Preliminary analysis of the post-disassembly expansion phase and structural response under unprotected loss of flow accident in prototype sodium cooled fast reactor

For the prototype sodium-cooled fast reactor, MONJU, the mechanical energy and structural response under energetics caused by neutronic power excursion during Unprotected Loss of Flow (ULOF) accident were preliminarily evaluated. In the first licensing of MONJU, pressure-volume relation (P-V relatio...

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Autores principales: Yuichi ONODA, Ken-ichi MATSUBA, Yoshiharu TOBITA, Tohru SUZUKI
Formato: article
Lenguaje:EN
Publicado: The Japan Society of Mechanical Engineers 2017
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Acceso en línea:https://doaj.org/article/029d69babe974376bf8abaf7ec1bda13
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