Development of LORL evaluation method and its application to a loop-type sodium-cooled fast reactor
The loss-of-reactor-level (LORL) where the coolant circulation path is lost is one of the important accident types of loss-of-heat-removal-system (LOHRS) in loop-type sodium-cooled fast reactors (SFRs). Due to the non-negligible possibility obtained by probabilistic risk assessment (PRA), pipe failu...
Guardado en:
Autores principales: | Yuya IMAIZUMI, Fumiaki YAMADA, Mitsuhiro ARIKAWA, Hiroki YADA, Yoshitaka FUKANO |
---|---|
Formato: | article |
Lenguaje: | EN |
Publicado: |
The Japan Society of Mechanical Engineers
2018
|
Materias: | |
Acceso en línea: | https://doaj.org/article/a486bebe15b44c138dfe0034be268f2d |
Etiquetas: |
Agregar Etiqueta
Sin Etiquetas, Sea el primero en etiquetar este registro!
|
Ejemplares similares
-
Preliminary analysis of the post-disassembly expansion phase and structural response under unprotected loss of flow accident in prototype sodium cooled fast reactor
por: Yuichi ONODA, et al.
Publicado: (2017) -
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) -
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) -
Development of a Fast-Spectrum Self-Powered Neutron Detector for Molten Salt Experiments in the Versatile Test Reactor
por: Goetz K. C., et al.
Publicado: (2021)