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Ivanenko, V.N.; Zybin, V.A.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1988
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1988
AbstractAbstract
[en] In this paper the different ways of development for the BN-800 maximum credible accident in case of loss and fire of primary sodium are examined. The more constraining scenario is presented. During the scenario analysis the accidental release of radioactive materials in the environment has been studied. These releases are below the authorized values
[fr]
Dans cette communication sont examinees les differentes voies de developpement d'un accident maximum presivible sur le reacteur BN-800, lie a une fuite et un feu de caloporteur du circuit primaire. On presente le scenario le plus contraignant de developpement d'un tel accident. Au cours de l'analyse de ce scenario, on a etabli les valeurs d'un rejet maximum de matieres radioactives dans l'environnement. On indique que ces rejets au cours de l'accident ne depassent pas les valeurs admissiblesOriginal Title
Analyse d'un accident maximum previsible avec une fuite de sodium sur le circuit primaire de BN-800 et un scenario de developpement d'accident le plus contraignant
Primary Subject
Source
Jan 1988; 21 p; Translated from Russian from French-Soviet Seminar on fast neutron reactor safety.
Record Type
Report
Literature Type
Translation
Report Number
Country of publication
ACCIDENTS, ALKALI METALS, BREEDER REACTORS, COLLOIDS, CONTAINMENT, COOLING SYSTEMS, DISPERSIONS, ELEMENTS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, METALS, POWER REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SODIUM COOLED REACTORS, SOLS, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS
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