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JAEA Reports

Study on representative events for safety design/evaluation and beyond-design-basis events

*; *; Himeno, Yoshiaki; Haga, Kazuo*; Miyake, Osamu; *; *

PNC TN9410 90-119, 58 Pages, 1990/03

PNC-TN9410-90-119.pdf:1.31MB

With a view to giving reasonable requirements for design of containment features in a large LMFBR, this study discusses the following issues: selection of representative events considered in the safety design/evaluation, consideration of the effect of sodium on FP retention in the "Hypothetical Accident" (site evaluation accident), and evaluation of safety margin against beyond-design-basis events. This report contains some technical documents which are provided to the study group meeting.

JAEA Reports

Computer codes for safety analysis of LMFBR

*; *; *; *; *; *; *

PNC TN241 85-12, 292 Pages, 1985/03

PNC-TN241-85-12.pdf:3.94MB

Computer codes for safety analysis, including systems codes, which are used for the evaluation of LMFBR plants, have been developed along with the progress of the construction and the operation of experimental fast reactor "JOYO". On the other hand, a large number of data has been accumulated at O-arai Engineering Center and other laboratories both in Japan and abroad with the advance of safety R&D on Liquid Metal Fast Breeder Reactor (LMFBR). Various models of analysis have been proposed and many computer codes have been developed which are based on these models. This paper describes the essential part of the models and the functions of the codes, thus developed, which are used for the safety evaluation of LMFBR plant such as the prototype fast breeder reactor "MONJU". Analize codes for sodium leakage accident were modified, so that detailed conditions could be taken into account.

JAEA Reports

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