Development of fundamental numerical simulation system for integrated safety evaluation in various innovative sodium-cooled fast reactor, 2; Development plan of integrated numerical simulation system for severe accident analysis

Uchibori, Akihiro ; Kawada, Kenichi ; Aoyagi, Mitsuhiro ; Takata, Takashi*; Nakahara, Hirotaka*; Abe, Takashi*

A safety evaluation technology which is based on the SPECTRA code for integrated analysis of in- and ex-vessel phenomena during severe accidents in sodium-cooled fast reactors has been developed. The development in the next four years includes a lumped mass model of in-vessel coolant behavior, an analytical model for a passive decay heat removal system, RVACS, and application of SPECTRA for the PRISM-type reactor which is a small modular fast reactor.

Language	:	Japanese
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Meeting title	:	日本原子力学会2021年秋の大会
Held date	:	2021/09
Location (city)	:	札幌(online)
Location (country)	:	日本
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Keywords	:	ナトリウム冷却高速炉; シビアアクシデント; 安全性評価; SPECTRA
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Cooperating Institute	:	文部科学省

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Registration No. : BB20210558
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