Development of the Methodology of the Safety Analysis Performed by the Coupled KIKO3D/ATHLET Code System in VVER-440 Type NPP
Keyword(s):
In the deterministic safety analysis codes are required in order to provide evaluations of potential nuclear plant accidents. In the fields of the core transient behaviour, the computer codes have achieved a high degree of realistic modelling. Nevertheless, some further tools for the investigations of the wide range of physical phenomena in the whole plant transient, such as modeling the ex-core detector signals and the malfunctioning of the emergency control system are unavoidable, too. The programs and methods used in KFKI-AEKI for safety analysis of VVER-440 NPP are presented. The accident analysis methodology for a boron dilution scenario, in which an inactive coolant loop is started, is shown.
1969 ◽
Vol 1
(02)
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pp. 211-237
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1966 ◽
Vol 17
(6)
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pp. 875
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2018 ◽
Vol 16
(05)
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pp. 362-368
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1965 ◽
Vol 209
(4)
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pp. 705-710
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