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...
Guardado en:
Autores principales: | Yuichi ONODA, Ken-ichi MATSUBA, Yoshiharu TOBITA, Tohru SUZUKI |
---|---|
Formato: | article |
Lenguaje: | EN |
Publicado: |
The Japan Society of Mechanical Engineers
2017
|
Materias: | |
Acceso en línea: | https://doaj.org/article/029d69babe974376bf8abaf7ec1bda13 |
Etiquetas: |
Agregar Etiqueta
Sin Etiquetas, Sea el primero en etiquetar este registro!
|
Ejemplares similares
-
Validation of analysis models on relocation behavior of molten core materials in sodium-cooled fast reactors based on the melt discharge experiment
por: Kai IGARASHI, et al.
Publicado: (2021) -
Experimental analyses by SIMMER-III on duct-wall failure and fuel discharge/relocation behavior
por: Hidemasa YAMANO, et al.
Publicado: (2014) -
Validation study of SAS4A code for the unprotected loss-of-flow accident in an SFR
por: Shinya ISHIDA, et al.
Publicado: (2020) -
Uncertainty analysis of toxic gas leakage accident in cogeneration high temperature gas-cooled reactor
por: Hiroyuki SATO, et al.
Publicado: (2019) -
Development of LORL evaluation method and its application to a loop-type sodium-cooled fast reactor
por: Yuya IMAIZUMI, et al.
Publicado: (2018)