Zobrazeno 1 - 10
of 37
pro vyhledávání: '"Seung-Cheol Jang"'
Autor:
Seung-Cheol Jang
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 7, Pp 1099-1105 (2018)
How to choose defaults in risk-informed regulations depends on the conservatism implicated in regulatory defaults. Without a universal agreement on the approaches dealing with the conservatism of defaults, however, the desirability of conservatism in
Externí odkaz:
https://doaj.org/article/0b60473857f645a3950b788dc8624121
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 1, Pp 59-65 (2015)
Background: After the Fukushima accident, the importance of hazard analysis for extreme external events was raised. Methods: To analyze typhoon-induced hazards, which are one of the significant disasters of East Asian countries, a statistical analysi
Externí odkaz:
https://doaj.org/article/fc9d5a9503794a8ca05f785213dc7046
Autor:
GEE-YONG PARK, SEUNG CHEOL JANG
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 1, Pp 55-62 (2014)
A method for estimating software reliability for nuclear safety software is proposed in this paper. This method is based on the software reliability growth model (SRGM), where the behavior of software failure is assumed to follow a non-homogeneous Po
Externí odkaz:
https://doaj.org/article/ae1c6e714abe4edea8a49877c6541b3d
Autor:
Yoon-Hwan Lee, Seung-Cheol Jang
Publikováno v:
Annals of Nuclear Energy. 161:108455
In this paper, the difference between the current design and a newly proposed method for the injection of supplementary cooling water into a nuclear research reactor in response to the rupture of a beam tube is investigated. Here, the newly proposed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fee8b0c2eaff8ff68dfc0fb53d235d80
https://doi.org/10.1016/j.anucene.2021.108455
https://doi.org/10.1016/j.anucene.2021.108455
Publikováno v:
Annals of Nuclear Energy. 85:36-46
After the Fukushima accident, a couple of novel issues have raised in terms of the safety assessment of nuclear power plants (NPPs). This means that the performance of human operators should be properly evaluated under an extreme event. However, it i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7909ee0a0081f9f439d8d80498edaa3e
https://doi.org/10.1016/j.anucene.2015.03.053
https://doi.org/10.1016/j.anucene.2015.03.053
Publikováno v:
Nuclear Engineering and Design. 289:195-207
This paper presents the process and results of a risk assessment for a main control board (MCB) fire using fire dynamics simulator (FDS). A decision tree for evaluating the risk of a MCB fire was proposed to systematically determine the MCB fire scen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d5ce94e470dea56aa3d955e0f1e2773b
https://doi.org/10.1016/j.nucengdes.2015.04.030
https://doi.org/10.1016/j.nucengdes.2015.04.030
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 1, Pp 59-65 (2015)
Background After the Fukushima accident, the importance of hazard analysis for extreme external events was raised. Methods To analyze typhoon-induced hazards, which are one of the significant disasters of East Asian countries, a statistical analysis
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::985066337a5967a42f30b568fc2b9ae8
https://doi.org/10.1016/j.net.2014.08.001
https://doi.org/10.1016/j.net.2014.08.001
Publikováno v:
Journal of the Korean Society of Safety. 29:199-207
In this paper, to systematically assess the abandonment risk of main control room (MCR) fire, fire simulations with Fire Dynamics Simulator were performed and abandonment probabilities were estimated for the MCR bench-board fire of domestic reference
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7175cfad3506237784dae5ab72a00f27
https://doi.org/10.14346/jkosos.2014.29.4.199
https://doi.org/10.14346/jkosos.2014.29.4.199
Publikováno v:
Journal of Nuclear Science and Technology. 50:1110-1126
This paper presents major design factors of the computerized procedure system (CPS) by task characteristics/requirements, with individual relative weight evaluated by the analytic hierarchy process (AHP) technique, for inclusion into human reliabilit
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27bba6f163f4109bafaa575f62f8c47d
https://doi.org/10.1080/00223131.2013.836065
https://doi.org/10.1080/00223131.2013.836065
Publikováno v:
Nuclear Technology. 183:107-118
This paper describes a method of estimating the probability of failure for trip-functioning software of a fully digitalized reactor protection system. The Bayesian inference is used to estimate and...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::da41754cf11ce1c92cdd042225fe538d
https://doi.org/10.13182/nt13-a16996
https://doi.org/10.13182/nt13-a16996