been able to apply this method to other ferromagnetic materials. In consideration of the peculiar characteristics of this nuclear resonance, which occurs without external magnetic field and whose line width is large, new models of spectrographs have been realized and have permitted accurate measures of the line shape. The weak intensity of the signals obtained in some cases, has induced the elaboration of an original method of extraction whose theory and practical uses are described here. The whole of this experiment reveals the nuclear resonance as a strong way for the study of ferromagnetism, which is able to detect microscopic phenomenons, not easily accessible by classical methods. (author) [French] L'etude theorique de la resonance magnetique nucleaire dans les metaux ferromagnetiques revele l'etroite liaison entre les proprietes ferromagnetiques et l'aspect inhabituel de cette resonance. Ceci

Relationship between the nuclear resonance of cobalt metal and its ferromagnetic properties; Relations entre la resonance nucleaire du cobalt metallique et ses proprietes ferromagnetiques

Energy Technology Data Exchange (ETDEWEB)

Aubrun, J N [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-05-15

Theoretical study of nuclear magnetic resonance in ferromagnetic metals shows the near dependence of ferromagnetic properties and unusual feature of this nuclear resonance. This results from a strong interaction between nuclei and magnetic electrons. They excite the nuclei, and, in Bloch walls, submit them to a RF field much stronger than those directly applied. The parameters of the resonance are determined from wall movement and depend consequently of ferromagnetic constants. The theory is enable to provide quantitatively some peculiar effects, specially those of a continuous magnetic field and of temperature. Experimental study was made on cobalt powders, and is in good agreement with theory. However one must take the skin-effect into consideration and accordingly adjust, the theory. This can explain some observed divergences, as well as the influence at particles size and magnetic field over the line shape. Original informations have been obtained about some typical ferromagnetic properties of cobalt, when studying magnetic field effect, and it has been able to apply this method to other ferromagnetic materials. In consideration of the peculiar characteristics of this nuclear resonance, which occurs without external magnetic field and whose line width is large, new models of spectrographs have been realized and have permitted accurate measures of the line shape. The weak intensity of the signals obtained in some cases, has induced the elaboration of an original method of extraction whose theory and practical uses are described here. The whole of this experiment reveals the nuclear resonance as a strong way for the study of ferromagnetism, which is able to detect microscopic phenomenons, not easily accessible by classical methods. (author) [French] L'etude theorique de la resonance magnetique nucleaire dans les metaux ferromagnetiques revele l'etroite liaison entre les proprietes ferromagnetiques et l'aspect inhabituel de cette resonance. Ceci resulte du

Description of methods for making activation detectors for use in nuclear reactors; Description des procedes de fabrication des detecteurs d'activation utilises dans les reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Barbalat, R; Le Coguie, R; Leger, P; Salon, L; Thierry, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1968-07-01

A brief description of methods currently used for making activation detectors, thin films and various deposits used in nuclear reactors. The thicknesses required vary from about a few tenths of a micron to a few tenths of a millimeter. Different techniques are used for fixing the large variety of elements: rolling, moulding, painting, electrolysis, vacuum deposition, thin films, wires, enamels, protective linings, etc. (authors) [French] Expose succinct des procedes actuellement mis en oeuvre pour la realisation des detecteurs d'activation, feuilles minces et depots divers utilises dans les reacteurs nucleaires. La gamme des epaisseurs necessaires s'etendant approximativement des dixiemes de micrometre aux dixiemes de millimetre. La diversite des elements a fixer justifiant les techniques differentes selon les cas: laminage, moulage, peinture, electrolyse, depot sous vide, couches minces, fils, emaux, revetements protecteurs, etc. (auteurs)

The formal notices of the French authority of nuclear safety; Les mises en demeure de l'autorite de surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The French authority of nuclear safety (ASN) publishes on its web site (http://www.asn.gouv.fr) the formal notices and official statements addressed by the ASN to the concerned responsible persons (operators of nuclear facilities, directors of companies etc..) when anomalies requiring a corrective action have been noticed during on-site or off-site safety inspections. This document brings together the formal notices addressed by the ASN since June 2000 and up to April 2002. (J.S.)

The nuclear safety and the radiation protection in France in 2003; La surete nucleaire et la radioprotection en France en 2003

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-03-15

Nine points are reviewed: the law project relative to the safety and openness in nuclear field, the safety of the European PWR type Reactor, the priorities in radiation protection, inspection of radiation protection, the surveillance of patients exposure to ionizing radiations, the hot days and dryness of summer 2003 and the functioning of nuclear power plant, the national planning of radioactive waste management, the becoming of high level and years living radioactive waste, the European nuclear policy. (N.C.)

Progress report: nuclear safety and radiation protection in 2006; Rapport annuel: la surete nucleaire et la radioprotection en France en 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

For the French Nuclear Safety Authority (Asn), the year 2006 was marked by two important nuclear laws being passed, one of which brought about a major change in its status. The year was a relatively satisfactory one with regard to nuclear safety, although the picture was more contrasted concerning radiation protection: in this area, more particularly in the medical field, the overall impression of good progress is offset by the declaration of a number of radiotherapy accidents. Given the benefits expected from radiotherapy treatment by the patient suffering from cancer, the conditions in which this activity is carried out are a subject of major concern for Asn, in the light of the serious risks linked to patient over-exposure. ( some important points as follows: the law on transparency and security in the nuclear field, the law on sustainable management of radioactive materials and waste, Asn: an independent administrative authority, EPR reactor project safety, I.R.R.S.: an international audit of Asn in 2006, harmonization of nuclear safety, cancer radiotherapy, improved information of the public after the T.S.N. law, taking account of organisational and human factors). (N.C.)

Underground nuclear explosions. Geological survey of the cavities; Explosions nucleaires souterraines etude geologique des cavites

Energy Technology Data Exchange (ETDEWEB)

Faure, J [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

1969-07-01

A geological survey of underground nuclear explosions makes it possible to determine the main characteristics of the cavity formed. The lower portion is spherical; the same was very likely true of the roof, which collapses in the majority of media with the exception of rock-salt. Its radius, for a given bomb size, can vary by a factor of two according to the type of rock. The lay-out of its contents depends on the characteristics of the solid and liquid products at the moment of the roof collapse; according to the medium involved, mixing of the rubble and the mud-flow occurs (granite) or does not occur (tuff and alluvia). In all media, the average physical properties can be evaluated. (author) [French] L'etude geologique d'explosions nucleaires souterraines permet de determiner les principaux caracteres de la cavite creee. Sa partie inferieure est spherique; il en etait vraisemblablement de meme de sa voute, effondree dans la plupart des milieux a l'exception du sel gemme. Son rayon, a energie d'engin egale, varie selon les roches du simple au double. La disposition de son contenu depend des caracteristiques des produits solides et liquides au moment de la chute du toit; selon le cas, il n'y a pas (tuf et alluvions) ou il y a (granite) melange des eboulis et des laves. Dans tous les milieux, les proprietes physiques moyennes peuvent etre evaluees. (auteur)

Improvement of pressure-vessel surveillance of a PWR-power plant of the Societe d'Energie Nucleaire Franco-Belge des Ardennes (S.E.N.A.)

International Nuclear Information System (INIS)

Bevilacqua, A.; Lloret, R.; Riehl, R.

1984-01-01

This paper describes a new dosimetry, installed inside and outside the Pressure Vessel of CHOOZ Nuclear Power Plant of the Societe d'Energie Nucleaire Franco-Belge des Ardennes (S.E.N.A.), during its 1982-83 operation cycle. The inner dosimetry deals with a simulated capsule located under the reactor plate, and includes copper, nickel, iron, niobium, copper-cobalt, neptunium and uranium dosimeters. Its aim is to qualify the information given by the existing copper dosimetry. The spectrum used with these measurements is obtained by the 1 D ANISN Code and BIP-N 2 library. The outer dosimety is the fluence determination along the outer wall of the vessel. Two tubes, equiped by neutron dosimeters, seven meters long, were fixed along the vessel. On the median plane, the results are compared to a 2 D DOT transport calculation. Preliminary results are given which improve the vessel and specimens neutronic characterisation. (Auth.)

Balance between automation and human actions in nuclear power plant operation. Results of international cooperation; Equilibre entre automatisation et action humaine dans la conduite des centrale nucleaires, resultats de la cooperation internationale

Energy Technology Data Exchange (ETDEWEB)

Sun, B [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d' Analyse de Surete; Bastl, W [Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany); Olmstead, R [Atomic Energy of Canada Ltd, Mississauga (Canada); Oudiz, A [Electric Power Research Inst., Palo Alto, CA (United States); Jenkinson, J [Nuclear Electric PLC, Gloucester (United Kingdom); Kossilov, A [International Atomic Energy Agency, Vienna (Austria)

1990-07-01

Automation has long been an established feature of power plants. In some applications, the use of automation has been the significant factor which has enabled plant technology to progress to its current state. Societal demands for increased levels of safety have led to greater use of redundancy and diversity and this, in turn, has increased levels of automation. However, possibly the greatest contributory factor in increased automation has resulted from improvements in information technology. Much recent attention has been focused on the concept of inherently safe reactors, which may simplify safety system requirements and information and control system complexity. The allocation of tasks between man and machine may be one of the most critical activity in the design of new nuclear plants and major retro-fits and it therefore warrants a design approach which is commensurate in quality with the high levels of safety and production performance sought from nuclear plants. Facing this climate, in 1989 the International Atomic Energy Agency (IAEA) formed an advisory group from member countries with extensive experience in nuclear power plant automation. The task of this group was to advise on the appropriate balance between manual and automatic actions in plant operation. (author) [French] L'automatisation a longtemps ete une caracteristique bien etablie des centrales nucleaires. Dans certaines applications, l'utilisation de l'automatisation a ete le facteur decisif qui a permis a la technologie des centrales de progresser jusqu'a son etat actuel. Les exigences de l'opinion publique en matiere de securite renforcee ont conduit a l'utilisation d'une plus grande redondance et a une plus grande diversification et ceci, en retour, a encore accru le niveau d'automatisation. Toutefois, il est possible que le facteur preponderant de cet accroissement de l'automatisation soit constitue par les progres effectues dans la technologie de l'information. Plus recemment, l'attention s

Lessons learned from accident simulation exercises and their implications for operation of the IPSN Centre Technique de Crise

International Nuclear Information System (INIS)

Manesse, D.; Ney, J.; Crabol, B.; Ginot, P.

1990-01-01

The Centre Technique de Crise (CTC) of the Institut de Protection et de Surete Nucleaire (IPSN) has an important role to play in the event of an accident at a nuclear installation of Electricite de France (EdF) concerning diagnosis of the situation and forecasting its evolution. For this purpose the CTS is organized into various groups; only that responsible for the evaluation of the radiological consequences is considered in the present paper. Since the beginning of the eighties numerous simulations of nuclear accidents have been organized both by the public authorities and by the nuclear operators. These exercises, of growing complexity, are distinguished according to the type of installation concerned, the scenario (with and without a simulator), the equipment involved, the participants (local and national officials), the accident phase used (at the time of the accident or post-accident), the use of actual or pre-determined meteorological conditions etc.. Different combinations are imposed as a function of the specific aims of each exercise. Numerous lessons have been drawn progressively from these very varied exercises for the operation of the CTC and, in particular, of the Radiological Consequences Group. The principal Lessons concern: development of calculation and mapping tools, specific liaison with the national meteorological services, modification of the centre's facilities, composition of the team and definition of the role of each of its members, improved liaison with the Site Evaluation Group and the provision of appropriate documentation. The need for continuous training of duty teams in the form of presentations and exercises has also been confirmed

Report of Activity, 1997

International Nuclear Information System (INIS)

Lacoste, Andre-Claude; Livolant, Michel

1998-01-01

The Institute of Nuclear Protection and Safety (Institut de Protection et de Surete Nucleaire) - IPSN carries out research and expert studies needed in managing nuclear risk and consequences of nuclear events on population and environment, i.e. supervises the safety of installations, the prevention and study of accidents, the human health and environmental conditions, the safety of transport and has also the task of organizing the management of the crisis situations. IPSN has the mission of informing the public and participates in numerous international actions. Thus, since 1989 IPSN and its German counterpart, GRS, co-operate towards improving of the nuclear safety in Europe and developing a common approach of international issues. As acting for public authorities (government departments in charge with industry, environment, health or labor), IPSN grants technical authorizations on request of DSIN exploiters. The IPSN personnel amounts up to 1300 employees of whom around two thirds are engineers, researchers, physicians, agronomists, and veterinarians. This IPSN annual report contains in the 'Free Tribune' section two general papers entitled: 'The federalist role of research at IPSN' by Catherine Lecompte and 'The dose, a central issue in radioprotection debates' by Annie Sugier. Then five sub-reports follow: 1.The safety of nuclear facilities and radioactive wastes; 2.Crisis management; 3. The management of sensitive materials (protection and control of sensitive materials and safety analysis of the radioactive materials transport); 4.Protection of human health; 5.Environment protection. The report also presents the international activities, the cooperation IPSN/GRS, the budget, the staff and the human resource policy and the communication activity

Historical seismicity in Morocco: methodological aspects and cases of multidisciplinary evaluation

International Nuclear Information System (INIS)

Elmrabet, T.; Ramdani, M.; Tadili, B.

1989-05-01

Within the framework of a cooperative agreement between Sofratome and the Office National d'Electricite of Morocco, the Centre National de la Recherche of Rabat, with the collaboration of the French Institut de Protection et de Surete Nucleaire, was put in charge of compiling a revised catalogue of the historical seismicity of Morocco. The method adopted calls for the participation of several different disciplines in view of situating each earthquake in its own geographical and historical context. The approach entails, during the first stage involving primarily the historian, gathering together the original sources of data and subjecting them to a critical analysis in order to assess their reliability. The second stage consists in interpreting the information so as to define those earthquake characteristics that are requisite to seismic hazard studies. This latter evaluation must be the fruit of a multidisciplinary effort. This is particularly true for earthquakes of past centuries, the observations of which are frequently incompatible or biased and accordingly need to be substantiated by referring to information of a varying nature and, wherever possible, calibrated using accurate data from recent events. In a number of instances, duplications are encountered, or lumped effects for distinct events due to calendar misreckonings, erroneous copying, or misconceptions relative to the geological or historical context. A particularly significant example of the interference of these diverse aspects is afforded by the assessment of the destructive effects in Morocco of the 1755 'Lisbon' earthquake: a method is proposed for calibrating its intensities by comparing them with those of the recent 1969 event of similar origin

Nuclear magnetic resonance of iron-57 nuclei in local fields in yttrium and iron garnets; Resonance magnetique nucleaire des noyaux du fer 57 dans les champs locaux du grenat d'yttrium et de fer

Energy Technology Data Exchange (ETDEWEB)

Robert, C. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1961-07-01

We have demonstrated the nuclear resonance of {sup 57}Fe nuclei in the local field of each of the two magnetic sub-lattices of yttrium and iron garnets. The resonance frequencies and the relaxation times have been measured as a function of the temperature. (author) [French] Nous avons mis en evidence la resonance nucleaire des noyaux de {sup 57}Fe dans le champ local de chacun des deux sous-reseaux magnetiques du grenat d'yttrium et de fer. Les frequences de resonances et les temps de relaxation ont ete mesures en fonction de la temperature. (auteur)

IRSN's opinion on criteria retained by the ANDRA for choosing a 'zone of interest for deepened investigation' (ZIRA, zone d'interet pour la reconnaissance approfondie) for the HA-MAVL-Site de Meuse/Haute-Marne project

International Nuclear Information System (INIS)

2009-12-01

Within the context of selection of a site for a future deep storage for high- and intermediate-level activity and long life wastes, this report comments the various results of geological investigations and characterizations performed on this site during the past years. It notices that the most recent results (2007 and 2008) do not put previous conclusions (2005) into question. It recalls the required geological characteristics for such a storage site and compares them with the site characteristics. The IRSN agrees with the technical criteria adopted by the ANDRA for the choice of a zone of interest for a deepened investigation, and more particularly for this particular zone located on the territory of both French departments of Meuse and Haute-Marne

Radioactivity monitoring within the environment of the Loire basin. A partnership between the IRSN and the Dampierre-en-Burly and Saint-Laurent CLIs at the service of citizen vigilance

International Nuclear Information System (INIS)

2008-01-01

The first part of this report presents the Loire basin and its environment, discusses the physical-chemical quality control of its waters and the main usages of the Loire waters. It also presents the nuclear installations present in the Loire basin (electricity production nuclear power stations and other installations), the actors involved in radioactivity measurement in the Loire basin environment (IRSN, EDF, AREVA, associations for the monitoring of water quality, public services), and the national network for radioactivity measurement in the environment. The second part describes and reports the radioactivity monitoring of the environment in the Loire basin, i.e. in the atmosphere, in rain waters and in continental waters, and in the food chain. Addressing this monitoring activity, a last part discusses the evolution of measurements, the importance of the plurality of actors involved in sampling and measurement (in order to guarantee the monitoring system transparency), the variety of sources, the assessment of health impact

SFEN Annual Convention 2012 - The nuclear energy one year after Fukushima. Proceedings; Convention SFEN 2012 - Le nucleaire un an apres Fukushima. Recueil des presentations

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-03-15

This document brings together the available presentations given at the 2012 edition of the Annual Convention of the French society of nuclear energy (SFEN) on the topic of nuclear energy one year after Fukushima. Twenty four presentations (slides) are compiled in this document: 1 - Presentation and introduction of the Annual Convention (Luc Oursel - SFEN President); 2 - Status of onsite/offsite remedial actions, key lessons learned (Akira Omoto, Tokyo univ., Japan Atomic Energy Commission); 3 - Complementary Safety Assessments (CSA) of the French NPP fleet (Dominique Miniere, EDF); 4 - Speech of M. Francois Fillon - Prime Minister; 5 - CSA of the fuel cycle facilities (Philippe Knoche, Areva); 6 - CSA of the EPR (Bertrand de l'Epinois, Areva; Jean-Luc Foret, EDF CNEN); 7 - The collective responsibility of the operators: the action of WANO (Laurent Stricker, WANO); 8 - Conclusions of French Nuclear Safety Authority (ASN) - Safety measures to be strengthened; 9 - Opinion no. 2012-AV-013 from January 3, 2012 of the French Nuclear Safety Authority - ASN (Sophie Mourlon, ASN; Caroline Lavarenne, IRSN); 10 - Nuclear energy: an energy for the future (Bernard Bigot, CEA); 11 - The nuclear phaseout in Germany from the view of German industry (Eberhard von Rottenburg, BDI); 12 - Prospects in China (Wei Lu, CGNP Europe); 13 - Industry Current Status and its Prospects in the United States (J. Spina, CENG); 14 - Nuclear energy prospects in France: recommendations of the Commission 'Energy 2050' (Jacques Percebois, Creden); 15 - Electrical generation system efficiency and economy (Yves Giraud, EDF); 16 - Electrical generation systems and distribution networks (Herve Mignon, Rte); 17 - Prospects in the UK (Tim Stone, DECC/OND, Senior Adviser to the Secretary of State); 18 - Climatic changes and energy policy (Laura Cozzi, IEA); 19 - The young nuclear professionals network (Boris Supiot, SFEN Young Generation Group); 20 - Socio-economic impacts of the nuclear power

A study of switch circuits for use as safety devices in nuclear reactors; Etude de circuits de commutation destines a la securite des reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Hantcherian, V [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1960-12-15

The author reviews briefly a few basic assemblies using electromagnetic relays for safety circuits in nuclear reactors; he then studies the use of static relays with a shorter time of response, based on impedance changes in a self-inductance consisting of a coil with a magnetic core having a rectangular hysteresis cycle. The author examines in particular the way in which it functions and the method of determining the parameters. (author) [French] L'auteur apres avoir examine sommairement en revue quelques montages de base des circuits de securite des reacteurs nucleaires utilisant des relais electromecaniques, etudie l'emploi des relais statiques a plus grande vitesse de reponse bases sur la variation d'impedance que presente une self-inductance realisee a l'aide d'une bobine enroulee autour d'un noyau magnetique a cycle d'hysteresis rectangulaire. En particulier, il en examine le mode de fonctionnement et la determination des parametres. (auteur)

Economic Criteria Applied to Nuclear Materials Management; Criteres Economiques Applicables a la Gestion des Matieres Nucleaires; Ehkonomicheskie kriterii, primenyaemye pri kontrole i uchete yadernykh materialov; Criterios Economicos Aplicados a la Administracion de Materiales Nucleares

Energy Technology Data Exchange (ETDEWEB)

Shelley, W. J.; Kuehn, M. N. [Mallinckrodt Chemical Works, St. Charles, MS (United States)

1966-02-15

placed upon such personnel to accept, understand and perform the work. Such personnel selected must be thoroughly and minutely trained in the importance of their activity. Those responsible for the management of nuclear materials must be continually alert to the smallest kind of aberration in the quality and performance of the personnel, the process, the systems, procedures and techniques. Only through such alertness and willingness to revise, so as to secure improvement, does one secure the optimum balance of costs and needs. (author) [French] La gestion des matieres nucleaires doit etre subordonnee aux objectifs principaux du traitement de ces matieres, c'est-a-dire la production d'energie ou la fabrication de produits finis. Les responsables de la gestion des matieres nucleaires doivent donc tenir constamment compte des besoins de la production principale et adapter les methodes de gestion aux operations de facon a pouvoir assurer cette gestion avec un minimum de depenses. Le systeme de gestion des matieres nucleaires doit soigneusement tenir compte des divers facteurs qui influent sur son prix de revient. Il vient en complement des operations et doit entrainer le minimum de frais de personnel et d'analyse et provoquer le moins d'interruptions possible dans les operations. U doit etre integre a ces dernieres, de facon que les renseignements d'ordre quantitatif qu'il permet d'obtenir puissent etre communiques rapidement aux responsables du controle des operations. Le systeme d'enregistrement et de preparation des rapports doit fournir une quantite maximale de donnees subsidiaires. Il doit etre compatible avec les systemes utilises par les fournisseurs et les consommateurs et assurer la diffusion, partout ou cela est possible, de renseignements supplementaires concernant les lots de matieres nucleaires. Les donnees a fournir pour le controle des matieres nucleaires doivent se limiter a celles qui sont necessaires pour s'assurer qu'il n'y a pas de pertes importantes, de

Radioactivity monitoring within the environment of the Loire basin. A partnership between the IRSN and the Dampierre-en-Burly and Saint-Laurent CLIs at the service of citizen vigilance; Surveillance de la radioactivite dans l'environnement du bassin de la Loire. Un partenariat entre l'IRSN et les CLI de Dampierre-en-Burly et de Saint-Laurent-des-Eaux au service de la vigilance citoyenne

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

The first part of this report presents the Loire basin and its environment, discusses the physical-chemical quality control of its waters and the main usages of the Loire waters. It also presents the nuclear installations present in the Loire basin (electricity production nuclear power stations and other installations), the actors involved in radioactivity measurement in the Loire basin environment (IRSN, EDF, AREVA, associations for the monitoring of water quality, public services), and the national network for radioactivity measurement in the environment. The second part describes and reports the radioactivity monitoring of the environment in the Loire basin, i.e. in the atmosphere, in rain waters and in continental waters, and in the food chain. Addressing this monitoring activity, a last part discusses the evolution of measurements, the importance of the plurality of actors involved in sampling and measurement (in order to guarantee the monitoring system transparency), the variety of sources, the assessment of health impact

Burkina Faso Experience with Establishment and Maintenance of an SSAC

International Nuclear Information System (INIS)

Belemsaga, D.M.A.; Ouedraogo, Z.A.; Sangre, S. Sam; Nabayaogo, D.

2010-01-01

Burkina Faso is a State with Small Quantity Protocol and its Additional Protocol (INFCIRC/618/Add.1) interred into force on the 17 of April 2003. Burkina Faso is involved in the Agency nuclear security activities through many multilateral and bilateral agreements; and obviously, Safeguards Agreements. The International Atomic Energy Agency (IAEA)'s statutes have been ratified by Burkina Faso in 1998. The country became IAEA membership since 14 September 1998 (number of accession: 128). The basic law relating to radiation protection and nuclear safety has been voted by the National Assembly on 26 April 2005. This law is the legal basis that allowed the creation of the National Regulatory Authority for Radiation protection and Nuclear safety (ARSN). The global aim is to regulate activities involving nuclear materials or radioactive sources, to control the traffic of such materials and to manage radioactive waste within the country. ARSN is the national regulatory body competent for the control of the better use of ionizing radiation sources. This authority received mandate to establish and maintain an SSAC in accordance with the IAEA guidance. For the ARSN to be effective in its responsibilities, all activities involving radiation exposure are subjected to regulatory control by a system of notification, authorization by registration or licensing and inspection. Two separated infrastructures are dealing with nuclear energy. The first one, called Autorite Nationale de Radioprotection et de Surete Nucleaire (ARSN) ) is acting as a regulator. The second one, Secretariat Technique a l'Energie Nucleaire (STEA) acts as a promoter. During the Santa Fe International Training Course, USA may 2008, we agreed the Burkina Faso SSAC to be implemented by ARSN. The STEA should be involved by sending officially reports and declarations (received from ARSN) to the IAEA, through the National Liaison Officer. In order to maintain the SSAC, physical inventories are conducted, regularly

Damage caused to houses and equipment by underground nuclear explosions; Degats dus aux explosions nucleaires souterraines sur les habitations et les equipements

Energy Technology Data Exchange (ETDEWEB)

Delort, F; Guerrini, C [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

1969-07-01

A description is given of the damaged caused to various structures, buildings, houses, mechanical equipment and electrical equipment by underground nuclear explosions in granite. For each type of equipment or building are given the limiting distances for a given degree of damage. These distances have been related to a parameter characterizing the movement of the medium; it is thus possible to generalize the results obtained in granite, for different media. The problem of estimating the damage caused at a greater distance from the explosion is considered. (authors) [French] Les degats sur diverses structures, constructions, habitations, equipements mecaniques et materiels electriques provoques par des explosions nucleaires souterraines dans le granite sont decrits. On a indique pour chaque type de materiel ou de construction, les distances limites correspondant a un degre de gravite de dommage observe. Ces distances ont ete reliees a un parametre caracterisant le mouvement du milieu, permettant ainsi de generaliser les resultats obtenus dans le granite, a differents milieux. Le probleme de la prevision des degats en zone lointaine a ete aborde. (auteurs)

Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

Energy Technology Data Exchange (ETDEWEB)

Robert, C [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

1962-07-01

Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

Professional Nuclear Materials Management; Gestion Industrielle des Matieres Nucleaires; Obrashchenie s yadernymi materialami na professional'nom urovne; Administracion Eficiente de Materiales Nucleares

Energy Technology Data Exchange (ETDEWEB)

Forcella, A. A.; O' Leary, W. J. [Allis-Chalmers Manufacturing Company, Bethesda, MD (United States)

1966-02-15

. (author) [French] Le memoire expose en quoi consiste la gestion des matieres nucleaires dans une centrale nucleaire type, aux Etats-Unis. Comme le reacteur en question est partiellement finance a l'aide de capitaux prives, l'une des principales obligations de l'exploitant est d'assurer la protection et la rentabilite des investissements. Etant donne que les matieres nucleaires sont d'une valeur intrinseque elevee, il faut constamment proceder a des controles appropries allant au-dela des mesures de securite et de la comptabilite interessant les matieresnucleaires proprement dites afin de reduire les pertes au minimum. Il faut faire preuve de clairvoyance et planifier judicieusement pour prevenir toute perte supplementaire de capital provenant de frais inutiles ou d'un manque a gagner dans divers secteurs de l'exploitation. C'est ainsi que le gestionnaire de matieres nucleaires doit prendre des dispositions pour garantir la bonne marche des operations et assurer le respect des plans d'execution par une liaison et un controle constants, dans les domaines suivants? a) acquisition du combustible et des elements combustibles, b) utilisation des elements combustibles dans le reacteur et c) recuperation, dans le combustible irradie, des produits et matieres presentant de l'interet. Pendant la periode qui precede l'utilisation du reacteur, il faut faire une place importante dans la planification et les travaux preparatoires aux considerations d'economie dans la conception des elements combustibles, en ce qui concerne leur fabrication, leur manutention, leur transport et leur remplacement. Les differentes etapes de la fabrication doivent etre planifiees de facon a reduire au minimum le manque a gagner du a des periodes improductives d'entreposage de matieres tres couteuses. Pendant la marche du reacteur, il faut assurer une combustion maximale de la matiere fissile par des redistributions appropriees du combustible dans le coeur du reacteur. Parallelement, les temps morts dus a

Quantitative measurements of small isotopic samples in gaseous mixtures by utilization of some nuclear properties; Etude des possibilites de mesures de faibles quantites de gaz radioactifs dans un melange en utilisant simultanement plusieurs proprietes nucleaires

Energy Technology Data Exchange (ETDEWEB)

Maragnon, J; Delperie, C

1967-12-01

The question is to define the characteristics of a group of measurements allowing the analysis of traces of radioactive rare gases in gas mixtures of different composition. To distinguish the radioactive isotopes from each other and the activity level reaching 10{sup 6} due to their nuclear properties, the method was chosen to use several nuclear properties: gamma radiation energy, beta particle energy, lifetime of excited states. The choice of a plastic scintillator as beta detector allows to answer satisfactorilly to this demand by measurement of nuclear constants because of the short de/excitation time of this detector. Another advantage is that it can be a reservoir for the sample without any destruction nor modification of the sample. The study has been based on the mixture of Kr-85, the analysis of other rare gases follwos immediately from the adopted principle. [French] Les auteurs ont oriente leur recherche vers une solution permettant de distinguer les isotopes radioactifs les uns des autres et dans des rapports d'activite pouvant atteindre 10{sup 6}, grace a plusieurs de leurs proprietes nucleaires, energie de rayonnement gamma, energie de la particule beta, temps de vie des niveaux excites. Le choix d'un scintillateur plastique comme detecteur beta permet de repondre d'une maniere satisfaisante a la mesure des constantes nucleaires en raison du temps de de/excitation rapide de ce scintillateur. Il offre en outre l'avantage de pouvoir servir de reservoir a l'echantillon sans entrainer aucune destruction ni modification de celui-ci. L'etude a ete basee sur la mixture de Kr-85, l'analyse des autre gaz rares decoulant immediatement du principe adopte. (auteur)

The nuclear power stations of the French atomic energy programme (1960); Les centrales nucleaires de puissance du programme francais (1960)

Energy Technology Data Exchange (ETDEWEB)

Leduc, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Roux, J P [Electricite de France (EDF), 75 - Paris (France)

1960-07-01

After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [French] Apres avoir rappele l'integration de l'energie nucleaire parmi les moyens de production de l'energie en France, les auteurs se penchent surtout sur l'evolution des techniques appliquees dans l'equipement des centrales nucleaires francaises et decrivent les moyens mis en oeuvre pour reduire les prix de revient du kWh d'EDF2 et d'EDF3 par rapport a EDF1: la puissance electrique par tonne d'uranium varie de 493 kW/t pour EDF1 a 970 kW/t pour EDF3. C'est dans ce but que les puissances thermiques et la puissance unitaire des groupes turbo-alternateurs passent respectivement de 290 MWt pour EDF1 a 1200 ou 1600 MWt pour EDF3 et de 82 a 250 MW. Les resultats sont obtenus par une amelioration des caracteristiques neutroniques, des progres realises sur la technologie des elements combustibles, une simplification du systeme de

Contributions to safety studies for new concepts of nuclear reactors; Contributions aux etudes de surete pour des filieres innovantes de reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Perdu, F

2003-12-01

The complete study of molten salt reactors, designed for a massive and durable nuclear energy production, must include neutronics, hydraulics and thermal effects. This coupled study, using the MCNP and Trio{sub U} codes, is undertaken in the case of the MSRE (molten salt reactor experiment) prototype. The obtained results fit very well the experiment. Their extrapolation suggests ways of improving the safety coefficients of power molten salt reactors. A second part is devoted to accelerator driven subcritical reactors, developed to incinerate radioactive waste.We propose a method to measure the prompt reactivity from the decay following a neutron pulse. It relies only on the distribution of times between generations, which is a characteristic of the reactor. This method is implemented on the results of the MUSE 4 experiment, and the obtained reactivity is accurate within 5%. (author)

Nuclear Safety and Radiation Protection in France in 2005; La surete nucleaire et la radioprotection en France en 2005. Dossier de presse

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-15

In 2005, the Asn pursued its significant investment in radiation protection and reaffirms its ambition to become as efficient in radiation protection as it is in nuclear safety as of 2009. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. The Asn plans to step up its efforts to ensure better monitoring of patient exposure to ionizing radiation and to provide better management of radon-related risks, particularly in housing. Fully aware that its newfound power in this area requires outside evaluation, the Asn has asked the International Atomic Energy Agency (IAEA) to organize an I.R.R.S. (Integrated Regulatory Review Service) assignment consisting of a peer-conducted audit. The IAEA has confirmed that this audit will take place in November 2006. (N.C.)

Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

Reports by the Parliamentary Office for scientific and technological assessments. Tuesday, May 31, 2011. Hearing opened to the press on the organization of nuclear safety; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Mardi 31 mai 2011. Audition, ouverte a la presse, sur l'organisation de la securite nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-05-15

Members of the French Parliament, and representatives of the French nuclear safety authority (ASN), of the European Nuclear Safety Regulators Group (ENSREG), of the IAEA, of the World Association of Nuclear Operators (WANO), of the French institute for radiation protection and nuclear safety (IRSN) first address the international dimension of nuclear safety control. They describe, comment and discuss the situation of the Fukushima nuclear plant, the impact of this accident on France (cooperation with Japan, atmospheric measurement in France), the different national approaches to nuclear safety, the specifications for the audit of the French nuclear power plants and the security assessments foreseen for the European nuclear stock, the issue of international standard elaboration, the activity of the WANO in the field of international cooperation. In a second part, members of Parliament and representatives of the ASN, the IRSN, EDF, and AREVA and of the French committee of certification of companies for the training and monitoring of personnel working under ionizing radiation (CEFRI) describe, comment and discuss the nuclear safety modalities in France

Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

Energy Technology Data Exchange (ETDEWEB)

Robert, C. [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

1962-07-01

Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

French achievements in the field of nuclear electronics; Realisations francaises dans le domaine de l'electronique nucleaire

Energy Technology Data Exchange (ETDEWEB)

Doireau, M; Fabre, R; Guillon, H; Guyot, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

Nuclear electronic equipment used by the french Atomic Energy Commission has been developed, with an increasing participation of the radioelectric industry (manufacture under AEC license, contracts for prototypes). The equipment for general use has been standardized and satis the technical specification sheets in which are specified more particularly, the conditions for construction, the choice of the spare parts and the conditions for acceptance by the french AEC at factory. The electronic equipment is classified in nine classes, and a brief description of the principal instruments is given in each class. The reliability of the equipment in use is satisfactory, as it is shown by the mean frequency of faults per 1000 hours operation. (author)Fren. [French] L'appareillage d'electronique nucleaire utilise au Commissariat a l'Energie atomique fran is a ete developpe en demandant un concours de plus en plus important a l'industrie radioelectrique (fabrications sous licence CEA, marches de prototypes, etc...). Le materiel d'emploi courant a ete standardise et repond aux specifications de cahiers des charges ou sont precises en particulier les conditions de realisation du materiel, le choix des pieces detachees et les conditions de recette en usine. L'appareillage electronique est classe en neuf rubriques et une description sommaire des principaux appareils est donnee dans chacune des rubriques. La tenue en service du materiel est satisfaisante, ainsi que le montre la frequence moyenne des pannes observees par 1000 heures de fonctionnement. (auteur)

Mobilization suited for each radiological emergency

International Nuclear Information System (INIS)

Chambrette, V.

2013-01-01

This poster presents the role played by IRSN (French Institute for Radiation protection and Nuclear Safety) in case of radiological alert. This alert can be sent by the administration, a fire brigade, a nuclear operator or a remote monitor of radioactivity. In case of an emergency situation: IRSN provides radiological intervention and assistance on the site. In case of national crisis organization, IRSN will implement the emergency technical center and will send a mobile cell to the Operational Command Station of the Prefecture concerned. In both cases IRSN will be in charge of assessing the individuals' exposure and the impact on the environment

International technical assistance example. Consortium action in Bulgaria

International Nuclear Information System (INIS)

Mattei, J.M.; Milhem, J.L.

1993-03-01

The safety status achieved last year at the Kozloduy Nuclear Power Plant (NPP) and the capability of the Bulgarian Nuclear Safety Authority (BNSA) to assess the safety of the plant and the adequacy of proposed improvements have been matters of international concern. However, the Kozloduy NPP contributes 35-40 per cent of the electrical generating capacity in Bulgaria. For further operation of the plants, it is therefore, essential that safety is improved. In july 1991, the Commission of the European Communities (CEC) instituted a Six Months Emergency Action Programme for Bulgaria under the PHARE regional nuclear safety programme. The programme consisted of three parts: - an industrial emergency programme supporting the utility of the Kozloduy NPP, - a study to evaluate Bulgaria's electricity needs, - technical assistance for reinforcement of the Bulgarian Nuclear Safety Authority. For the third part, complementary to the industrial emergency programme carried out by the WANO (World Association of Nuclear Operators), a Consortium of expert institutions and regulatory from EC member states was established by CEC for assistance to BNSA. The Consortium consisted of: - Institut de Protection et de Surete Nucleaire (IPSN), France, technical support of the French regulatory body, - Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) mbH, Germany, an organization in safety engineering, technical support of governmental regulatory body, - AIB-Vincotte Nuclear (AVN), Belgium, the organization authorized by the Belgian Government for licensing and inspection of nuclear power plants, - UK Atomic Energy Authority (AEA Technology), an independent UK Government owned nuclear R and D and consultancy organization, - Nuclear Installations Inspectorate (NII) of the Health and Safety Executive, United Kingdom, the nuclear regulatory body for the United Kingdom

Institute for Energy Technology - Annual report 1997

International Nuclear Information System (INIS)

1998-01-01

Most of the nuclear-related work at Kjeller is based on the JEEP II research reactor, the operation of which is a prerequisite for Kjeller's activities. The work includes basic research in physics, the production of radiopharmaceuticals, the irradiation of materials for various technical applications, neutron radiography, activation analyses and silicon doping. 1997 was the first year of the 1997-1999 research period for the international OECD Halden Reactor Project. With the National Nuclear Regulatory Board (CNEN) of Brazil becoming a member late last year, the Project now include organizations from 20 countries. A membership agreement was also signed with the Institut de Protection et de Surete Nucleaire (IPSN) of France in 1997. The Project is operation by a staff of 280. In the fuel safety area, work focused chiefly on concerns arising at high burn-up in normal operation and in transient conditions. The unique Halden instrumentation has been extremely valuable for obtaining high relevance data. In respect of core materials, work has concentrated on corrosion issues, including in-core measurements of crack propagation rates in stainless steels. These data are used to estimate the expected lifetime of materials and to learn how effective measures are in improving the materials's performance. In the man-machine are the Halden Man-Machine Laboratory (HAMMLAB) is being upgraded and expanded. Modern, powerful simulators for PWR, BWR and WER reactors began to be installed during the year, and a Virtua Reality centre was set up to complement the HAMMLAB. As the infrastructure was build up, activities dwelt on human factors studies, encompassing situation awareness, the development and assessment of operator support systems, and the validation of software

Report of Activity, 1997; Rapport d'activite, 1997

Energy Technology Data Exchange (ETDEWEB)

Lacoste, Andre-Claude; Livolant, Michel [eds.] [Inst. de Protection et de Surete Nucleaire, CEA Centre d' Etudes de Fontenay-aux-Roses, 92 (France)

1998-07-01

The Institute of Nuclear Protection and Safety (Institut de Protection et de Surete Nucleaire) - IPSN carries out research and expert studies needed in managing nuclear risk and consequences of nuclear events on population and environment, i.e. supervises the safety of installations, the prevention and study of accidents, the human health and environmental conditions, the safety of transport and has also the task of organizing the management of the crisis situations. IPSN has the mission of informing the public and participates in numerous international actions. Thus, since 1989 IPSN and its German counterpart, GRS, co-operate towards improving of the nuclear safety in Europe and developing a common approach of international issues. As acting for public authorities (government departments in charge with industry, environment, health or labor), IPSN grants technical authorizations on request of DSIN exploiters. The IPSN personnel amounts up to 1300 employees of whom around two thirds are engineers, researchers, physicians, agronomists, and veterinarians. This IPSN annual report contains in the 'Free Tribune' section two general papers entitled: 'The federalist role of research at IPSN' by Catherine Lecompte and 'The dose, a central issue in radioprotection debates' by Annie Sugier. Then five sub-reports follow: 1.The safety of nuclear facilities and radioactive wastes; 2.Crisis management; 3. The management of sensitive materials (protection and control of sensitive materials and safety analysis of the radioactive materials transport); 4.Protection of human health; 5.Environment protection. The report also presents the international activities, the cooperation IPSN/GRS, the budget, the staff and the human resource policy and the communication activity.

Institute for Energy Technology - Annual report 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-31

Most of the nuclear-related work at Kjeller is based on the JEEP II research reactor, the operation of which is a prerequisite for Kjeller`s activities. The work includes basic research in physics, the production of radiopharmaceuticals, the irradiation of materials for various technical applications, neutron radiography, activation analyses and silicon doping. 1997 was the first year of the 1997-1999 research period for the international OECD Halden Reactor Project. With the National Nuclear Regulatory Board (CNEN) of Brazil becoming a member late last year, the Project now include organizations from 20 countries. A membership agreement was also signed with the Institut de Protection et de Surete Nucleaire (IPSN) of France in 1997. The Project is operation by a staff of 280. In the fuel safety area, work focused chiefly on concerns arising at high burn-up in normal operation and in transient conditions. The unique Halden instrumentation has been extremely valuable for obtaining high relevance data. In respect of core materials, work has concentrated on corrosion issues, including in-core measurements of crack propagation rates in stainless steels. These data are used to estimate the expected lifetime of materials and to learn how effective measures are in improving the materials`s performance. In the man-machine are the Halden Man-Machine Laboratory (HAMMLAB) is being upgraded and expanded. Modern, powerful simulators for PWR, BWR and WER reactors began to be installed during the year, and a Virtua Reality centre was set up to complement the HAMMLAB. As the infrastructure was build up, activities dwelt on human factors studies, encompassing situation awareness, the development and assessment of operator support systems, and the validation of software.

International technical assistance example. Consortium action in Bulgaria; Exemple d`assistance internationale. Cas de la Bulgarie, action du consortium

Energy Technology Data Exchange (ETDEWEB)

Mattei, J M; Milhem, J L [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Heuser, F W; Kelm, P [Gesellschaft fuer Reaktorsicherheit mbH (GRS), Koeln (Germany)

1993-03-01

The safety status achieved last year at the Kozloduy Nuclear Power Plant (NPP) and the capability of the Bulgarian Nuclear Safety Authority (BNSA) to assess the safety of the plant and the adequacy of proposed improvements have been matters of international concern. However, the Kozloduy NPP contributes 35-40 per cent of the electrical generating capacity in Bulgaria. For further operation of the plants, it is therefore, essential that safety is improved. In july 1991, the Commission of the European Communities (CEC) instituted a Six Months Emergency Action Programme for Bulgaria under the PHARE regional nuclear safety programme. The programme consisted of three parts: - an industrial emergency programme supporting the utility of the Kozloduy NPP, - a study to evaluate Bulgaria`s electricity needs, - technical assistance for reinforcement of the Bulgarian Nuclear Safety Authority. For the third part, complementary to the industrial emergency programme carried out by the WANO (World Association of Nuclear Operators), a Consortium of expert institutions and regulatory from EC member states was established by CEC for assistance to BNSA. The Consortium consisted of: - Institut de Protection et de Surete Nucleaire (IPSN), France, technical support of the French regulatory body, - Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) mbH, Germany, an organization in safety engineering, technical support of governmental regulatory body, - AIB-Vincotte Nuclear (AVN), Belgium, the organization authorized by the Belgian Government for licensing and inspection of nuclear power plants, - UK Atomic Energy Authority (AEA Technology), an independent UK Government owned nuclear R and D and consultancy organization, - Nuclear Installations Inspectorate (NII) of the Health and Safety Executive, United Kingdom, the nuclear regulatory body for the United Kingdom.

Radioprotection after therapeutic injection of [{sup 131}I]-mibg: Prerequisite to the MIITOP protocol opening; Radioprotection apres injection therapeutique de [131I]-mIBG: donnees prealables a l'ouverture du protocole MIITOP-0607

Energy Technology Data Exchange (ETDEWEB)

Petyt, G.; Cougnenc, O.; Carpentier, P. [Centre Oscar-Lambret, CLCC Nord-Pas-de-Calais, Dept. de Medecine Nucleaire, 59 - Lille (France); Defachelles, A.S. [Centre Oscar-Lambret, Dept. d' Oncologie Pediatrique, 59 - Lille (France); Cazin, J.L. [Centre Oscar-Lambret, Dept. de Pharmacie Clinique, 59 - Lille (France)

2009-12-15

Introduction The MIITOP-0607 protocol, studying the efficiency of administration of topotecan and myelo-suppressive [{sup 131}I]-mibg therapy in children affected by neuroblastoma, needed to assess irradiation risks on staff and family of children to obtain the agreement of the Autorite de surete nucleaire (A.S.N.). Our aim was to quantify irradiation of the staff during preparation of the mibg and to assay the irradiation and contamination of the accompanying persons. Patient and methods Radiation exposure of the staff was measured during the preparation, transport and administration of the first treatment. Salivary and urinary excretions were monitored well as the atmospheric radioactivity. Radiation exposure and contamination of the accompanying persons were also measured. Results Finger dose of 3 mSv and whole body dose of 50 {mu}Sv were estimated for preparation of an 11.1 GBq syringe. Irradiation from urinary activity can be as low as 100 {mu}Sv if a dedicated device is used. Salivary excretion decreased rapidly during the first 24 hours. Atmospheric contamination always remained below 25 Bq m-3. Total irradiation of the accompanying persons is about 2.35 mSv for the two consecutive injections (9,3 and 11,1 GBq). Internal contamination occurred only once and corresponded to a 27 {mu}Sv whole body irradiation and 670 {mu}Sv thyroid irradiation. Conclusion This study shows the safety of [{sup 131}I]-mibg treatments using high activities. The involved dose is not negligible but seems to be acceptable in the specific paediatric oncology context if radioprotection instructions are met and if optimization of protocols is performed. (authors)

Uranium mining sites of Somair and Cominak (Niger). Situation of mission on site in may 2004, application of radiological impact and advice on the network of environmental surveillance; Sites miniers d'uranium de Somair et Cominak (Niger). Bilan de la mission sur site en mai 2004, appreciation de l'impact radiologique, et avis sur le reseau de surveillance de l'environnement

Energy Technology Data Exchange (ETDEWEB)

Servant, A.C.; Cessac, B.; Bassot, S

2005-07-01

The report presents successively the context of the two mining sites, the situation of the I.R.S.N. mission on site of may 2004, an appreciation by I.R.S.N. of sites impact on the populations, the evaluation by I.R.S.N. of associated impact to generic scenario of scrap recovery from sites by the population around. (N.C.)

Development of mercury porosimeter. Application to nuclear graphite studies (1961); Mise au point d'un porosimetre a mercure. Application a l'etude des graphites nucleaires (1961)

Energy Technology Data Exchange (ETDEWEB)

Bocquet, M; Genisson, J; Sailleau, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1961-07-01

A mercury porosimeter, model IFP-CEA, has been developed for application to nuclear graphite studies. The apparatus is based on the capillary depression phenomenon. The relationship between the radius of a pore and the pressure at which mercury fills it is pr = -2 {sigma} cos {theta} ( {sigma} is the surface tension, {theta} the angle of contact of the mercury). After some theoretical consideration, the apparatus is described. The mercury pressure is increased step-wise from 0 to 1000 kg/cm{sup 2} thus yielding the complete distribution of pores from 92 {mu} to 75 A. Results are, then presented concerning nuclear graphites which show the evolution of the porous structure under the effect of bitumen impregnation. In general, the volume of the large pores decreases while that of the small pores increases. The structure of impregnated products appears to depend to a certain extent on that of the starting materials. It has also been possible to study other products with this porosimeter; the range of measurements possible is such that it may be used for the study of the majority of porous materials. (authors) [French] Un porosimetre a mercure modele IFP-CEA a ete mis au point en vue de son application a l'etude de graphites nucleaires. Le fonctionnement de l'appareil repose sur le phenomene de depression capillaire. On etablit la relation existant entre le rayon r d'un pore et la pression p pour laquelle le mercure peut y penetrer: pr = -2 {sigma} cos {theta} ( {sigma} tension superficielle, {theta} angle de contact du mercure). Apres quelques considerations theoriques, l'appareil utilise est decrit. Il permet de faire varier par palier la pression du mercure entre 0 et 1000 kg/cm{sup 2} et d'etablir ainsi la distribution complete des rayons de pores compris entre 92 {mu} et 75 A. Les resultats d'une etude faite sur des graphites nucleaires sont alors presentes faisant apparaitre l'evolution de la structure poreuse sous l'effet des impregnations au brai. D'une facon

Health problems raised by the elimination of radioactive wastes and nuclear accidents; Problemes sanitaires poses par l'elimination des dechets radioactifs et par les accidents nucleaires

Energy Technology Data Exchange (ETDEWEB)

Jammet, H; Mechali, D; Dousset, M [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1964-07-01

The rapid development of nuclear energy demands an urgent solution to the health problems arising from the discharge into the environment of radioactive residues produced by nuclear installations. - To be able to evaluate the risks run by the population and to fix tolerance limits for waste discharge, it is necessary to possess an exact knowledge of the course taken by the radioelements discharged, from their source until they reach man. The incorporation of radioelements in food cycles is the first risk to take into consideration. The factors involved in all stages of this transmission must be foreseen, whether they concern physical or biological media, because of their continuity and their interdependence. Finally, socio-economic and dietetic data must be collected in order that the risks and tolerance levels estimated are based on concrete and experimental rather than theoretical knowledge. The risk of nuclear accidents in the atomic industry, although very improbable, must be taken into consideration because of the seriousness of their consequences. The health problems arise in the field of professional hygiene on the one hand and in that of public hygiene on the other. In the first field the risk is two-fold and involves irradiation and contamination. The public sphere is reduced essentially to the risk of contamination by radioactive substances accidentally released in the surrounding medium. The health studies to be conducted in this field therefore include research not only on irradiation or contamination therapeutics but also on the transfer of radioelements from the accident site to man, mainly through food cycles, in their physical and in their biological components. Studies of this kind form the basis of decisions in the health field which would have to be taken in the case of an accident. (authors) [French] Le developpement rapide de l'energie nucleaire rend urgente la solution des problemes sanitaires poses par le rejet dans le milieu ambiant des

Progress report: nuclear safety and radiation protection in France in 2005; Rapport annuel: la surete nucleaire et la radioprotection en France en 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

Thermal energy of nuclear origin produced in non-fissile materials (1962); Energie calorifique d'origine nucleaire degagee dans les materiaux non fissiles (1962)

Energy Technology Data Exchange (ETDEWEB)

Naudet, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Millies, P; Berger, J [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1962-07-01

A first part is devoted to the description of the interaction phenomena between elementary particles and material that may be observed during the irradiation process in a nuclear reactor: nuclear reactions due to neutrons, production of gamma rays and absorption of those gamma rays through various processes. In a second part the phenomena producing calorific energy in irradiated material are quantitatively examined. In the third part results are summed up in a formulary. The fourth part presents tables and figures giving to the reader all the numerical values necessary for practical calculations. (authors) [French] Une premiere partie est consacree a l'examen des principaux phenomenes d'interaction des particules avec la matiere qui interviennent lors d'une irradiation dans un reacteur: reactions nucleaires dues aux neutrons, production des rayons gamma et absorption de ces derniers par les divers processus. Une deuxieme partie etudie quantitativement les phenomenes qui conduisent a l'apparition d'energie calorifique dans le materiau irradie. En troisieme partie, un formulaire resume les resultats etablis. Dans une quatrieme partie, des tableaux et des courbes fournissent a l'experimentateur toutes les valeurs numeriques necessaires aux calculs pratiques. (auteurs)

Radon thematic days - Conference proceedings

International Nuclear Information System (INIS)

2011-03-01

This document brings together the available presentations given at the Radon thematic days organized by the French society of radiation protection (SFRP). Twenty five presentations (slides) are compiled in the document and deal with: 1 - General introduction about radon (Sebastien Baechler, IRA); 2 - Survey of epidemiological studies (Dominique Laurier, IRSN); 3 - Dosimetric model (Eric Blanchardon, Estelle Davesne, IRSN); 4 - Radon issue in Franche-Comte: measurement of the domestic exposure and evaluation of the associated health impact (Francois Clinard, InVS); 5 - WHO's (World Health Organization) viewpoint in limiting radon exposure in homes (Ferid Shannoun, OMS); 6 - Radon measurement techniques (Roselyne Ameon, IRSN); 7 - Quality of radon measurements (Francois Bochud, IRA); 8 - International recommendations (Jean-Francois Lecomte, IRSN); 9 - Radon management strategy in Switzerland - 1994-2014 (Christophe Murith, OFSP); 10 - 2011-2015 action plan for radon risk management (Jean-Luc Godet, Eric Dechaux, ASN); 11 - Radon at work place in Switzerland (Lisa Pedrazzi, SUVA); 12 - Strategies of radiation protection optimization in radon exposure situations (Cynthia Reaud, CEPN); 13 - Mapping of the radon potential of geologic formations in France (Geraldine Ielsch, IRSN); 14 - Radon database in Switzerland (Martha Gruson, OFSP); 15 - Radon 222 in taps water (Jeanne Loyen, IRSN); 16 - Buildings protection methods (Bernard Collignan, CSTB, Roselyne Ameon, IRSN); 17 - Preventive and sanitation measures in Switzerland (Claudio Valsangiacomo, SUPSI); 18 - Training and support approach for building specialists (Joelle Goyette-Pernot, Fribourg engineers and architects' school); 19 - Status of radon bulk activity measurements performed between 2005-2010 in public areas (Cyril Pineau, ASN); 20 - Neuchatel Canton experiments (Didier Racine, SENE); 21 - Montbeliard region experience in the radon risk management (Isabelle Netillard, Pays de Montbeliard Agglomeration); 22

Radiation protection measurement techniques and the challenges encountered in industrial and medical environments

International Nuclear Information System (INIS)

2013-01-01

Nowadays everybody is concerned by the use of ionizing radiations for diagnostic and therapy purposes. Radiation protection regulatory requirements are becoming more and more constraining and have an impact on the performance criteria required for measurement systems. The measurement of some radiation protection data requires the use of complex and costly devices, leading to hardly manageable constraints for the users. Do they have to be systematically implemented? How is it possible to reduce, control and optimize the medical exposures using new methodological approaches? During this conference the participants have shed light on some concrete situations and realisations in the environmental, nuclear industry and medical domains. The document brings together 34 presentations (slides) dealing with: 1 - Environmental monitoring and measurement meaning (P.Y. Emidy (EDF)); human radiation protection and measurement meaning (A. Rannou (IRSN)); Eye lens dosimetry, why and how? (J.M. Bordy (CEA)); critical and reasoned approach of the ISO 11929 standard about decision threshold and detection limit (A. Vivier (CEA)); Samples collection and low activities measurement in the environment (D. Claval (IRSN)); Dosemeters calibration, what is new? (J.M. Bordy (CEA)); Appropriateness of measurement means for radiological controls (P. Tranchant (Techman Industrie)); Pulsed fields dosimetric reference for interventional diagnosis (M. Denoziere (CEA)); Pulsed complex fields dosimetry (F. Trompier (IRSN)); DOSEO: a tool for dose optimization in radiological imaging (C. Adrien (CEA)); Eye lens dosimetry (R. Kramar, A. De Vita (AREVA)); Eye lens dosimetry - workers exposure and proper radiation protection practices (I. Clairand (IRSN)); Individual neutrons dosimetry - status of existing standards (F. Queinnec (IRSN)); Complex field neutron spectroscopy: any new tool? (V. Lacoste (IRSN)); Photon mini-beams dosimetry in radiotherapy: stakes and protocols (C. Huet (IRSN)); Reference and

Reports by the Parliamentary Office for scientific and technological assessment. Wednesday, March 16, 2011. Nuclear crisis in Japan - Round table; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Mercredi 16 mars 2011. Crise nucleaire au Japon - Table ronde

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-03-15

A round table brought together members of the French national Assembly and Senate, the French ministers of ecology and of industry, the chairmen of the Nuclear Safety Authority (ASN), of the OECD agency for nuclear energy, of AREVA, of EDF and of the High Committee for transparency and information on nuclear safety, and representatives of the IRSN and of the CEA. Three main topics have been addressed: the present technical configuration of the Fukushima site, the situation at the vicinity of the power station and on the whole Japanese territory, and the possible evolution scenarios

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 23, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 23 mars 2011 a 06 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 23, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 22, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 22 mars 2011 a 06 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 22, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 24, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 24 mars 2011 a 08 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 24, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 20, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 20 mars 2011 a 06 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 20, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 18, 2011, 2:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 18 mars 2011 a 14 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 18, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 21, 2011, 3:00 PM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 21 mars 2011 a 15 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 21, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 25, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 25 mars a 08h00

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 25, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 17 mars 2011 a 06 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 17, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 3:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 17 mars 2011 a 15 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 17, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 19, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 19 mars 2011 a 06 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 19, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 7:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 19 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 16, 2011, at 7:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Health problems raised by the elimination of radioactive wastes and nuclear accidents; Problemes sanitaires poses par l'elimination des dechets radioactifs et par les accidents nucleaires

Energy Technology Data Exchange (ETDEWEB)

Jammet, H.; Mechali, D.; Dousset, M. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1964-07-01

The rapid development of nuclear energy demands an urgent solution to the health problems arising from the discharge into the environment of radioactive residues produced by nuclear installations. - To be able to evaluate the risks run by the population and to fix tolerance limits for waste discharge, it is necessary to possess an exact knowledge of the course taken by the radioelements discharged, from their source until they reach man. The incorporation of radioelements in food cycles is the first risk to take into consideration. The factors involved in all stages of this transmission must be foreseen, whether they concern physical or biological media, because of their continuity and their interdependence. Finally, socio-economic and dietetic data must be collected in order that the risks and tolerance levels estimated are based on concrete and experimental rather than theoretical knowledge. The risk of nuclear accidents in the atomic industry, although very improbable, must be taken into consideration because of the seriousness of their consequences. The health problems arise in the field of professional hygiene on the one hand and in that of public hygiene on the other. In the first field the risk is two-fold and involves irradiation and contamination. The public sphere is reduced essentially to the risk of contamination by radioactive substances accidentally released in the surrounding medium. The health studies to be conducted in this field therefore include research not only on irradiation or contamination therapeutics but also on the transfer of radioelements from the accident site to man, mainly through food cycles, in their physical and in their biological components. Studies of this kind form the basis of decisions in the health field which would have to be taken in the case of an accident. (authors) [French] Le developpement rapide de l'energie nucleaire rend urgente la solution des problemes sanitaires poses par le rejet dans le milieu ambiant des

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:30 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du mardi 15 mars 2011 a 10h30

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 15, 2011, at 10:30 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Controlling safety at all stage of parcel lifetime

International Nuclear Information System (INIS)

Sert, Gilles; Aguilar, Jacques; Clemente, Colette; Sauron, Claire; Labergri, Fabien; Jacob, Emmanuel; Sallit, George; Lourtie, Guy

2012-01-01

This chapter is made of several small articles entitled: - 'L'etude des risques lies aux situations extremes pouvant survenir lors du transport des substances radioactives' (The investigation of risks related to extreme situations which may occur during radioactive material transport); - 'Une necessaire diversification de l'expertise: le role du Groupe permanent d'experts pour les transports' (A required diversification of expertise: the role of the permanent group of experts for transports); - 'Vers un nouveau consensus sur les methodes et les parametres de reference a retenir lors des agrements des modeles de colis destines au transport' (Towards a new consensus on methods and reference parameters to be retained during agreements of models of parcels designed for transport); - 'Le controle de la fabrication des emballages par l'ASN' (Control of packaging manufacturing by the ASN); - 'Concevoir et realiser un emballage destine au transport de substances radioactives: l'exemple de la societe ROBATEL' (Designing and manufacturing a package for nuclear material transport: the example of the ROBATEL company); - 'Les transports internes dans les installations nucleaires de base secretes' (Internal transports within secrete base nuclear installations); - 'Les operations de transport interne sur les sites nucleaires' (Transport operations within nuclear sites); - 'Cooperation entre les Autorites competentes britanniques et francaises en matiere de regulation de la surete du transport des substances radioactives' (Cooperation between British and French Authorities in charge of radioactive material transport safety regulation); - 'Inspections et sanctions en Belgique' (Inspections and sanctions in Belgium). While evoking regulations and research studies, the first article comments the various risks (mechanical and thermal risks, and risks related to radiation leakage) associated with radioactive material transport. In an interview, the chairman of the permanent group of

Coarse-grained molecular dynamics simulation of transport through the nuclear pore complex

NARCIS (Netherlands)

Ghavami, Ali

2014-01-01

Dit proefschrift is gewijd aan het mechanisme van Nucleo - cytoplasmatisch transport openbaren door grofkorrelige moleculaire dynamica simulaties van ontvouwen eiwitten in de nucleaire porie complex (NPC) . NPC's zijn zeer selectief poorten, die alle transporten over nucleaire envelop controleren .

Chernobyl: 30 years after - Proceedings of the technical meeting of the French Society of Radiation Protection

International Nuclear Information System (INIS)

Champion, Didier; Chouha, Michel; Damette, Guy; Durand, Vanessa; Besnus, Francois; Renaud, Philippe; Adam-Guillermin, Christelle; Laurier, Dominique; Chabrier, Patrick; Chauveau, Thomas; Thiry, Yves; Menetrier, Florence; Chevillard, Sylvie; Lesueur, Fabienne; Schneider, Thierry

2016-03-01

The French Society of Radiation Protection (SFRP) organized a technical meeting on the present day situation of the Chernobyl site, 30 years after the accident of the nuclear power plant. The review deals with the situation of the facility and of its safety works, the environment, the management of wastes, the workers and populations exposure, and the health monitoring of the exposed populations. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - The main highlights 30 years after the Chernobyl accident (Didier CHAMPION, SFRP); 2 - Circumstances, progress and consequences of the Chernobyl accident - Lessons and experience feedback for the other RBMK reactors (Michel CHOUHA, IRSN); 3 - Chernobyl, a confinement arch for 100 years (Patrick CHABRIER, Thomas CHAUVEAU - BOUYGUES); 4 - The reactor wastes management and the dismantling operations (Guy DAMETTE - IRSN); 5 - Environment contamination in the vicinity of the site (Yves THIRY - ANDRA); 6 - Impact of the accident on agriculture (Vanessa DURAND - IRSN); 7 - The fate of remediation wastes (Francois BESNUS - IRSN); 8 - Chernobyl fallouts in France (Philippe RENAUD - IRSN); 9 - The ecological consequences of the Chernobyl accident (Christelle ADAM-GUILLERMIN - IRSN); 10 - Results of liquidators and populations exposure (Florence MENETRIER - CEA); 11 - Thyroid cancers monitoring in the Chernobyl area and the role of modifying genetic factors (Fabienne LESUEUR - Institut Curie); 12 - Results of the Chernobyl accident health impact studies (Dominique LAURIER - IRSN); 13 - Impact on populations living condition (Thierry SCHNEIDER - CEPN); 14 - Molecular signature of radiation induced thyroid tumors (Sylvie CHEVILLARD - CEA)

Irradiation and development of the nuclear emulsions exposed to intense fluxes of thermal neutrons with {gamma} rays; Irradiation et developpement des emulsions nucleaires exposees a des flux intenses de neutrons thermiques, accompagnes de rayons {gamma}

Energy Technology Data Exchange (ETDEWEB)

Faraggi, H; Bonnet, A; Cohen, J [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1952-07-01

The thermal neutron fluxes provided by nuclear reactors permit the survey of relatively rare phenomenons, and dosage of very weak quantities of some elements. One of the most favorable detection technique are constituted by the use of the nuclear emulsions. one can mention: - the dosage of uranium by counting in the emulsion the number of traces due to fission fragments after irradiation. - The dosage of the lithium and the boron as trace amounts with the help of nuclear reactions (n, {alpha}) and thermal neutrons. - The research of reactions (n, {alpha}) or (n, p) of very weak cross section for middle or heavy elements. These different applications require however important neutrons fluxes. It had therefore obliged us to search for the most favorable irradiation and development of the emulsions conditions, to get the best visibility of the trajectories and decrease the phenomena of fog on the emulsion, which prevents any observation. (M.B.) [French] Les flux de neutrons thermiques fournis par les reacteurs nucleaires permettent l'etude de phenomenes relativement rares, et le dosage de tres faibles quantites de certains elements. Un des moyens de detection les plus favorables est constitue par l'utilisation des emulsions nucleaires. on peut citer: - le dosage de l'uranium par comptage dans l'emulsion du nombre de traces dues aux fragments de fission apres irradiation. - Le dosage du lithium et du bore a l'etat de traces a l'aide des reactions (n, {alpha}) sous l'action des neutrons thermiques. - La recherche de reactions (n,{alpha}) ou (n,p) de tres faible section efficace pour des elements moyens ou lourds. Ces differentes applications necessite cependant des flux de neutrons important. On a donc ete amene a rechercher les conditions les plus favorables d'irradiation et de developpement des emulsions, de maniere a obtenir la meilleure visibilite des trajectoires et diminuer les phenomenes de voile de l'emulsion, qui empeche toute observation. (M.B.)

Irradiation and development of the nuclear emulsions exposed to intense fluxes of thermal neutrons with {gamma} rays; Irradiation et developpement des emulsions nucleaires exposees a des flux intenses de neutrons thermiques, accompagnes de rayons {gamma}

Energy Technology Data Exchange (ETDEWEB)

Faraggi, H.; Bonnet, A.; Cohen, J. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1952-07-01

The thermal neutron fluxes provided by nuclear reactors permit the survey of relatively rare phenomenons, and dosage of very weak quantities of some elements. One of the most favorable detection technique are constituted by the use of the nuclear emulsions. one can mention: - the dosage of uranium by counting in the emulsion the number of traces due to fission fragments after irradiation. - The dosage of the lithium and the boron as trace amounts with the help of nuclear reactions (n, {alpha}) and thermal neutrons. - The research of reactions (n, {alpha}) or (n, p) of very weak cross section for middle or heavy elements. These different applications require however important neutrons fluxes. It had therefore obliged us to search for the most favorable irradiation and development of the emulsions conditions, to get the best visibility of the trajectories and decrease the phenomena of fog on the emulsion, which prevents any observation. (M.B.) [French] Les flux de neutrons thermiques fournis par les reacteurs nucleaires permettent l'etude de phenomenes relativement rares, et le dosage de tres faibles quantites de certains elements. Un des moyens de detection les plus favorables est constitue par l'utilisation des emulsions nucleaires. on peut citer: - le dosage de l'uranium par comptage dans l'emulsion du nombre de traces dues aux fragments de fission apres irradiation. - Le dosage du lithium et du bore a l'etat de traces a l'aide des reactions (n, {alpha}) sous l'action des neutrons thermiques. - La recherche de reactions (n,{alpha}) ou (n,p) de tres faible section efficace pour des elements moyens ou lourds. Ces differentes applications necessite cependant des flux de neutrons important. On a donc ete amene a rechercher les conditions les plus favorables d'irradiation et de developpement des emulsions, de maniere a obtenir la meilleure visibilite des trajectoires et diminuer les phenomenes de voile de l'emulsion, qui

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 29, 2011, 12:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 29 mars 2011 a 12h00

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 29, 2011, at 12:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 26, 2011, 10:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 26 mars 2011 a 10h00

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 26, 2011, at 10:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 28, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 28 mars 2011 a 08h00

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 28, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Differential measurement of the earth's magnetic field by nuclear magnetic resonance; Mesure differentielle du champ magnetique terrestre par resonance magnetique nucleaire

Energy Technology Data Exchange (ETDEWEB)

Robach, F [Commissariat a l' Energie Atomique, 38 - Grenoble (France). Centre d' Etudes Nucleaires

1967-07-01

MNR transducers using proton dynamic polarisation allows to convert into a phase measurement any variation of the earth magnetic field. There exist several versions of the instrument corresponding to various models of MNR transducers, which the author analyses in detail, devoting an important place to influence of their alignment with respect to the earth's magnetic field. The sensibility obtained is of one hundredth of a gamma over a bandwidth of (0-0,1 Hz). - This instrument is designed for measuring field gradients in airborne magnetic surveying, for detecting nearly magnetic anomalies, and for distinguishing between nearly and distant magnetic phenomena. (author) [French] L'emploi de capteurs, bases sur la resonance magnetique nucleaire des protons en presence de polarisation dynamique, permet de traduire une difference de champ magnetique terrestre en une mesure de phase. L'appareil existe sous plusieurs versions avec des capteurs de modeles differents dont l'auteur fait une analyse detaillee en accordant une part importante a l'influence de l'orientation des capteurs par rapport au champ magnetique terrestre. La sensibilite est de 1/100 {gamma} pour une bande passante de (0 - 0,1 Hz). Cet appareil s'applique a la mesure du gradient en prospection magnetique aeroportee, a la detection d'anomalies magnetiques proches, a la differentiation d'effets magnetiques proches et lointains. (auteur)

High committee for nuclear safety transparency and information. September 23, 2008 meeting; Haut comite pour la transparence et l'information sur la securite nucleaire. Reunion du 23 septembre 2008

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-09-15

The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 6 main points: 1 - the terms of the High Committee operation and the internal rules for the meetings; 2 - the plutonium imports and transportation between Great Britain and France (contracts status, ship safety report, plutonium grade, return of plutonium-derived wastes): hearing of Areva, of the general direction of infrastructures, transports and sea (DGITM), of Greenpeace organisation, debate; 3 - the follow-up of the July 7, 2008 incident at the Socatri facility (Tricastin site (France)) where the overflow of a storage tank led to the spillage of a uraniferous solution on the ground: hearing of Areva (remedial action, re-start up of the facility, environmental monitoring, communication and transparency), hearing of the nuclear safety authority (ASN), of the institute of radiation protection and nuclear safety (IRSN), of the local commission of information (CIGEET), of the hygiene, safety and labour conditions committee (CHSCT) of Socatri company, of the direction of civil safety (DSC), debate about the information dissemination around this incident; 4 - Opinion of the High Committee about the plutonium transportation between Great Britain and France, and about the Socatri incident; 5 - referral to the High Committee of the radioecological follow up of all nuclear sites and of the quality of the information given to the public: ASN's reports about the radioecological follow-up of surface and ground waters and of the ancient radioactive waste storage sites, ASND's answer (Nuclear safety authority of defense), IRSN

Neutron Fluence and Energy Reconstruction with the LNE-IRSN/MIMAC Recoil Detector MicroTPC at 27 keV

Energy Technology Data Exchange (ETDEWEB)

Maire, D.; Lebreton, L.; Querre, Ph. [Institute for Radioprotection and Nuclear Safety - IRSN, site of Cadarache, 13115 Saint Paul lez Durance (France); Bosson, G.; Guillaudin, O.; Muraz, J.F.; Riffard, Q.; Santos, D. [Laboratoire de Physique Subatomique et de Cosmologie - LPSCCNRSIN2P3/ UJF/INP, 38000 Grenoble (France)

2015-07-01

The French Institute for Radiation protection and Nuclear Safety (IRSN), designated by the French Metrology Institute (LNE) for neutron metrology, is developing a time projection chamber using a Micromegas anode: microTPC. This work is carried out in collaboration with the Laboratory of Subatomic Physics and Cosmology (LPSC). The aim is to characterize the energy distribution of neutron fluence in the energy range 8 keV - 5 MeV with a primary procedure. The time projection chambers are gaseous detectors able to measure charged particles energy and to reconstruct their track if a pixelated anode is used. In our case, the gas is used as a (n, p) converter in order to detect neutrons down to few keV. Coming from elastic collisions with neutrons, recoil protons lose a part of their kinetic energy by ionizing the gas. The ionization electrons are drifted toward a pixelated anode (2D projection), read at 50 MHz by a self-triggered electronic system to obtain the third track dimension. The neutron energy is reconstructed event by event thanks to proton scattering angle and proton energy measurements. The scattering angle is deduced from the 3D track. The proton energy is obtained by charge collection measurements, knowing the ionization quenching factor (i.e. the part of proton kinetic energy lost by ionizing the gas). The fluence is calculated thanks to the detected events number and the simulation of the detector response. The μTPC is a new reliable detector able to measure energy distribution of the neutron fluence without unfolding procedure or prior neutron calibration contrary to usual gaseous counters. The microTPC is still being developed and measurements have been carried out at the AMANDE facility, with neutrons energies going from 8 keV to 565 keV. After the context and the μ-TPC working principle presentation, measurements of the neutron energy and fluence at 27 keV and 144 keV are shown and compared to the complete detector response simulation. This work

Transport safety and struggle against malevolent acts: a synergy to be developed - Protecting transports against malevolent acts, Synergies between security and safety: lessons learned from the IAEA international conference, Role of the IRSN transport operational level in the field of safety, Transparency and secret in the field of nuclear material transport

International Nuclear Information System (INIS)

Riac, Christian; Flory, Denis; Loiseau, Olivier; Mermaz, Frederic; Demolins, Laurent

2012-01-01

The first article proposes an interview with the chief of the security department within the French ministry of Ecology, Sustainable Development, Transports and Housing who comments his missions and his relationships with the ASN and the French Home Office for the protection and control of nuclear materials. A second article discusses the lessons learned from an IAEA international conference about the relationship between the approaches to security and to safety. The third article briefly describes the role of the IRSN transport operational level in the field of safety. The last article discusses how opposite notions like transparency and secret are managed in the case of nuclear material transport

From Crex mutualization to clinical audit; De la mutualisation des comites de retour d'experience (Crex) a l'audit des pratiques cliniques

Energy Technology Data Exchange (ETDEWEB)

Debouck, F. [Departement securite operationnelle, Air France Consulting, 95 - Roissy-CDG (France); Petit, H.B. [AFM42, 78 - Chambourcy (France); Lartigau, E. [Centre Oscar-Lambret, departement universitaire de radiotherapie, 59 - Lille (France); Universite Lille Nord-de-France, 59 - Lille (France)

2010-10-15

In mid-2004, following a Mission nationale d'expertise et d'audits hospitaliers (MeaH) proposal, three voluntary cancer centres started setting up a safety procedure in radiotherapy. Their work made it possible to single out the need to continue elaborating a repository, aiming at a 'minimal written reference', to take into account the human factor as one of the four families of factors contributing to a systemic deviation and to build collectively, in radiotherapy departments, the experience feedback committee (comite de retour d'experience [Crex]). Formalizing a comite de retour d'experience is unavoidable in any safety-management system (SMM or MGS). The comite de retour d'experience enables every active member of a department to listen to any of the events of the month (incidents and precursors), to select the event which will be under scrutiny for the next systemic analysis (Orion{sup C} method) and above all to choose the most appropriate correcting action and ensure its proper implementation. That approach has been approved and then acknowledged by the Autorite de surete nucleaire (ASN) before being extended to the other radiotherapy departments. The use of the comite de retour d'experience, which is a safety management tool, should not be limited to a local circle of insiders, but shared to benefit everybody. Putting comite de retour d'experience together - a move that was hoped for and brought up as soon as the tool was created - is now being implemented. Several initiatives have already permitted to assess its collective interest; other steps have yet to be taken to enable a true collective sharing of experience. On this basis, the definition of quality/safety practices in radiotherapy will allow the professionals to implement clinical audits in 2012. (authors)

Study of the thermal and mechanical behaviour of granite applied to the nuclear waste repository: conclusions drawn from the Fanay-Augeres experiment

International Nuclear Information System (INIS)

Rejeb, A.; Vouille, G.; Gros, J.C.

1993-01-01

The considerable advances made in nuclear technology in recent years have brought with them a sizeable accumulation of nuclear waste. Leaving aside the low-activity wastes which are stored at ground level, the problem of high-activity wastes still remains. A concerted research effort has been dedicated to perfecting certain methods for waste disposal. At present, this effort has been directed towards evaluating feasibility and the long-term safety of burying these wastes in deep-lying and stable geological repositories. A priori, many types of rocks are suitable for isolating nuclear wastes: clay, salt, granite, schists, basalt and tuff. These wastes are exothermic owing to their radioactive decay which decreases continuously with time. From the geotechnical point of view, storage of these high-activity wastes in a deep-lying geological environment will increase temperature in the host rock accompanied by changes in stresses and strains. Quantifying these changes, by means of a thermomechanical analysis, is of prime importance when the mechanical behaviour of the storage drifts has to be ensured by avoiding major modifications to the characteristics of the geological barrier. This article summarises the present state of knowledge acquired about the thermomechanical behaviour of granite, and presents the results as research requirements for better characterisation in the laboratory and in situ as well as a more realistic model. We also stress the results of research carried out by the Centre de Geotechnique et d'Exploitation du sous-sol (CGES) of the Ecole des Mines de Paris (ENSMP) on the Fanay-Augeres Thermal, Hydraulic and Mechanical experiment organised by the Institut de Protection et de Surete Nucleaire (IPSN) in the context of a shared-costs contract with the Commission of the European Communities (CEC). (authors). 4 figs., 10 refs

Status results of an annual campaign of continuous measurement of air radioactivity in Novozybkov, Briansk region. Recent data of a Russian-French study

International Nuclear Information System (INIS)

Petrov, E.; Zaboudko, A.; Seldiakov, Y.; Fertman, D.; Rizin, A.; Chemtob, M.; Charuau, J.; Sabroux, J.C.; Grivaud, L.; Fazileabasse, J.

1996-01-01

At the request of the Association of Radiological Problems of Russia (ARPR), in charge of environmental measurements and clean up of contaminated territories by Chernobyl accident, an instrument measuring continuously the radioactivity of aerosols in the environment was installed and operated for demonstration during a complete annual cycle in NOVOZYBKOV, Briansk Region (RUSSIA), in order to determine locally residual atmospheric contamination. This measuring campaign was carried out using the so called RADAIR instrument. This campaign was organised in the framework of a Russian -French cooperation between IPPE (Institute of Physics and Power Engineering, OBNINSK), SEC-SNIIP (Scientific and Engineering Center 'SNIP', MOSCOW), IPSN (Institut de Protection et de Surete Nucleaire, Fontenay-aux-Roses) and MGP-Instruments (LAMANON). The first step of the operation consisted in a preliminary verification of the instrument calibration in the site using aerosols sources deposited on filters. This calibration carried out on specialized facilities of IPSN and SEC-SNIIP showed a satisfactory agreement between different results. The second step consisted in exploiting the instrument. Beside the demonstration that the instrument worked suitably during its continuous operation in variable climatic conditions, the results obtained showed: - that the indicated volume activities of α and β emitters were low and near the instrument minimum values (for a: 4.10 -3 Bq.m -3 and for β: 10 -1 Bq.m -3 ); - that the indicated volume activities of 222 Rn lie between 2 and 30 Bq.m -3 (the high values are obtained in favourable climatic conditions: no wind, no rain or snow, soil not covered by snow and not frosted, etc.); - that the indicated environmental dose rate values at the point of measurement were of the order of 0.15 μGy.h -1 (150 μGy.h -1 ). (author)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011 (15 mars 2011 - point a 22h00 heures)

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 15, 2011, at 10:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 9:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 9 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 16, 2011, at 9:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 2:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 14 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 16, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of all 6 reactors of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

Very high temperature measurements: Applications to nuclear reactor safety tests; Mesures des tres hautes temperatures: Applications a des essais de surete des reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Parga, Clemente-Jose

2013-09-27

This PhD dissertation focuses on the improvement of very high temperature thermometry (1100 deg. C to 2480 deg. C), with special emphasis on the application to the field of nuclear reactor safety and severe accident research. Two main projects were undertaken to achieve this objective: - The development, testing and transposition of high-temperature fixed point (HTFP) metal-carbon eutectic cells, from metrology laboratory precision (±0.001 deg. C) to applied research with a reasonable degradation of uncertainties (±3-5 deg. C). - The corrosion study and metallurgical characterization of Type-C thermocouple (service temp. 2300 deg. C) prospective sheath material was undertaken to extend the survivability of TCs used for molten metallic/oxide corium thermometry (below 2000 deg. C)

Challenges for the nuclear safety of the deregulation of electricity markets; Defis pour la surete nucleaire de la dereglementation des marches de l'electricite

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Eurosafe 2000 was organised around two round tables on the first day and four seminars on the second day. The first round table dealt with general aspects of deregulation including the economic constraints and the special challenges arising during transition from regulated to deregulated structures. The second round table focussed on technical and organisational safety issues which are directly or indirectly related to the changes introduced by deregulation. The four seminars hold in order to provide opportunities for comparing experiences and learning about recent activities of IPSN, GRS and their partners in the European Union and Eastern Europe: Seminar 1 (Nuclear installation safety, assessment and analysis): assessment of the flooding incident at the Blayais nuclear power plant; PSA data base, comparison of the French and German approach; assessment of the Balakovo fire probabilistic study and elaboration of a guide for reviewing fire PSA; comprehensive technical assessment of an advanced German PWR by PSA - objectives and main results; PSA approach for the safety assessment of low-power and shutdown states; correlation of initiating events with the PSA level-2 results; safety assessment for fission products tests in the Phebus reactor; use of NPP simulators for applied human factor studies; assessment of the 'deterministic realistic method' applied to large LOCA analysis; assessment of the feasibility of an improvement programme enabling operation of units 3 and 4 of Kozloduy nuclear power plant. Seminar 2 (nuclear installation safety, research): PHEBUS 2K project on severe accidents; current status of the COCOSYS development; fission product modeling in ASTEC; Euratom Framework Programme (FP) research in reactor safety: main achievements of FP- 4 (1994-1998), some preliminary results of FP-5 (1998-2002) and prospects for beyond 2002; development of coupled systems of 3D neutronics and fluid-dynamic system codes and their application for safety analyses. Seminar 3 (environment and radiation protection): implementations of the variability in critical group doses for the control of radionuclides releases; campaign of environmental radioactivity measurements in the vicinity of La Hague made by European mobile laboratories - both a technical and sociological experience; contribution of some leading radioprotection societies to the current considerations with regard to the possible improvement of the ICRP policy system; decommissioning and dismantling of nuclear power plants: radiation protection experience in Germany; epidemiology of French nuclear workers within the IARC study. Seminar 4 (waste management): the Mont Terri rock laboratory, Switzerland; prediction of hydro-mechanical responses of a long-term pump test at the Sellafield site; modelling of water-rock interactions in deep ground-waters: equilibrium and perturbations; modelling of saturation and swelling effects in clays under different saline conditions; qualification of clay barriers in underground repository systems; integrating structural, hydraulic and geochemical evidence: a step towards understanding fluid flow through clay-rich formations; application of geostatistical methods to long-term safety analyses for radioactive waste repositories; major results and lessons learned from performance assessments on spent fuel geological disposal: the SPA project; repository incidents in Germany and abroad: what can be learnt; progress in the Chernobyl decommissioning and waste management strategy. (J.S.)

Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA; Evaluation complementaire de la surete des installations nucleaires de base - Site du Tricastin - AREVA

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

Europe's progress towards joint regulation of nuclear safety; Le cheminement de l'Europe vers une reglementation commune sur la surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

Hennenhofer, G. [surete des installations nucleaires et la radioprotection, Ministere de l' Environnement, de la Protection de la nature et de la securite nucleaire (BMU) (Germany)

2010-11-15

Following the end of the Second World War, there was great hope for the use of nuclear energy for peaceful applications. In the beginning, the different approaches adopted by East and West led to the design of different types of reactors, with priority being given to rapid development of the reactor fleet. Cooperation between safety regulators only came about very gradually. The Chernobyl disaster was in this respect the trigger event, as it clearly showed that the effects of nuclear events do not stop at borders and that collaboration by the safety regulators in this field was essential. Texts such as the Convention on Nuclear Safety, requiring the creation of a regulatory body independent of economic interests, the other work done by IAEA on the issue of nuclear safety and, within the European context, the creation of WENRA, are all milestones along the path to close cooperation. The recently adopted European directive on the safety of nuclear installations is the natural successor to these achievements. The road to a common European vision of nuclear safety is now mapped out. Germany will be joining this movement and making its own contribution. (author)

Life scientists in the nuclear domain

International Nuclear Information System (INIS)

Guetat, Philippe; Egal, Yves; Wolf, Gerard; Fleuriot, Sabine; Van Hecke, Walter; Coulon, Remi; Seilhean-Frossard, Estelle; Sevin, Helene; Schoulz, Daniel; Lebaron-Jacobs, Laurence; Menetrier, Florence; Crochon, Philippe; Buchholzer, Vincent; Chagvardieff, Pierre; Camus, Henri; Raynaud, Jacques; Biet, Elodie; Mathis, Paul

2011-01-01

This dossier is made of several small articles entitled: - 'Exploite intelligemment, le nucleaire n'est pas dangereux' (Exploited smartly, nuclear is not dangerous); - 'l'amont du cycle du combustible nucleaire' (the upstream part of the nuclear fuel cycle); - 'Le nucleaire, une energie recyclable' (Nuclear, a recyclable energy); - 'Centrale nucleaire et environnement - exemple de Cattenom' (Nuclear power station and the environment - the example of Cattenom); - 'Ingenieur environnement, un metier exigeant' (Engineer in environment, a demanding profession); - 'Rayonnements ionisants: a quels risques sommes-nous exposes?' (Ionizing radiations: to which risks are we exposed?); - 'Les anciennes mines d'uranium, un sujet toujours d'actualite' (Old uranium mines: a topic always of actuality); - 'Les dechets nucleaires, des dechets comme les autres?' (Nuclear wastes: wastes like others?); - 'Les Ingenieurs du Vivant dans le nucleaire' (Engineers in life sciences in the nuclear sector); - 'Tchernobyl: 25 ans apres, quel impact sur la sante?' (Chernobyl: 25 years after: which impact on health?); - 'Fukushima, catastrophe naturelle ou accident nucleaire?' (Fukushima, natural disaster or nuclear accident?); - 'Rehabiliter les sols contamines' (Restoring contaminated soils); - 'Nucleaire et risque de proliferation' (nuclear and risk of proliferation); - 'Les rayonnements dans la lutte contre le cancer' (Radiations in the struggle against cancer); - 'L'energie nucleaire est-elle essentielle a notre bouquet energetique?' (Is nuclear energy essential to our energy mix?). The articles of this dossier outline that nuclear energy can be exploited without any danger if it is done intelligently, describes the upstream part of the nuclear fuel cycle, outlines that most of the nuclear fuel can be recycled, presents the activities of survey and control of the environment around a French nuclear power station, outlines the high commitment required for and engineer in environment working

The atomic energy course of the 'Institut National des Sciences et Techniques nucleaires' at the centre d'Etudes Nucleaires at Saclay; L'enseignement de genie atomique de l'Institut national des Sciences et Techniques nucleaires au Centre d'Etudes nucleaires de Saclay

Energy Technology Data Exchange (ETDEWEB)

Baissas, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

foreign students. 8- Annexe: list of courses, practical work, pile projects drawn up by the 1957 students. (author)Fren. [French] 1- Les raisons de sa creation. L'electricite de France et l'industrie interessee par le developpement de l'Energie atomique ont demande au Commissariat a l'Energie atomique de former des ingenieurs capables d'etudier des projets de piles et de diriger leur construction. 2- Recrutement et Droits d'inscription. Les demandes d'inscription ont toujours depasse les possibilites. Cette annee, les cours sont suivis par 74 eleves permanents, dont 20 etrangers, et une centaine d'auditeurs libres. Tous les elevont deja ingenieurs ou nantis de grades universitaires eleves. Droit d'inscription: 250 000 F pour les eleves, 125 000 F pour les auditeurs. 3- Organisation de l'Enseignement. II comprend deux options: physique et chimie et dans chaque option: une centaine de conferences, une trentaine de travaux pratiques, des stages dans les services, l'etude d'un projet de reacteur par un groupe de 4 ou 5 eleves. L'ensemble occupe l'annee universitaire du 1 novembre au 14 juillet. 4- Sanction. Un examen final combinant les notes de deux epreuves theoriques, des travaux pratiques, du stage, et du projet conduit a un diplome d'ingenieur en genie atomique. Il n'est pas cree en realite de nouveaux ingenieurs; une mention nouvelle est seulement ajoutee a un diplome deja acquis. Les resultats ont toujours ete excellents. Le pourcentage des echecs est tres faible. 5- Placement des Diplomes. Ils reviennent tous dans leurs industries d'origine qui ont paye leurs salaires et les droits d'inscription en se privant de leurs services pendant les neuf mois de duree des cours. 6- Creations analogues. Un cours analogue a ete cree au Centre d'Etudes Nucleaires de Grenoble. Tandis que celui de SACLAY s'adresse plus specialement aux ingenieurs deja en fonctions, celui de Grenoble est, en principe, destine aux jeunes ingenieurs sortant des ecoles. 7- Conclusion. L

Optimal sizes and siting of nuclear fuel reprocessing plants; Tailles et localisations optimales des usines de retraitement des combustibles nucleaires

Energy Technology Data Exchange (ETDEWEB)

Thiriet, L; Deledicq, A [Commissariat a l' Energie Atomique, Siege (France). Centre d' Etudes Nucleaires

1967-07-01

The expansion of a nuclear economy entails the development of fuel process and reprocessing plant programmes. The model proposed makes it possible to select the size, the site and the start-up schedule of the plants in such a way as to minimize the total freight and reprocessing costs. As an illustration, we have approached the problem of burnt natural uranium processing plants related to natural uranium-graphite as nuclear power stations. The sites and annual output of the reactors, the possible plant sites and cost functions (freight and reprocessing) are supposed to be known. The method consists in first approaching the process plant problem as a Dynamic Programming problem, increasing programme slices (total reactor output) being explored sequentially. When the quantities of burnt natural uranium to be reprocessed are fixed, the minimization of the transport cost is then also carried out as a dynamic programming problem. The neighbourhood of the optimum process cost is explored in order to find the minimum summation of a suboptimal processing cost and corresponding optimal transport cost. As the reprocessing problem can be represented on a sequential graph, in order to compute the sub-optima, we developed and used a 'reflexion algorithm'. The method can be interpreted as a general mechanism for determining the optimum when to a sequential dynamic problem (for example an equipment programme) is added a complementary problem (transport, for instance). It also makes it possible to estimate the economic losses which result from the choice of a non optimal policy for other than economic reasons. (author) [French] L'expansion de l'economie nucleaire se traduit par un developpement des programmes d'usines d'elaboration et de retraitement des combustibles. Le modele propose permet de choisir la taille, la localisation et la cadence de mise en service des usines de maniere a minimiser le total des frais de transport et de retraitement. A titre d'exemple nous avons

Contribution to the study of the evolution of radiation induced He in Be O; Etudes sur l'evolution de l'helium produit par reactions nucleaires dans l'oxyde de beryllium

Energy Technology Data Exchange (ETDEWEB)

Bareau, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1966-11-15

The purpose of this work in-pile investigation of He formed by (n, 2n) and (n, {alpha}) nuclear reactions, released from irradiated BeO, in the temperature range 1000 - 1350 deg. C. The experimental results show that, for an instantaneous neutron fast flux of 10{sup 13} n cm{sup -2} sec{sup -1}, an equilibrium is attempted, after several days, for a part lower than 20 per cent of the quantity of He formed, theoretically calculated from the neutron cross sections of nuclear reactions, and from the analytical form of the neutron fast flux, releases from the solid. The validity of the values of calculated helium and the gas chromatographic analytical method are also verified by dissolution of the BeO pellets in cryolite. A new fast neutron flux measuring method may be so defined. The discussion of the experimental results enables to establish that the processus of He release is characterized by two phenomena: the first one which controls the release of He atoms out of the solid and the second which reveals a capture processus, connected to the irradiation and probably due to the vacancies induced in the lattice. (author) [French] On etudie en pile le degagement de l'helium forme par reactions nucleaires (n, 2 n) et (n, {alpha}) dans l'oxyde de beryllium irradie entre 1000 et 1350 deg. C. Les resultats experimentaux montrant que, pour un flux rapide instantane de 10{sup 13} n{sub r} cm{sup -2} s{sup -1}, on aboutit, au bout de quelques jours, a un etat d'equilibre pour lequel une partie, inferieure a 20 pour cent de la quantite d'helium forme, calculee theoriquement a partir des sections efficaces des reactions nucleaires et de la forme analytique du flux rapide, s'echappe du solide. On verifie egalement par dissolution des echantillons de BeO dans la cryolithe la validite du calcul de l'helium et de la methode de dosage par chromatographie en phase gazeuse. On peut ainsi definir une methode nouvelle de mesure des flux rapides. La discussion des resultats experimentaux

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 3:30 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 15 mars 2011 a 15h30

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 15, 2011, at 3:30 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

A study of the fluorescence of the rare gases excited by nuclear particles. Use of the principle for the detection of nuclear radiation by scintillation; Etude de la fluorescence des gaz rares excites par des particules nucleaires. Utilisation pour la detection des rayonnements nucleaires par scintillation

Energy Technology Data Exchange (ETDEWEB)

Koch, L [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-12-15

composantes, l'une tres breve due a la desexcitation directe du gaz rare, l'autre relativement plus lente, due au transfert d'energie sur les impuretes. La mesure des durees de vie des etats excites a confirme l'hypothese precedente, la partie breve de l'impulsion est extremement courte: inferieure a 2,25.10{sup -9} s dans le cas du xenon, la partie plus lente a une duree qui depend etroitement de la concentration d'azote, l'azote etant l'impurete dont le role est preponderant dans tous les cas. L'etude des gaz rares soumis a un champ electrique a permis de montrer que la quantite de lumiere produite par une particule {alpha} peut etre multipliee (par 60 dans un champ de 600 V/cm par exemple) ce qui correspond a un rendement de luminescence superieur a celui de INa TI. Dans la deuxieme partie on a etudie les caracteristiques des gaz rares comme scintillateurs, la plus importante est l'absence de saturation de la fluorescence lorsque la densite d'excitation transmise au gaz devient tres grande. Ceci joint au temps de scintillation tres court a permis d'etudier un certain nombre d'applications a la physique nucleaire (mesure d'energie des particules lourdes, etude cinetique des reacteurs nucleaires, spectroscopie des neutrons...). (auteur)

Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident (ROBELSYS). Workshop Proceedings, Paris, France, 1-4 April 2014 - Robustness of Electrical Systems of NPP's in Light of the Fukushima Daiichi Accident. ROBELSYS Workshop Proceedings

International Nuclear Information System (INIS)

2015-01-01

The March 2011 accident at Fukushima Daiichi triggered discussions about the significance of electrical power hazards and their treatment in safety analyses. In order to address these issues and provide relevant conclusions and recommendations to CSNI and CNRA, the Robustness in Electrical Systems (ROBELSYS) Technical Working Group was established in 2012 under the leadership of the Institut de Radioprotection et de Surete Nucleaire (IRSN) of France. The purpose of the ROBELSYS Technical Working Group was to organize an international workshop to identify and discuss the lessons learned from the Fukushima Daiichi accident. The workshop was focused on the provisions taken by various countries concerning national requirements and modifications to the plant designs in order to enhance the robustness of electrical systems, especially the protection against extreme external hazards. The ROBELSYS workshop was held at the OECD Conference Centre in Paris in April 1-4, 2014. A total of 105 participants attended the workshop representing industry and government organisations from 25 countries, as well as international organisations. A total of 34 technical presentations were given in seven sessions as follows: - 1: National Programmes on Evolution of Onsite and Offsite Electric Power Systems; - 2: Role of Electric Power in Severe Accident Management; - 3: Requirements for Robustness of Onsite Electric Power Systems; - 4: Simulation of Transients within NPP Plant Distribution Systems; - 5: Requirements for Equipment Used for Emergency Response; - 6: Margin Assessments for Modern Power Electronics; - 7: Digital Components in Power Systems. Items addressed in the workshop included: - Review of the lessons learned from the Fukushima accident concerning the robustness of electrical systems; - Review of the provisions already taken or planned after the Fukushima accident, regarding the sources, the distribution systems and the loads, and documenting the technical basis for these

Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident (ROBELSYS). Workshop Proceedings, Paris, France, 1-4 April 2014. Appendix 2 (Cont'd) and Appendix 3 - Robustness of Electrical Systems of NPP's in Light of the Fukushima Daiichi Accident. ROBELSYS Workshop Proceedings. Appendices 2 and 3

International Nuclear Information System (INIS)

2015-01-01

The March 2011 accident at Fukushima Daiichi triggered discussions about the significance of electrical power hazards and their treatment in safety analyses. In order to address these issues and provide relevant conclusions and recommendations to CSNI and CNRA, the Robustness in Electrical Systems (ROBELSYS) Technical Working Group was established in 2012 under the leadership of the Institut de Radioprotection et de Surete Nucleaire (IRSN) of France. The purpose of the ROBELSYS Technical Working Group was to organize an international workshop to identify and discuss the lessons learned from the Fukushima Daiichi accident. The workshop was focused on the provisions taken by various countries concerning national requirements and modifications to the plant designs in order to enhance the robustness of electrical systems, especially the protection against extreme external hazards. The ROBELSYS workshop was held at the OECD Conference Centre in Paris in April 1-4, 2014. A total of 105 participants attended the workshop representing industry and government organisations from 25 countries, as well as international organisations. A total of 34 technical presentations were given in seven sessions as follows: - 1: National Programmes on Evolution of Onsite and Offsite Electric Power Systems; - 2: Role of Electric Power in Severe Accident Management; - 3: Requirements for Robustness of Onsite Electric Power Systems; - 4: Simulation of Transients within NPP Plant Distribution Systems; - 5: Requirements for Equipment Used for Emergency Response; - 6: Margin Assessments for Modern Power Electronics; - 7: Digital Components in Power Systems. Items addressed in the workshop included: - Review of the lessons learned from the Fukushima accident concerning the robustness of electrical systems; - Review of the provisions already taken or planned after the Fukushima accident, regarding the sources, the distribution systems and the loads, and documenting the technical basis for these

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 12, 2011, 8:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur servenu le 11 mars 2011. Point de situation du 12 mars 2011 a 20 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 12, 2011, at 8:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2 and 3 of the Fukushima I site is briefly presented with the progress of the accident management actions. The operation principles of a BWR-type reactor and of a PWR-type reactor are presented in appendix as well as the confinement principle specific to Mark I-type BWR reactors designed by General Electric. The meteorological forecasts of the day are presented in a figure. (J.S.)

Spectral content of seismic movements produced by underground nuclear explosions; Contenu spectral des mouvements seismiques dus aux explosions nucleaires souterraines

Energy Technology Data Exchange (ETDEWEB)

Albaret, A; Duclaux, F [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

1969-07-01

After a summary of available data, both theoretical and experimental, concerning the spectral content of seismic movements, a description is given of the experiments carried out during the French nuclear explosions in the Sahara, and of the results obtained on the volume waves. A comparison is then made with certain American results. A new method is described for studying the amplitude spectra; it has made it possible to show that the amount of low frequencies in the spectrum increases with the power of the explosion, and decreases with the distance to the zero point and with the filtering effect of the weathered zone. A calculation is then made of the low cut-off ground filter, this giving a better representation of the initial seismic phenomenon. (authors) [French] Apres avoir resume les connaissances disponibles, aussi bien theoriques qu'experimentales, sur le contenu spectral des mouvements seismiques, on decrit les experiences effectuees a l'occasion des explosions nucleaires francaises du Sahara et les resultats obtenus sur les ondes de volume. Puis on les compare avec certains resultats americains. On decrit une nouvelle methode d'etude des spectres d'amplitudes qui montre que le spectre est d'autant plus riche en basses frequences que la puissance de l'explosion est grande, que la distance au point zero est faible et qu'il est moins filtre par la zone alteree superficielle. Puis on calcule le filtre terrain coupe-bas qui permet de donner une representation plus fidele du phenomene seismique initial. (auteurs)

Situation of the surveillance of radioactivity in French Polynesia in 2006. results of the I.R.S.N. 's surveillance network

International Nuclear Information System (INIS)

2007-01-01

The 543 atmospheric nuclear tests released radionuclides that have deposited themselves throughout the world. The Environmental Study and Surveillance Laboratory, 'Laboratoire d etude et de suivi de l environnement' (L.E.S.E.) of the Institute of nuclear safety and radiation protection (I.R.S.N.), takes part, for more than 35 years, in the evaluation of the dosimetric consequences of these atmospheric depositions, especially those originating with the 41 tests realized in the territory of French polynesia from 1966 to 1974. This laboratory is established in Tahiti. The ingestion component of this dosimetric evaluation requires to collect the most representative samples of the feed ration of the Polynesians living in the 5 archipelagoes of this territory. These samples belong to the marine environment of full sea, the lagoon environment and the terrestrial environment. Certain samples of the physical environment are also taken (air, water). 388 samples are measured by Hp-Ge low background gamma spectrometry in order to be able to characterize lowest possible radioactivity levels. The levels of activity of Pu isotopes and 90 Sr are also given for 50 selected samples and tritium activities for 14 water samples. Moreover, 101 soil samples were measured by gamma spectrometry to update the external dose due to 137 Cs deposition. During the year 2006 results fall under the continuity of a regular reduction in the levels of radioactivity since the stop, in 1974 of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity, estimated from the base of these measurements, is lower than 6 μSv by year (this maximum is obtained for the adults of the Gambiers archipelago). This value corresponds to less than 1% of exposure due to natural radioactivity in Polynesia (approximately 1 milli Sv). this value is of the same order with the estimates made for the previous years. (N.C.)

Situation of the surveillance of radioactivity in French Polynesia in 2007. Results of the I.R.S.N. 's surveillance network

International Nuclear Information System (INIS)

2008-01-01

The 543 atmospheric nuclear tests released radionuclides that have deposited themselves throughout the world. The Environmental Study and Surveillance Laboratory, 'Laboratoire d etude et de suivi de l'environnement' (L.E.S.E.) of the Institute of nuclear safety and radiation protection (I.R.S.N.), takes part, for more than 35 years, in the evaluation of the dosimetric consequences of these atmospheric depositions, especially those originating with the 41 tests realized in the territory of French polynesia from 1966 to 1974. This laboratory is established in Tahiti. The actualized dosimetric evaluation due to the foodstuff ingestion requires to collect the most representative samples of the feed ration of the Polynesians living in the 5 archipelagoes of this territory. These samples belong to the marine environment of full sea, the lagoon environment and the terrestrial environment. Certain samples of the physical environment are also taken (air, water). 355 samples collected in 2007 are measured by Hp-Ge low background gamma spectrometry in order to be able to characterize lowest possible radioactivity levels. The levels of activity of Pu isotopes and 90 Sr are also given for 50 selected samples and tritium activities for 20 water samples. After a period of regular decay of radioactivity after the stop, in 1974, of the French atmospheric tests, the radiological state observed in the year 2007 is the same of that of the recent previous years, at a very low level. for example, the 137 Cs rate in the polynesian air is ten times lower than the parisian rate. In fact, the residual radioactivity essentially relates to 137 Cs, the only artificial radionuclide still measurable in the archipelago. In term of additional dose, this artificial and residual radioactivity is lower than 6 μSv by year. this value corresponds to less than 1% of exposure due to natural radioactivity in Polynesia (approximately 1 milli Sv). (N.C.)

Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Communication recue de la mission permanente du Bresil concernant les Directives de certains Etats Membres applicables a l'exportation de matieres, d'equipements et de technologie nucleaires

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-12-03

The Agency has received a Note Verbale from the Permanent Mission of Brazil, dated 22 March 2007, in which it requests that the Agency circulate to all Member States a letter of 12 December 2006 from the Chairman of the Nuclear Suppliers Group, Ambassador Jose Artur Denot Medeiros, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [French] L'Agence a recu une note verbale de la mission permanente du Bresil, en date du 22 mars 2007, lui demandant de diffuser a tous les Etats Membres une lettre du 12 decembre 2006 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Artur Denot Medeiros, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Chypre, Croatie, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraine. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

Radiological protection of workers. The IRSN proposes new functionalities to the users of the national information system for the radiological follow-up of workers exposed to ionizing radiations (SISERI)

International Nuclear Information System (INIS)

Portes, Pascale

2014-01-01

After a brief definition of the SISERI (national information system for the radiological follow-up of workers exposed to ionizing radiations) and of its new arrangements introduced in 2014, this document outlines that the radiological follow-up of workers is one of the national missions of the IRSN in different ways: risk prevention (regulatory support, certification, workstation studies), individual control of workers exposed to ionizing radiations (internal and external dosimetry), follow-up of all exposed workers (SISERI, annual assessment, follow-up of incidents and events), expertise in case of anomalies or crisis, sharing of knowledge and know-how. It describes the traceability of the individual dosimetric follow-up of workers exposed to ionizing radiations in France (regulatory requirement, centralization of data). It comments the evolutions introduced in 2014 in the modalities of follow-up of worker exposure: publication of a new order, evolution of the SISERI information system with new functionalities, totally dematerialised signature of the access protocol, pages of the SISERI specifically dedicated to the CSE (SISERI correspondent of the employer), a sheet of medical follow-up, access rights for the competent radiological protection person. It gives an overview of regulation on worker control: present context with threshold exposure values, past evolution, follow-up principles. A diagram indicates these evolutions (dates of orders, concerned personnel, and dose thresholds)

Fukushima, 4 years after. Proceedings of the technical day

International Nuclear Information System (INIS)

Champion, Didier; Charles, Thierry; Renaud, Philippe; Fievet, Bruno; Besnus, Francois; Tichauer, Michael; Lecomte, Jean-Francois; Lebaron-Jacobs, Laurence; Menetrier, Florence; Piroux, Jean-Christophe; Schneider, Thierry; Godet, Jean-Luc

2015-03-01

Three years after the 2012 meeting of the French Society of Radiation Protection (SFRP) devoted to the Fukushima accident, the SFRP organized a new technical meeting to take stock of the actual situation in Japan. The program comprises 5 topical sessions dealing with: the accident, the status of the facility and its fate, the terrestrial and marine environmental impacts, the human health impacts and the preventive actions, the remedial actions in contaminated territories, and the post-accident management of territories, populations and foodstuffs. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - The Chernobyl and Fukushima accidents: common points and differences (Didier CHAMPION, SFRP); 2 - Fukushima Dai-ichi: present day situation and fate of the facilities (Thierry CHARLES, IRSN); 3 - The Fukushima accident impact on the terrestrial environment and the related doses (Philippe RENAUD, IRSN); 4 - The Fukushima accident impact on the marine environment (Bruno FIEVET, IRSN); 5 - Short-term health effects and implementation of the long-term population monitoring (Laurence LEBARON-JACOBS, CEA); 6 - Radiations and thyroid cancer risk (Florence MENETRIER, CEA); 7 - Decontamination wastes management (Francois BESNUS, IRSN); 8 - Solutions offered by Areva for the cleansing of the Fukushima site (Jean-Christophe PIROUX, AREVA); 9 - Questions about wastes management in post-accident situation (Michael TICHAUER, IRSN); 10 - Experts involvement to the population (Thierry SCHNEIDER, CEPN); 11 - Management of local foodstuffs (Jean-Francois LECOMTE, IRSN); 12 - Lessons learnt at the national and international scale (Jean-Luc GODET, ASN)

Feedback on the radiological management of a urban site contaminated with tritium

Energy Technology Data Exchange (ETDEWEB)

Leprieur, F.; Pierrard, O. [Institut de radioportection et de surete nucleaire - IRSN (France)

2014-07-01

Introduction: In November 2010, the IRSN is reached on a rare case of environmental tritium contamination on a site located in an urban area near Paris (Saint-Maur-des-Fosses - dpt 94). This contamination resulted from the presence in an enterprise's premises of an experimental device containing molecular sieve from the Valduc nuclear site, wrongly considered as un-used. First actions: IRSN has quickly performed an initial characterization of tritium contamination in the premises of the company and its close environment. The first results showed the existence of a strong local contamination (tritium activity> 150 000 Bq/m{sup 3} in air) and a important labeling in samples collected in the close vicinity of the company premises (between 1000 and 10000 Bq/kg f.w. in plants, between 500 and 1500 Bq/L in water). These results led IRSN to conduct multiple investigations: - tritium measurements on samples of water, air and plants collected in the area close to the building to know the importance and extent of environmental marking and follow its evolution over time. In this aim, 450 measurements were made between 2010 and 2013; - measurements of tritium in the urine of residents living near the contaminated building: the results showed traces of tritium for some of them but the assessments conducted by the IRSN from these results led to extremely low dosimetry estimates without consequences for the health of these people; - dosimetric evaluations of tritium exposure of employees and visitors of the company contaminated. Informing the public and stakeholders In November 2010, IRSN has collaborated with the mayor to facilitate early interventions in urban areas and in particular to facilitate contacts for access to private property. In this perspective, the IRSN participated in public meetings to explain the cause of this accident and the results of tritium measurements to residents. IRSN also published regularly on its web site briefing notes reflecting the results

Challenges for the nuclear safety of the deregulation of electricity markets; Defis pour la surete nucleaire de la dereglementation des marches de l'electricite

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Eurosafe 2000 was organised around two round tables on the first day and four seminars on the second day. The first round table dealt with general aspects of deregulation including the economic constraints and the special challenges arising during transition from regulated to deregulated structures. The second round table focussed on technical and organisational safety issues which are directly or indirectly related to the changes introduced by deregulation. The four seminars hold in order to provide opportunities for comparing experiences and learning about recent activities of IPSN, GRS and their partners in the European Union and Eastern Europe: Seminar 1 (Nuclear installation safety, assessment and analysis): assessment of the flooding incident at the Blayais nuclear power plant; PSA data base, comparison of the French and German approach; assessment of the Balakovo fire probabilistic study and elaboration of a guide for reviewing fire PSA; comprehensive technical assessment of an advanced German PWR by PSA - objectives and main results; PSA approach for the safety assessment of low-power and shutdown states; correlation of initiating events with the PSA level-2 results; safety assessment for fission products tests in the Phebus reactor; use of NPP simulators for applied human factor studies; assessment of the 'deterministic realistic method' applied to large LOCA analysis; assessment of the feasibility of an improvement programme enabling operation of units 3 and 4 of Kozloduy nuclear power plant. Seminar 2 (nuclear installation safety, research): PHEBUS 2K project on severe accidents; current status of the COCOSYS development; fission product modeling in ASTEC; Euratom Framework Programme (FP) research in reactor safety: main achievements of FP- 4 (1994-1998), some preliminary results of FP-5 (1998-2002) and prospects for beyond 2002; development of coupled systems of 3D neutronics and fluid-dynamic system codes and their application for safety analyses. Seminar 3 (environment and radiation protection): implementations of the variability in critical group doses for the control of radionuclides releases; campaign of environmental radioactivity measurements in the vicinity of La Hague made by European mobile laboratories - both a technical and sociological experience; contribution of some leading radioprotection societies to the current considerations with regard to the possible improvement of the ICRP policy system; decommissioning and dismantling of nuclear power plants: radiation protection experience in Germany; epidemiology of French nuclear workers within the IARC study. Seminar 4 (waste management): the Mont Terri rock laboratory, Switzerland; prediction of hydro-mechanical responses of a long-term pump test at the Sellafield site; modelling of water-rock interactions in deep ground-waters: equilibrium and perturbations; modelling of saturation and swelling effects in clays under different saline conditions; qualification of clay barriers in underground repository systems; integrating structural, hydraulic and geochemical evidence: a step towards understanding fluid flow through clay-rich formations; application of geostatistical methods to long-term safety analyses for radioactive waste repositories; major results and lessons learned from performance assessments on spent fuel geological disposal: the SPA project; repository incidents in Germany and abroad: what can be learnt; progress in the Chernobyl decommissioning and waste management strategy. (J.S.)

Progress in the domain of emissions tracking and environment radioactivity monitoring - Proceedings of the technical days organised by the SFRP Environment Section

International Nuclear Information System (INIS)

Calmet, Dominique; Calvez, Marianne; Rivasseau, Corinne Cea; Monfort, Marguerite; Manificat, Guillaume; Pierrard, Olivier; Couvez, Celine; Masson, Olivier; Bruno, Valerie; Renaud, Philippe; Genova, Zhana; Reynal, Nathalie; Le Coz, Eric; Tchilian, Nathalie; Diana, Jean-Jacques; Beguinel, Philippe; Cortes, Pierre; Puydarrieux, Stephane; Brun, Thierry; Devin, Patrick; Clavel, Benoit; Hemidy, Pierre-Yves; Gontier, Gilles; Delloye, Thierry; Mailliat, Alain; Ferreri, Giovanni; LECLERC, Elisabeth

2015-11-01

The Environment Section of the French Society of Radiation Protection (SFRP) organized a technical meeting on the progress made in the domain of emissions tracking and environment radioactivity monitoring. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - Environment monitoring at the global, national and local scale: historical overview (Dominique CALMET, CEA); 2 - Evolution of radioactivity monitoring in the environment from 1960 to the present day (Guillaume MANIFICAT, IRSN); 3 - Euratom's legal framework (Zhana GENOVA, CTE); 4 - Main regulatory changes during the last decade (Nathalie REYNAL, ASN); 5 - Progress of standardization works on radioactive effluent emissions control and environment monitoring (Philippe BEGUINEL, BNEN); 6 - From operators' self-monitoring to ASN's inspections: a many components control system (Eric LE COZ, ASN); 7 - Control of effluents and emissions management at CEA Centres (Marianne CALVEZ, CEA); 8 - Liquid and gaseous effluents of ITER experimental facility: description and impacts (Pierre CORTES, IO); 9 - Effluents and emissions management strategy at AREVA NC La Hague facility (Stephane PUYDARRIEUX, AREVA); 10 - Radioactive effluents from nuclear facilities ongoing deconstruction: from dimensioning to real effluents (Benoit CLAVEL, EDF); 11 - Radionuclides decontamination process for liquid effluents using micro-algae at the laboratory scale (Corinne RIVASSEAU, CEA); 12 - Radioactive effluents from nuclear medicine services: management, monitoring and impact measurement methods (Nathalie TCHILIAN, ASN); 13 - Evolution history of effluents management and environment monitoring at the Solvay La Rochelle site (Thierry DELLOYE, SOLVAY); 14 - Different international approaches in effluents management and monitoring: example of French and German gaseous effluents - regulation, analyses, accounting rules (Jean-Jacques DIANA, ASN); 15 - Environment

Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 13, 2011, 7:00 PM status - updated at 11:00 PM; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 13 mars 2011 a 19 heures - Mis a jour a 23 heures

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This situation note is established according to the information gained on March 13, 2011, at 7:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2 and 3 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

High committee for transparency and information on nuclear safety: meeting of December 16, 2010; Haut Comite pour la Transparence et l'Information sur la Securite Nucleaire. Reunion du 16 decembre 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

The discussion between members dealt with the following topics: the committee' program and implication with respect to the ACN approach (Aarhus Convention and Nuclear), the main orientations of the Transparency and Secret work group, the hearing of actors involved in a Tritium contamination incident in Valduc. These actors belonged to the CEA, to the 2M Process company, to the Nuclear safety authority or ASN, to the Institute for radiation protection and nuclear safety or IRSN, or to the Delegate to radiation protection and nuclear safety for installations of interest for the defence or DSND. Then the committee addressed the issue of old uranium mines and of places of use of uranium mining tailings. The committee members discuss the results of investigations performed around the Tricastin site (studies on cancers, on the presence of uranium in underground water sheets). Other topics are addressed: waste transportation to Germany, the French-British nuclear cooperation, the creation of a web site

Developing guidance in the nuclear criticality safety assessment for fuel cycle facilities

International Nuclear Information System (INIS)

Galet, C.; Evo, S.

2012-01-01

In this poster IRSN (Institute for radiation protection and nuclear safety) presents its safety guides whose purpose is to transmit the safety assessment know-how to any 'junior' staff or even to give a view of the safety approach on the overall risks to any staff member. IRSN has written a first version of such a safety guide for fuel cycle facilities and laboratories. It is organized into several chapters: some refer to types of assessments, others concern the types of risks. Currently, this guide contains 13 chapters and each chapter consists of three parts. In parallel to the development of criticality chapter of this guide, the IRSN criticality department has developed a nuclear criticality safety guide. It follows the structure of the three parts fore-mentioned, but it presents a more detailed first part and integrates, in the third part, the experience feedback collected on nuclear facilities. The nuclear criticality safety guide is online on the IRSN's web site

Staff Organization in Nuclear Power Stations; Organisation du personnel des centrales nucleaires; Organizatsiya personala na atomnykh ehlektrostantsiyakh; Organizacion del personal de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Scuricini, G. B. [Comitato Nazionale Energia Nucleare, Roma (Italy)

1963-10-15

This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author) [French] Dans le memoire, on examine l'organisation du personnel d'exploitation et d'entretien des centrales nucleaires italiennes et les differences existant dans les effectifs, differences dues soit aux caracteristiques des centrales memes, soit aux particularites d'organisation des entreprises. Le personnel charge de fonctions determinees pour lesquelles un entrainement special est requis, fait l'objet d'une attention particuliere. (author) [Spanish] En la memoria se examina la organizacion del personal de explotacion y conservacion de las centrales nucleares italianas y las diferencias que existen entre sus efectivos, diferencias que se deben a las caracteristicas de las mismas centrales o a las particularidades de organizacion de las empresas. El autor dedica especial atencion al personal encargado de funciones que requieren una formacion profesional especial. (author) [Russian] Issleduyutsya voprosy organizatsii personala, zanimayushchegosya ehkspluatatsiej ital'yanskikh atomnykh ehlektrostantsij i ukhodom za nimi, a takkhe razlichiya v sostave personala, vytekayushchie libo iz kharakternykh osobennostej samikh stantsij, libo iz osobennostej organizatsii predpriyatij. Osoboe vnimanie udelyaetsya personalu, kotoromu porucheny opredelennye funktsii, trebuyushchie spetsial'noj pod go tovki. (author)

Review of Development Status of Nuclear Superheat; Expose sur l'etat actuel des travaux concernant la surchauffe nucleaire; Obzor razrabotki voprosa o yadernykh peregrevatelyakh; Estudio de los progresos realizados en niateria de sobrecalentamiento nuclear

Energy Technology Data Exchange (ETDEWEB)

Imhoff, D. H.; Pennington, R. T. [General Electric Company, San Jose, CA (United States)

1963-10-15

fuel irradiation performance, in-pile and out-of-pile uniform and localized corrosion evaluations, results from thermal superheat critical experiments, results from experimental heat-transfer testing and a brief appraisal of the economic incentives of the separate superheat reactor, integral superheat reactor, and mixed-spectrum superheat reactor design studies. (b) A brief description is given of the USAEC-Sponsored ESADA-VESR nuclear superheat fuel development programme. The development tasks, the initial core superheat fuel-element design, the range of experimental variables, and the expected results for the three-year fuel development programme are discussed. (author [French] Depuis 1959, la Societe General Electric s'occupe activement de mettre au point la surchauffe nucleaire dans les reacteurs ralentis a l'eau ordinaire. A cette epoque, le ''Superheat Advance Demonstration Experiment'' (SADE), finance par la societe, a permis d'obtenir, pour la premiere fois aux Etats-Unis, de la vapeur surchauffee par un dispositif nucleaire. Les auteurs du memoire font le point de la situation actuelle concernant la surchauffe nucleaire. Ils decrivent, dans une premiere partie, les trois principales installations de surchauffe nucleaire utilisees par la General Electric et, dans la seconde, les deux principaux programmes de recherches sur la surchauffe ainsi que les resultats les plus importants obtenus jusqu'ici dans ce domaine. 1. Principales installations pour les experiences de surchauffe: a) Breve description du SADE utilise dans le reacteur a eau bouillante de Vallecitos (VBWR), avec tableaux des conditions dans lesquelles se deroulent les experiences, et des elements combustibles irradies pendant la periode comprise entre mai 1959 et juin 1962; puis examen critique des resultats les plus importants ainsi obtenus. b) Breve description de l' ''Expanded Superheat Advance Demonstration Experiment'' (E-SADE) installe dans le reacteur de Vallecitos, avec tableaux des

The design and construction of a nuclear free-precession magnetometer; Etude et realisation d'un magnetometre a precession libre nucleaire

Energy Technology Data Exchange (ETDEWEB)

Baconnier, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1960-10-15

After presenting the advantages of nuclear magnetic resonance with respect to electromagnetic processes, as far as the measurement of the earths' magnetic field is concerned, we deal with the macroscopic theory for the Bloch model and analyse Packard and Varions' experiment. The development of a particular absolute free-precession magnetometer is studied, and the conditions are determined for obtaining a maximum amplitude signal as a function of the geometrical form of the detector coil, of the method of cut-off, and of the coupling between various parts of the system. After having described in detail the technology of amplifiers, we consider the problem of the measurement of the frequency of precession for which an original solution, of analogy form, is proposed and discussed. Complete plans of the equipment are given in an appendix. (author) [French] Apres avoir presente les avantages de la resonance magnetique nucleaire relativement aux procedes electromagnetiques, en ce qui concerne la mesure du champ magnetique terrestre, on traite de la theorie macroscopique dans le modele de Bloch et analyse l'experience de Packard et Varian. On etudie une realisation particuliere d'un magnetometre absolu a precession libre et determine les conditions d'obtention d'un signal d'amplitude maximale en fonction de la forme geometrique du bobinage detecteur, de la methode de coupure, et du couplage entre les differents elements du montage. Apres avoir decrit en detail la technologie des amplificateurs, on aborde le probleme de la mesure de la frequence de precession, pour laquelle une solution originale, sous forme analogique, est proposee et discutee. En annexe est joint un dossier complet des plans de la realisation. (auteur)

Synthesis of the report from the IRRS evaluation mission performed at the ASN in April 2009 by 12 international experts under the IAEA coordination

International Nuclear Information System (INIS)

2009-01-01

At the request of the Government authorities of France, an international team of 24 experts visited the Autorite de Surete Nucleaire (ASN), the French regulatory authority for nuclear and radiation safety, in November 2006 to conduct the first full scope Integrated Regulatory Review Service (IRRS) mission. The purpose of the mission was to undertake a peer review of the regulatory body of France against the IAEA Safety Standards and to exchange information and experience on safety regulation. In March 2008 the Government authorities of France requested a follow-up mission to review the measures undertaken following the recommendations and suggestions presented in the report of the November 2006 IRRS mission. The scope of the IRRS follow-up mission covered the regulatory aspects of the facilities and practices regulated by ASN, nuclear power plants, research reactors, fuel cycle facilities, medical practices with further review of radiotherapy, industrial and research activities, waste facilities, decommissioning, remediation, public information and communication and, in addition, it was also extended to cover the application of the Code of Conduct of Safety and Security of Radioactive Sources. The review was conducted from March 29 to April 3 2009 by an IRRS team consisting of 12 senior regulatory experts from 11 Member States, two staff members from the IAEA, one IAEA observer and an IAEA administrative assistant. During the review the team recognized that ASN has taken a number of initiatives to improve its effectiveness and efficiency and that ASN faces new challenges. ASN supplied a package of documentation and a well prepared self-assessment, in advance of the mission, including a status report and an action plan to improve its regulatory effectiveness. Both regulatory technical and policy issues were addressed. The policy issues discussed were: regulatory independence, the relationship between ASN and IRSN and medical issues. The IRRS follow-up mission

Plutonium demonstration assemblies in the CNA core

International Nuclear Information System (INIS)

Romain, J.L.

1975-01-01

The SENA (Societe d'Exploitation Nucleaire des Ardennes) has decided to load two plutonium assemblies at the beginning of the 6th cycle of the CNA (Centrale Nucleaire des Ardennes). These assemblies will be loaded in September 1975 and will undergo three irradiation cycles. A general description of these two assemblies and nuclear design calculations that have been performed are presented [fr

Communication Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material, Software and Related Technology; Communication recue de certains Etats Membres concernant les directives applicables aux transferts d'equipements, de matieres et de logiciels a double usage dans le domaine nucleaire, ainsi que de technologies connexes

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-09-09

The Agency has received a Note Verbale from the Permanent Mission of Hungary, dated 14 June 2010, in which it requests that the Agency circulate to all Member States a letter of 7 May 2010 from the Chairman of the Nuclear Suppliers Group, Ambassador Ms. Gyorgyi Martin Zanathy, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America,1 providing further information on those Governments' Guidelines for Nuclear Transfers [French] L'Agence a recu une note verbale de la mission permanente de la Hongrie, en date du 14 juin 010, lui demandant de communiquer a tous les Etats Membres une lettre du 7 mai 2010 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Gyorgyi Martin Zanathy, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Croatie, Chypre, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Islande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraine1. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre; Traitement des Effluents Radioactifs au Centre d'Etudes Nucleaires de Saclay; 041e 0414 ; Tratamiento de los Efluentes Radiactivos en el Centro de Energia Nuclear de Saclay

Energy Technology Data Exchange (ETDEWEB)

Wormser, G. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

1960-07-01

The Report Gives The Account Of Four Years' Experience In Operating The Treatment Plant For Effluents From The Saclay Nuclear Research Centre. It Contains Data Relating To The Origin, Volume And Treatment Of Waste. (author) [French] Ce rapport presente un bilan d'exploitation de l'installation de traitement des effluents du Centre d'etudes nucleaires de Saclay depuis quatre ans. On donne des chiffres concernant l'origine des residus, leur volume, leur traitement. (author) [Spanish] El autor hace un balance de explotacion de la instalacion de tratamiento de efluentes del centro de Saclay desde hace cuatro anos, dando las cifras correspondientes al origen de los residuos, a su volumen y a su tratamiento. (author) [Russian] V jetom dokumente podvoditsja itog chetyrehletnej jekspluatacii ustanovki po obrabotke zhidkih othotov v Centre jadernyh issledovanij v Sakle. V doklade privodjatsja dannye o proishozhdenii othodov, jh ob'eme i obrabotke. (author)

Communication Received from the Permanent Mission of the Netherlands regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Communication recue de la mission permanente des Pays-Bas concernant les Directives de certains Etats Membres applicables a l'exportation de matieres, d'equipements et de technologie nucleaires

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-09-05

The Agency has received a Note Verbale from the Permanent Mission of the Kingdom of the Netherlands, dated 12 July 2011, in which it requests that the Agency circulate to all Member States a letter of 12 July 2011 from the Chairman of the Nuclear Suppliers Group, Ambassador Piet de Klerk, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [French] L'Agence a recu une note verbale de la mission permanente du Royaume des Pays-Bas, en date du 12 juillet 2011, lui demandant de communiquer a tous les Etats Membres une lettre du 12 juillet 2011 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Piet de Klerk, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Croatie, Chypre, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Islande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraineb. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

Safety balance: Analysis of safety systems; Bilans de surete: analyse par les organismes de surete

Energy Technology Data Exchange (ETDEWEB)

Delage, M; Giroux, C

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses.

Nuclear non proliferation. To declare, to support, and to analyse

International Nuclear Information System (INIS)

Anon.

2016-01-01

While proposing a brief presentation of the three main stages of an inspection (from the notification and preparation to the implementation of corrective actions), and a brief interview of a member of the French Euratom technical Committee (CTE) who presents this body and its role, this article proposes an overview of the commitment and practices of the IRSN regarding nuclear non-proliferation. It recalls that the control of nuclear materials is required by the Euratom Treaty, describes how the IRSN supports industrials to facilitate inspections made by the European Commission, and helps them in answering the post-inspection letter and in implementing corrective actions. It also evokes the role of the IRSN in nuclear material accounting

Study methods for the drillings around the underground nuclear explosions in the Sahara. Part 1. study of rock samples; Methodes d'etude des forages realises autour des explosions nucleaires souterraines au Sahara. Premiere partie: etude des echantillons de roche

Energy Technology Data Exchange (ETDEWEB)

Derlich, S [Commissariat a l' Energie Atomique, Bruyers-le-Chatel (France). Centre d' Etudes

1969-07-01

An examination of the mechanical effects produced on rocks by an underground nuclear explosion calls for the use of particular means of exploration which are described in this report, special attention being paid to the equipment used in connection with the French nuclear tests in the Sahara. The drilling methods used (rotary and turbo-drilling) are adapted to the particular conditions of the sampling programme, to the radioactivity and to the temperature in the region of the explosion. A study of the samples makes it possible to obtain the new characteristics of the rock and to assess the chemical and mechanical transformations which it has undergone. An examination of the core obtained from the drilling, together with a knowledge of the drilling parameters (depth of the probe, sample recovery, etc...), makes it possible to study the extent and the characteristics of the zones which have been damaged to different degrees according to their distance from the zero point: cavity, strongly powdered zone, fractured zone, chimney, zones containing high stresses leading to a particular type of fracture of the cores. The problems connected with the interpretation of the results are also presented. (author) [French] L'examen des effets mecaniques provoques par une explosion nucleaire souterraine sur la roche necessite la mise en oeuvre de moyens d'exploration particuliers dont l'expose fait l'objet de ce rapport, essentiellement pour les moyens utilises autour des essais nucleaires francais au Sahara. Les methodes de forage (rotary et turboforage) sont adaptees aux conditions particulieres dues au programme d'echantillonnage, a la radioactivite et a la temperature regnant a proximite du point de tir. L'etude des echantillons permet la determination des nouveaux caracteres de la roche et de ses transformations chimique et mecanique. L'examen des carottes et l'utilisation des parametres de forage (cotes sondeurs, recuperation des echantillons, etc...) permettent d'etudier l

The European nuclear safety and radiation protection area: steps and prospects; L'Europe de la surete nucleaire et de la radioprotection: grandes etapes et perspectives

Energy Technology Data Exchange (ETDEWEB)

Gillet, G. [Autorite de Surete Nucleaire, Dir. des relations internationales 75 - Paris (France)

2010-11-15

Launched with enthusiasm and determination in 1957, The European Atomic Energy Community (EAEC - EURATOM), which aimed to promote the development of a 'powerful nuclear industry' in Europe, has not ultimately fulfilled the wishes of its founding fathers. Rapidly, and on a topic as strategic as the peaceful use of the atom, national reflexes prevailed. The Chernobyl disaster, in 1986, also substantially slowed down the use of nuclear energy in Europe. Nuclear safety and radiation protection have followed two different paths. Backed by Chapter III of the EURATOM treaty, over time the EAEC has developed a substantial legislative corpus on radiation protection. Meanwhile, and strange as it may seem, nuclear safety has remained the poor relation, on the grounds that the treaty does not grant EURATOM competence in the area. It is true that legislation was adopted in reaction to Chernobyl, but for a long time there was no specific regulation of nuclear safety in the EU. The European nuclear safety and radiation protection area owes its construction to Community mechanisms as well as to informal initiatives by safety authorities. Today, more than ever, this centre provides consistency, an overall balance which should both strengthen it and impose it as an international reference. Progress can now be expected on waste management, radiation protection and the safety objectives of new reactors. (author)

New features of nuclear excitation by {alpha} particles scattering; Nouveaux aspects de l'excitation nucleaire par diffusion de particules {alpha}

Energy Technology Data Exchange (ETDEWEB)

Saudinos, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1962-07-01

Inelastic scattering of medium energy a particles by nuclei is known to excite preferentially levels of collective character. We have studied the scattering of isotopically enriched targets of Ca, Fe, Ni, Cu, Zn. In part I, we discuss the theoretical features of the interaction. In part II, we describe the experimental procedure. Results are presented and analysed in part III. {alpha} particles scattering by Ca{sup 40} is showed to excite preferentially odd parity levels. In odd nuclei we have observed multiplets due to the coupling of the odd nucleon with the even-even core vibrations. For even-even nuclei, a few levels are excited with lower cross-sections between the well-known first 2{sup +} and 3{sup -} states. Some could be members of the two phonon quadrupole excitation and involve a double nuclear excitation process. (author) [French] On sait que la diffusion inelastique des particules alpha de moyenne energie excite preferentiellement des niveaux de caractere collectif. Nous avons etudie la diffusion des particules alpha de 44 MeV du cyclotron de Saclay par des isotopes separes de Ca, Fe, Ni, Cu, Zn. Dans la premiere partie nous exposons les theories de cette interaction. Dans la seconde nous decrivons le systeme experimental. Les resultats sont donnes dans la troisieme partie. Nous montrons que les niveaux excites preferentiellement pour {sup 40}Ca par diffusion ({alpha},{alpha}') sont de parite negative. Dans les noyaux pair-impair nous avons observe des multiplets dus au couplage du nucleon celibataire avec les vibrations du coeur pair-pair. Pour les noyaux pair-pair nous avons pu etudier entre le premier niveau 2{sup +} et le niveau 3{sup -} deja bien connus certains etats plus faiblement excites. Il semble qu'ils sont dus a une excitation quadrupolaire a deux phonons et impliquent un processus de double excitation nucleaire. (auteur)

Some aspects of the nuclear fission process; Quelques aspects du processus de fission nucleaire

Energy Technology Data Exchange (ETDEWEB)

Netter, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1961-07-01

In the following report one can find first a short general view on the present situation of our knowledge concerning the nuclear fission process, namely on the nucleus going through the saddle-point. Then there are some aspects connected with the excitation energy of the fissioning nucleus. The measurements made at Saclay on the fast neutron fission cross-section of U{sup 233}, U{sup 235}, Pu{sup 239}, U{sup 238} are described at the beginning of this work. It appears that for U{sup 233} there is some characteristic shape modulation of the cross-section curve, in relation with the collective excited state of the deformed nucleus at the saddle-point. Good evidence of this is also given by the study of the relative fission rate with emission of long-range particles; it appears also that this ternary fission rate does not change substantially for neutron between thermal energy and 2 MeV, but that is very lower for the compound nucleus U{sup 239} than for even-even compound nuclei. At the end there are some experiments on the strong 4,5 MeV gamma-ray originated by slow neutron absorption in U{sup 235}. Time-of-flight device is used to establish that this 4,5 MeV gamma-ray seems mostly connected with radiative capture. (author) [French] Le present travail debute par un apercu de l'etat actuel de nos connaissances sur le processus de fission nucleaire, notamment sur le passage par le point-seuil. Puis sont evoques des aspects lies au niveau d'energie d'excitation auquel est porte le noyau qui subit la fission. Les mesures de sections efficaces de fission induite dans {sup 233}U, {sup 235}U, {sup 239}Pu et {sup 238}U par des neutrons rapides effectuees a Saclay sont decrites en premier lieu; elles font apparaitre pour {sup 233}U une ondulation caracteristique du role des etats collectifs d'excitation du noyau deforme au point-seuil. Des experiences sur la fission avec emission de particules de long parcours confirment cet aspect tout en demontrant que la frequence

Contribution to the study of the evolution of radiation induced He in Be O; Etudes sur l'evolution de l'helium produit par reactions nucleaires dans l'oxyde de beryllium

Energy Technology Data Exchange (ETDEWEB)

Bareau, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1966-11-15

The purpose of this work in-pile investigation of He formed by (n, 2n) and (n, {alpha}) nuclear reactions, released from irradiated BeO, in the temperature range 1000 - 1350 deg. C. The experimental results show that, for an instantaneous neutron fast flux of 10{sup 13} n cm{sup -2} sec{sup -1}, an equilibrium is attempted, after several days, for a part lower than 20 per cent of the quantity of He formed, theoretically calculated from the neutron cross sections of nuclear reactions, and from the analytical form of the neutron fast flux, releases from the solid. The validity of the values of calculated helium and the gas chromatographic analytical method are also verified by dissolution of the BeO pellets in cryolite. A new fast neutron flux measuring method may be so defined. The discussion of the experimental results enables to establish that the processus of He release is characterized by two phenomena: the first one which controls the release of He atoms out of the solid and the second which reveals a capture processus, connected to the irradiation and probably due to the vacancies induced in the lattice. (author) [French] On etudie en pile le degagement de l'helium forme par reactions nucleaires (n, 2 n) et (n, {alpha}) dans l'oxyde de beryllium irradie entre 1000 et 1350 deg. C. Les resultats experimentaux montrant que, pour un flux rapide instantane de 10{sup 13} n{sub r} cm{sup -2} s{sup -1}, on aboutit, au bout de quelques jours, a un etat d'equilibre pour lequel une partie, inferieure a 20 pour cent de la quantite d'helium forme, calculee theoriquement a partir des sections efficaces des reactions nucleaires et de la forme analytique du flux rapide, s'echappe du solide. On verifie egalement par dissolution des echantillons de BeO dans la cryolithe la validite du calcul de l'helium et de la methode de dosage par chromatographie en phase gazeuse. On peut ainsi definir une methode nouvelle de mesure des flux rapides. La

In brief...France

International Nuclear Information System (INIS)

Anon.

2008-01-01

Among the different news we can find information about the situation of the radiation accidents at the hospital of Epinal in the east of France. The medical surveillance of the irradiated patients has allowed to find others cases of over exposure.These new cases add to a series of events enlightened in this service: 24 patients treated for a prostate cancer between may 2004 and august 2005 have been over exposed of about 20 % because of a bad use of the treatment planning software. 4 hundred patients treated for a prostate cancer between 2001 and 2006 have been over exposed of about 8% by an excessive use of the imaging controlling the positioning during the treatment. Among 4500 patients treated for different cancers between september 1987 and july 2000 and concerned by a programming error of an internal software, 312 patients have received an overexposure of about 7%. The Authority of nuclear safety and the Institute of radiation protection and nuclear safety (I.R.S.N.) publish the report of management 2006 on the Internet gate of the National network of environmental radioactivity measurements. The Internet site of the pluralist expertise group on the uranium mines sites of the Limousin opens at the address :www.gep-nucleaire.org. The high committee for the transparency and information on nuclear safety is officially created. The Asn has classified at the level 4+ of the experimental scale Asn-S.F.R.O. the accident occurred at the teaching hospital of Toulouse between the 11. april 2006 and the 18. april 2007 implying 145 patients treated by intracranial radiosurgery. (N.C.)

Criticality guide. I - Introduction to criticality. II - Practical rules. III - Curves; Guide de criticite. I - Introduction a la criticite. II - Regles pratiques. III - Courbes

Energy Technology Data Exchange (ETDEWEB)

NONE

1967-07-01

Somme elements of neutronics are presented in a simple and often intuitive way; the 'K infinite' and 'K effective' formulae are derived and discussed. The limiting solid angle method is explained and some simple formulae proposed for evaluating the interaction between 'fissile units'. The general principles used in studying the safety of nuclear installations using fissile matter are given. Practical rules, critical mass and critical geometry curves as well as all the numerical values required for normal criticality calculations are given for plutonium and uranium at various degrees of enrichment. This guide is not intended to produce experts in criticality and cannot replace the advice which can be given by specialists of a science which is still expanding rapidly. It should however simplify the task of these specialists by familiarising with these problems both the engineers and scientists in charge of the design of installations using fissile matter, and the persons in charge of their operation. (author) [French] Des elements de neutronique sont exposes d'une fapon simple et souvent intuitive les formules du 'K infini' et du 'K effectif' sont etablies et commentees. La 'methode de l'angle solide limite' est expliquee et des formules simples proposees pour evaluer l'interaction entre des 'unites fissiles'. Les principes generaux utilises dans les etudes de surete nucleaire d'installation, mettant en ceuvre des matieres fissiles, sont donnes. Des regles pratiques, des courbes de masse et geometrie critiques ainsi que toutes les valeurs numeriques necessaires aux calculs usuels de criticite sont fournies pour du plutonium et de l'uranium a divers enrichissements. Ce guide n'a pas la pretention de former des experts en criticite et ne doit pas dispenser de s'entourer de l'avis de specialistes dans une science encore en pleine evolution. II doit simplement faciliter la tache de ceux-ci, en familiarisant avec ces problemes les ingenieurs charges de la conception des

Forest food chain and dose model (FDMF) for RODOS. Model description

International Nuclear Information System (INIS)

Rantavaara, A.; Vetikko, V.; Calmon, P.; Wendt, J.

2001-12-01

Protection et de Surete Nucleaire), France, under the umbrella of the RODOS project of the 4th Framework Programme of the EC. (orig.)

Analysis of a large break LOCA in the cold leg of the WWER-440/W-213 plant Griefswald, Unit 5

International Nuclear Information System (INIS)

Horche, W.

1993-01-01

The Gessellschaft fur Anlagen und Reaktorsicherheit (GRS) has performed a safety evaluation of the nuclear power plant (NPP) Greifswald, unit 5, of the Soviet type WWER-440/W-213, in cooperation with the French Institute de Protection of de Surete Nucleaire (IPSN) and other partners. Within this project an independent accident analysis is performed by GRS in order to assess the results of existing analysis and to supplement them. In this paper the analysis of the double-ended guillotine break (DEGB) of one cold leg of the main circulation pipe is described. The major objective of the calculation was the investigation of the accident sequence with reduced availability of the emergency core cooling system (single failure criterion). In addition, the simultaneous loss of onsite and offsite power and the failure of scram were assumed. The thermal-hydraulic system code ATHLET/FLUT, developed at GRS and already applied for the safety analysis of several WWER plants, was chosen again. The pressure in the confinement, the back pressure for the discharge model, was calculated as a function of time for this accident separately with GRS-Code RALOC. Furthermore, it was necessary to model the local concentration of direct accumulator injection into the reactor vessel with the help of a special two-channel model of the core and upper plenum. For this model, results were considered obtained from the 1:1 scaled test facility UPTF. It was assumed that only 25% of the upper plenum and core volume is directly penetrated by the injected water. The DEGB was defined in that loop, which is connected with one of three low-pressure injection subsystems. This means that this injected water flows towards the leak without passing the core. As single failure the failure of one of three diesel generators was assumed. The full paper will contain nodalization schemes, which are generated by the ATHLET-Input-Grafic

Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Darras, R. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de Saclay, Section d' etude de la corrosion par gaz et metaux liquides (France)

1960-07-01

This article begins with a review of the various materials which can be used and the cooling gases in which they may be heated, emphasis being placed on the importance of reaching temperatures as high as possible. This is followed by a few general remarks on the dry oxidation of metals and alloys, particularly with regard to diffusion phenomena and their various possible mechanisms, and also the methods of investigation employed. Finally, the behaviour of the chief nuclear materials heated in the various gases is studied successively. Materials used for fuel (metallic uranium, uranium oxide, carbides and silicides), canning materials (magnesium, aluminium, zirconium, beryllium, stainless and refractory steels), structural materials (ordinary or slightly alloyed steels), and finally moderators (graphite, beryllium oxide) are deal with in this way. This account is backed up both by the results obtained at the CEA and by work published outside or abroad up to the present day. In conclusion, every effort has been made to direct future research on the basis of the foregoing. Reprint of a paper published in Industries Atomiques - no. 9/10, 1959, p. 3-23 [French] Dans cet article, on passe tout d'abord en revue les divers materiaux utilisables et les gaz de refroidissement dans lesquels ils peuvent etre chauffes, en insistant sur l'interet d'atteindre des temperatures aussi elevees que possible. On rappelle ensuite quelques generalites sur l'oxydation seche des metaux et alliages, notamment en ce qui concerne les phenomenes de diffusion et leurs divers mecanismes possibles ainsi que les methodes d'etude. Enfin, le comportement des principaux materiaux nucleaires chauffes dans les divers gaz est etudie successivement. On traita ainsi des materiaux combustibles (uranium metallique, oxyde, carbures et siliciures d'uranium), des materiaux de gainage (magnesium, aluminium, zirconium, beryllium, aciers inoxydables et refractaires), des materiaux de structure (aciers ordinaires