Zobrazeno 1 - 10
of 32
pro vyhledávání: '"Hiroyuki Nishino"'
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00409-23-00409 (2023)
The effectiveness evaluation of safety measures against severe accident is necessary for restart of experimental sodium-cooled fast reactor Joyo in Japan. These safety measures correspond to those in defense-in-depth (DiD) level 4. In the previous st
Externí odkaz:
https://doaj.org/article/f196bbcc9d334d85a636d119882fdac7
Publikováno v:
Mechanical Engineering Journal, Vol 10, Iss 4, Pp 22-00387-22-00387 (2023)
For nuclear power plants, probabilistic risk assessment (PRA) should be performed not only against earthquake and tsunami, which are critical events especially in Japan, but also other external hazards such as strong wind. The aim of the present stud
Externí odkaz:
https://doaj.org/article/ff74f282dd6749fb967f480c34d500ae
Publikováno v:
Mechanical Engineering Journal, Vol 5, Iss 4, Pp 18-00079-18-00079 (2018)
A probabilistic risk assessment (PRA) should be performed not only for earthquake and tsunami which are major natural events in Japan but also for other natural external hazards. However, PRA methodologies for other external hazards and their combina
Externí odkaz:
https://doaj.org/article/587838137ba7491891b6e43ae2036533
Publikováno v:
Mechanical Engineering Journal, Vol 5, Iss 4, Pp 18-00093-18-00093 (2018)
This paper describes the development of a probabilistic risk assessment (PRA) methodology against a combination hazard of strong wind and rainfall. In this combination hazard PRA, a hazard curve is evaluated in terms of maximum instantaneous wind spe
Externí odkaz:
https://doaj.org/article/94f1d9708ac54684830761cf2f2b1eda
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 83, Iss 847, Pp 16-00392-16-00392 (2016)
The objective of this study is to develop probabilistic risk assessment (PRA) methodology for combination event of low temperature and snow by focusing on decay heat removal system (DHRS) of sodium-cooled fast reactor. For this combination event, ann
Externí odkaz:
https://doaj.org/article/22d2cd7e99ca41d4bb3c51bf07379395
Publikováno v:
Mechanical Engineering Journal, Vol 5, Iss 4, Pp 18-00079-18-00079 (2018)
A Probabilistic Risk Assessment (PRA) should be performed not only for earthquake and tsunami which are major natural events in Japan, but also for other natural external hazards. However, PRA methodologies for other external hazards and their combin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::91a85bcb7c3d502fb91183a19438c83f
https://doi.org/10.1299/mej.18-00079
https://doi.org/10.1299/mej.18-00079
Publikováno v:
Mechanical Engineering Journal, Vol 5, Iss 4, Pp 18-00093-18-00093 (2018)
This paper describes the development of a probabilistic risk assessment (PRA) methodology against a combination hazard of strong wind and rainfall. In this combination hazard PRA, a hazard curve is evaluated in terms of maximum instantaneous wind spe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::07d2778b9be61b1c380d2dd423e27fad
https://doi.org/10.1299/mej.18-00093
https://doi.org/10.1299/mej.18-00093
Publikováno v:
Nuclear Engineering and Design. 308:86-95
This paper describes snow probabilistic risk assessment (PRA) methodology development through external hazard and event sequence evaluations mainly in terms of decay heat removal (DHR) function of a sodium-cooled fast reactor (SFR). Using recent 50-y
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::916abcee4cd7b7a1a5bd3b42e6fa8f69
https://doi.org/10.1016/j.nucengdes.2016.08.006
https://doi.org/10.1016/j.nucengdes.2016.08.006
Autor:
Shigeki OKAMURA, Takahiro KINOSHITA, Hiroyuki NISHINO, Hidemasa YAMANO, Kenichi KURISAKA, Satoshi FUTAGAMI, Tsuyoshi FUKASAWA
Publikováno v:
The Proceedings of the National Symposium on Power and Energy Systems. :A135
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9bd6f63e8f273e3079b774c2caddc192
https://doi.org/10.1299/jsmepes.2021.25.a135
https://doi.org/10.1299/jsmepes.2021.25.a135
Publikováno v:
Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management.
Spent fuels are transferred from a reactor core to a spent fuel pool through an external vessel storage tank (EVST) filled with sodium in sodium-cooled fast reactors in Japan. This paper describes identification of dominant accident sequences leading
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::08344b93d65d9d30fc0a27281c42f7d3
https://doi.org/10.1115/icone26-81079
https://doi.org/10.1115/icone26-81079