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Report No.
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Valuation of seismic safety of the prototype fast breeder reactor Monju on the basis of the revised regulatory guide for seismic design, 5; Evaluation of sloshing in the fuel pool

Ito, Kei; Ohshima, Hiroyuki; Moribe, Takeshi; Koga, Kazuhiro*

In accordance with the revision of "Regulatory guide for seismic design of nuclear power plants", the seismic safety assessment of the prototype fast breeder reactor "Monju" was carried out based on the revised guide. In this report, the sloshing in the fuel pool is simulated by the MPS method and the overflow from the pool is evaluated.

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