Zobrazeno 1 - 10
of 10
pro vyhledávání: '"Eishiro HIGO"'
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6e3df0a4f15dc33c7e48787c8ceca094
https://doi.org/10.1080/00223131.2023.2172086
https://doi.org/10.1080/00223131.2023.2172086
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:
Reliability Engineering & System Safety. 216:107912
This paper presents a model to quantify the economic value gained by implementation of an inspection and preventive maintenance program for managing an ageing component population. The proposed approach is a refinement of the Bayesian value of inform
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7096307b753ef9fe8be448a26499f2c1
https://doi.org/10.1016/j.ress.2021.107912
https://doi.org/10.1016/j.ress.2021.107912
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::69b6f6cd8f0fb871dc2d34377cc9c048
https://doi.org/10.1016/j.ress.2021.107802
https://doi.org/10.1016/j.ress.2021.107802
Publikováno v:
Expert Systems with Applications. 83:379-395
Evacuation and rescue principles under life-threatening situations are clarified.A multi-agent simulation approach based on the Vitae System model is presented.A person's ability is characterized by survivability, vitality, and conviviality.Three str
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb4e2b767e077ebb8c94998bd61ae201
https://doi.org/10.1016/j.eswa.2017.04.034
https://doi.org/10.1016/j.eswa.2017.04.034
Autor:
Mahesh D. Pandey, Eishiro Higo
Publikováno v:
Journal of Integrated Disaster Risk Management. 5:153-166
Since the disastrous earthquake and tsunami on March 11, 2011, Japanese people have discussed the question of “How safe is safe enough?” The risk of spills from nuclear power plants is one of the major issues, and the government has shut down alm
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::72f8c1bf0873eaec4e5cfda4d50149a9
https://doi.org/10.5595/idrim.2015.0109
https://doi.org/10.5595/idrim.2015.0109
Autor:
Mahesh D. Pandey, Eishiro Higo
Publikováno v:
Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 24th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Electric Power Research Institute (EPRI) Creep Fatigue Workshop.
A sample size determination method is developed for a two-action problem that represents a component maintenance scenario requiring current state estimation. For safety and generation efficiency, each component of a nuclear power plant must be regula
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1640246946b915a8f861828df5cb4a29
https://doi.org/10.1115/pvp2016-63932
https://doi.org/10.1115/pvp2016-63932
Autor:
Mahesh D. Pandey, Eishiro Higo
Publikováno v:
International Journal of Quality Engineering and Technology. 7:128
A complex engineering system like a nuclear power reactor consists of a large variety and number of engineering components. As a part of a component aging management program, the diagnostic inspections of various component populations are performed t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0eaf50a60dfa4089c653844f5b8c5406
https://doi.org/10.1504/ijqet.2018.097341
https://doi.org/10.1504/ijqet.2018.097341
Publikováno v:
SMC
The process of evacuation and rescuing in underground flooding has been modeled, simulated and analyzed based on the Vitae System Model. Based on our previous work, some extensions have been made to deal with the process of self-evacuation to rescuin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3aec8c8d67240dd55176397f70cbb418
https://doi.org/10.1109/icsmc.2011.6084129
https://doi.org/10.1109/icsmc.2011.6084129