Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Hiromichi Miura"'
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00415-23-00415 (2024)
It is crucial to perform a multi-unit probabilistic risk assessment (MUPRA) to identify the risk of a nuclear power station (Hereafter referred to as site) with multiple units. External hazards play a significant role in MUPRA because they simultaneo
Externí odkaz:
https://doaj.org/article/c6256a646a7446ef89db68ddbce42ea1
Publikováno v:
Journal of Nuclear Science and Technology. :1-21
Autor:
Hiromichi Miura
Publikováno v:
Journal of the Atomic Energy Society of Japan. 63:60-64
This study provides an inter-unit common cause failure (CCF) analysis method utilizing the international CCF database. The inter-unit CCF is one of the possible major risks at a site with multiple units. The conventional CCF analysis is based on the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::def650b9e0d4770bd3cd40372716683e
https://doi.org/10.1115/1.0000449v
https://doi.org/10.1115/1.0000449v
Publikováno v:
Journal of the Atomic Energy Society of Japan. 60:687-691
Publikováno v:
Reliability Engineering & System Safety. 215:107802
Inter-unit common-cause failure (CCF) analysis is one of the technical issues for a probabilistic risk assessment for multiple nuclear reactors in a site. It is because inter-unit CCF events are rare and the symmetric assumption in intraunit CCF anal
Publikováno v:
Transactions of the Atomic Energy Society of Japan. 16:89-99
Autor:
Hiromichi Miura, Shota Soga
Publikováno v:
The Proceedings of Mechanical Engineering Congress, Japan. 2019:S08102
Autor:
Hiromichi Miura, Ryou Inomata
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :2139
Autor:
Yuji Kosaka, Takaaki Kitagawa, Nobuo Nakae, Toshikazu Baba, Shigeru Kurematsu, Hiromichi Miura, Hidetoshi Akiyama, Katsuichiro Kamimura, Aya Yoshino
Publikováno v:
Journal of Nuclear Materials. 440:515-523
Thermal property is important because it controls fuel behavior under irradiation. The thermal property change at high burnup of more than 70 GWd/t is examined. Two kinds of MOX fuel rods, which were fabricated by MIMAS and SBR methods, and one refer