Zobrazeno 1 - 10
of 42
pro vyhledávání: '"Young-Seok Bang"'
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 4, Pp 481-488 (2014)
An analysis of the uncertainty quantification related to LBLOCA using the Monte-Carlo calculation has been performed and compared with the tolerance level determined by the Wilks’ formula. The uncertainty range and distribution of each input parame
Externí odkaz:
https://doaj.org/article/6b07ef5acef04e40b07a933e53e71023
Publikováno v:
Energies, Vol 14, Iss 5, p 1504 (2021)
Concern over the asymmetric phenomena in the core region has increased considering safety issues that are highly possible to reduce the thermal margin significantly in nuclear power plants. Since the seized reactor coolant pump (RCP) accident of an a
Externí odkaz:
https://doaj.org/article/308c1a0abf234bed85bacadd7d1f15b4
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2f3261c447c5d7c726f9b0ca8a75d540
https://doi.org/10.2139/ssrn.4029644
https://doi.org/10.2139/ssrn.4029644
Autor:
Joosuk Lee, Young Seok Bang
Publikováno v:
Annals of Nuclear Energy. 134:350-358
The present study discusses a model of Large Break Loss-Of-Coolant Accident (LBLOCA) calculation using the multiple fuel rods modeling scheme which was developed to consider the fuel rods with different burnup in preparation for the recently proposed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::93b28651b2efca7308c0d6e6508b094f
https://doi.org/10.1016/j.anucene.2019.06.023
https://doi.org/10.1016/j.anucene.2019.06.023
Publikováno v:
Journal of Thermal Science and Technology, Vol 4, Iss 3, Pp 382-390 (2009)
For the purpose of evaluation of debris transport on containment floor of nuclear power plants, a model to calculate the transient flow field on the floor is developed. Two-dimensional shallow water equation (SWE) is solved by finite volume method (F
Externí odkaz:
https://doaj.org/article/65adea966209415b832aeb40b93c0baa
Autor:
Joosuk Lee, Young Seok Bang
Publikováno v:
Nuclear Engineering and Design. 397:111945
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9d4d4c3d2a3a1689f675cb4f53873e33
https://doi.org/10.1016/j.nucengdes.2022.111945
https://doi.org/10.1016/j.nucengdes.2022.111945
Autor:
Young Seok Bang, Joosuk Lee
Publikováno v:
International Journal of Energy Production and Management. 4:86-95
Since the revision of the requirements to consider the effect of fuel burnup on emergency core cooling system performance was proposed, flow blockage in reactor core has been one of the important issues in the thermal-hydraulic analysis of loss-of-co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::85bd67937d913a91a386ac0a0726a0bf
https://doi.org/10.2495/eq-v4-n1-86-95
https://doi.org/10.2495/eq-v4-n1-86-95
Publikováno v:
Nuclear Engineering and Design. 392:111770
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::611031cbcbcc8bf409f1687fc851a5d6
https://doi.org/10.1016/j.nucengdes.2022.111770
https://doi.org/10.1016/j.nucengdes.2022.111770
Autor:
Young Seok Bang, Seung Hun Yoo
Publikováno v:
Annals of Nuclear Energy. 112:143-149
To predict the performance of the Safety Injection Tank (SIT) with Fluidic Device (FD) of APR1400 (Advance Power Reactor 1400) and its effect on Large Break Loss-of-Coolant Accident (LBLOCA) of APR1400, a model using two flow paths within the SIT is
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2eaf8f08d0eed2238f607f6bf8b6ff0
https://doi.org/10.1016/j.anucene.2017.09.047
https://doi.org/10.1016/j.anucene.2017.09.047