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AbstractAbstract
[en] This paper gives an exhaustive inventory of criticality accidents that occurred in nuclear facilities of USA, UK and USSR. The paper starts with the description and the analysis of the Oak Ridge Y-12 plant criticality accident from June 16, 1958, and the general material, human and environmental consequences of criticality accidents. The safety rules followed in CEA sites and COGEMA fuel cycle facilities to prevent criticality accidents are briefly described. (J.S.). 2 tabs., 1 photo
Original Title
Les accidents de criticite
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Secondary Subject
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Journal Article
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ACCIDENTS, BIOLOGICAL EFFECTS, BIOLOGICAL RADIATION EFFECTS, DEVELOPED COUNTRIES, DISEASES, DISPERSIONS, FISSIONABLE MATERIALS, HOMOGENEOUS MIXTURES, INJURIES, MATERIALS, MIXTURES, NATIONAL ORGANIZATIONS, NEUTRON ABSORBERS, NORTH AMERICA, NUCLEAR POISONS, RADIATION EFFECTS, REACTOR MATERIALS, SIZE, SOLUTIONS, TENNESSEE, URBAN AREAS, US AEC, US DOE, US ERDA, US ORGANIZATIONS, USA
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Lefort, G.; Puit, J.C.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Physique du Plasma et de la Fusion Controlee1978
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Physique du Plasma et de la Fusion Controlee1978
AbstractAbstract
[en] The operation of the LWRs requires the storage of irradiated fuel elements in cooling pools, to which it is possible to access directly from the reactor core. After transportation to the reprocessing plants, the storage must be continued in storage pools located at the entry of the plant. The requirements retained in order that no safety problems arise during the overall storage time have been defined from the acquired experience : they are relative to all functions having an effect on the normal operating conditions : cooling, containment, shielding, handling, controls, waste and effluents processing, etc. The requirements have been defined so that the storages cannot be the cause of accidents either resulting in an impact on the environment or being the consequences of the environment conditions : criticality, loss of water, missile impact, earthquakes, etc. They need permanent presence of a qualified staff. (author)
Original Title
La surete des installations francaises de stockage des elements combustibles irradies de la filiere a eau legere
Primary Subject
Secondary Subject
Source
1978; 8 p; The storage of spent fuel elements; Madrid, Spain; 20 - 22 Jun 1978
Record Type
Miscellaneous
Literature Type
Conference
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Country of publication
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INIS IssueINIS Issue
Lefort, G.; Puit, J.C.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France)1982
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France)1982
AbstractAbstract
[en] Storage conditions for the cooling of fast neutron spent fuel assembly, before reprocessing, will be adapted specifically to this fuel cycle, but in a preliminary testing period it is better to take advantage of the industrial storage conditions already used for spent fuel of light water reactors, even if no extrapolation is possible in the future. In this aim fuel assemblies are dismantled, as soon as thermal conditions allow it, and pins are gathered in leak proof containers in a gas atmosphere and put in a cooling pool. This solution gives good results but studies and experiments are resumed, for future processing, for safe, easy and economical transport and storage conditions
[fr]
Les conditions de stockage pour refroidissement en attente de retraitement des assemblages combustibles de la filiere des reacteurs a neutrons rapides lui seront specifiques lorsque l'on aura atteint le regime de croisiere; mais il a semble preferable, pour toute la periode de mise au point actuelle, de retenir des solutions qui, bien que n'etant peut-etre pas directement extrapolables a l'avenir, permettent de profiter des conditions de stockage industrielles deja utilisees pour les combustibles des reacteurs de la filiere a eau ordinaire. Pour cela, des que les conditions thermiques le permettent, les assemblages sont demanteles et les aiguilles sont rassemblees dans des conteneurs etanches sous gaz; ces ensembles sont mis en piscine de refroidissement. A ce jour, cette solution donne entiere satisfactionOriginal Title
La surete des installations de stockage des combustibles rapides uses
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Secondary Subject
Source
Apr 1982; 18 p; Seminar on fuel storage; Leningrad (USSR); 20 - 27 Apr 1982; DSN--556
Record Type
Report
Literature Type
Conference
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Maubert, L.; Puit, J.C.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1987
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1987
AbstractAbstract
[en] In this paper, the authors present the philosophy which have conducted them at the realization of this book, the critical values retained and the future developments
[fr]
Dans ce papier, les auteurs presentent la philosophie qui les a conduits a realiser un guide de criticite, les valeurs critiques retenues et les developpements futursOriginal Title
Le guide de criticite Francais
Primary Subject
Source
Nov 1987; 8 p; International seminar on nuclear criticality safety; Tokyo (Japan); 19-23 Oct 1987
Record Type
Report
Literature Type
Conference
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Lefort, G.; Puit, J.C.
Proceedings of the NEA seminar on the storage of spent fuel elements. Madrid, 20-23 June 19781978
Proceedings of the NEA seminar on the storage of spent fuel elements. Madrid, 20-23 June 19781978
AbstractAbstract
[en] The operation of the LWRs requires the storage of irradiated fuel elements in cooling pools, to which it is possible to access directly from the reactor core. After transportation to the reprocessing plants, the storage must be continued in storage pools located at the entry of the plant. The requirements retained in order that no safety problems arise during the overall storage time have been defined from the acquired experience; they are relative to all functions having an effect on the normal operating conditions: cooling, containment, shielding, handling, controls, waste and effluents processing, etc. The requirements have been defined so that the storages cannot be the cause of accidents either resulting in an impact on the environment or being the consequences of the environment conditions: criticality, loss of water, missile impact, earthquakes, etc... They need the permanent presence of a qualified staff
[fr]
L'exploitation des reacteurs de la filiere a eau legere impose de stocker les elements combustibles irradies dans des piscines de refroidissement directement accessibles a partir du coeur des reacteurs, puis, apres transport, de poursuivre ce stockage dans les piscines d'entree des usines de retraitement. Les conditions retenues pour que ces stockages ne soulevent pas de difficultes au plan de la surete, pendant cette periode, ont ete definies a partir de l'experience acquise; elles concernent tous les postes ayant une repercussion sur les conditions normales d'exploitation - refroidissement, confinement, blindage, manutention, controles, traitement des dechets et effluents, etc - et ont ete arretees pour que ces stockages ne soient pas la cause d'accidents pouvant atteindre l'environnement ou en subir les repercussions - criticite, perte d'eau, chute de missile, seisme, etc - Elles imposent la presence permanente de personnel qualifieOriginal Title
La surete des installations francaises de stockage des elements combustibles irradies de la filiere a eau legere
Primary Subject
Secondary Subject
Source
Anon; p. 97-106; ISBN 92-64-01840-9;
; 1978; p. 97-106; OECD; Paris, France; Seminar on the storage of spent fuel elements; Madrid, Spain; 20 - 23 Jun 1978

Record Type
Book
Literature Type
Conference
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Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Maubert, L.; Puit, J.C.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1987
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1987
AbstractAbstract
[en] In France, all the calculations for preventing criticality are based on uranium oxyde with a maximal enrichment of 3.5% in 235 U. Because the electricity producers use now a more enrichment fuel (until 4.5%, in weight), it is necessary to take in account the burnup for studies of criticality in containers or in reprocessing plants. In this paper the author shows the main problems for taking in account the burnup
[fr]
En FRANCE jusqu'a present, tous les calculs lies a la prevention du risque de criticite dans le cycle du combustible des reacteurs a eau ont porte sur l'oxyde d'uranium non irradie d'enrichissement maximal 3,5% en 235U pour ce qui concerne les usines de retraitement, les emballages de transport et les piscines de stockage. Cependant les producteurs d'electricite d'origine nucleaire s'orientent maintenant vers l'utilisation de combustible a base d'uranium plus enrichi (jusqu'a 4,5% en 235U), il est necessaire de prendre en compte le taux de combustion si l'on ne veut pas remettre en cause la conception des stockages en piscine et des emballages de transport ainsi que celle des tetes d'usine de retraitement (dissolveur). Les problemes lies a la prise en compte d'un taux de combustion sont nombreux et complexes. Nous nous proposons ici d'en exposer les principauxOriginal Title
La prise en compte du taux de combustion dans les etudes de criticite des installations du cycle du combustible irradie
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Source
Nov 1987; 9 p; International seminar on nuclear criticality safety; Tokyo (Japan); 19-23 Oct 1987
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Report
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Conference
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AbstractAbstract
[en] After briefly mentioning processes, the principal measures used to guaranty the safety-criticality as well as the way to apply them are reviewed
[fr]
Apres un bref rappel des procedes, on passe en revue les principaux moyens utilises pour garantir la surete-criticite, ainsi que la facon de les appliquerOriginal Title
La surete-criticite dans les usines de retraitement et les ateliers de fabrication d'elements combustibles
Primary Subject
Secondary Subject
Source
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; 405 p; nd; p. 65-90; CEA-IPSN; Fontenay-aux-Roses, France; Seminar on safety criticality; Valduc, France; 16 - 18 Oct 1979
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Book
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Conference
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AbstractAbstract
[en] An examination is made of the various parameters acting on the neutron balance: mass, moderation, density, geometry, interactions, absorption and poisoning. The monitoring methods are deduced from this. Using two examples, it is shown how the various parameters act together and in different ways so that it is difficult to predict the results and that it is necessary to have calculation codes well qualified on experience
[fr]
On examine les differents parametres agissant sur le bilan neutronique: masse, moderation, densite, geometrie, interactions, absorption et empoisonnement. On en deduit les modes de controle. On montre par deux exemples que les differents parametres agissent ensemble et de facons differentes de sorte qu'il est difficile de prevoir le resultat et qu'il est necessaire d'avoir des codes de calcul bien qualifies sur l'experienceOriginal Title
Criteres fondamentaux de surete-criticite dans la conception des installations
Primary Subject
Source
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; 405 p; nd; p. 21-49; CEA-IPSN; Fontenay-aux-Roses, France; Seminar on safety criticality; Valduc, France; 16 - 18 Oct 1979
Record Type
Book
Literature Type
Conference
Country of publication
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Lefort, G.; Bourgeois, M.; Poulain, A.; Maigret, C.; Puit, J.C.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1982
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1982
AbstractAbstract
[en] Fast neutron reactors fuels have a high proportion of plutonium and undergo severe irradiation. Risks during spent fuel reprocessing and subsequent fabrication will depend on isotopic composition, fission product content, physico-chemical form of products, quantities handled. These risks (criticality, contamination, irradiation) are listed for the different steps of the cycle and methods used to control the risks (chemical reaction yields, equipment reliability, intervention, conditions...) are indicated. Problem arising from wastes and effluents produced at each step are briefly given
[fr]
Le combustible des reacteurs a neutrons rapides contient une proportion importante de plutonium et subit un taux d'irradiation eleve. Les risques engendres par le traitement des combustibles irradies puis la fabrication dependront des compositions isotopiques des matieres, des teneurs en produits de fission, des differentes formes physico-chimiques des produits, des quantites manipulees. Ces risques (criticite, contamination, irradiation ...) sont recenses aux differents stades du cycle et les methodes mises en oeuvre pour les maitriser (rendement chimique, fiabilite des appareils, modalites d'intervention...) sont indiquees. Enfin, les problemes souleves par les dechets et effluents engendres sont abordes aux differents stadesOriginal Title
Les problemes de surete dans le cycle du combustible des reacteurs rapides
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Source
Jul 1982; 9 p; International topical meeting on liquid metal fast breeder reactor safety and related design and operational aspects; Lyon (France); 19 - 23 Jul 1982
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Report
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AbstractAbstract
No abstract available
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Source
ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
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Journal Article
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Conference
Journal
Transactions of the American Nuclear Society; v. 28 p. 287-288
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