Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Dong-Gun Son"'
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3990-4002 (2021)
CSPACE (Core meltdown, Safety and Performance Analysis CodE for nuclear power plants) for a simulation of severe accident progression in a Pressurized Water Reactor (PWR) is developed by coupling of verified system thermal hydraulic code of SPACE (Sa
Externí odkaz:
https://doaj.org/article/2a5e4a0fb2a145b3b6b63b198fecfbf7
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 8, Pp 1916-1938 (2019)
The objective of this paper is to discuss the modeling principles of phenomena governing core degradation/melting and in-vessel melt relocation during severe accidents in light water reactors. The proposed modeling approach has been applied in the de
Externí odkaz:
https://doaj.org/article/af718b72f5e741bf98d570ef8ccbff58
Autor:
YuJung Choi, Sung Won Bae, Dong-Gun Son, Bub-Dong Chung, JinHo Song, JunHo Bae, Kwang-Soon Ha
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3990-4002 (2021)
CSPACE (Core meltdown, Safety and Performance Analysis CodE for nuclear power plants) for a simulation of severe accident progression in a Pressurized Water Reactor (PWR) is developed by coupling of verified system thermal hydraulic code of SPACE (Sa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0fe5938ea5eef51fa78bde0c0badc03d
https://doi.org/10.1016/j.net.2021.06.039
https://doi.org/10.1016/j.net.2021.06.039
Autor:
JinHo Song, Dong Gun Son, JunHo Bae, SungWon Bae, KwangSoon Ha, ByungJo Kim, BubDong Chung, SoonHo Park, Changwan Park, Jaehwan Park, YuJung Choi
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bc91982a60bfa6a08bc40bcc28df687e
https://doi.org/10.2139/ssrn.4264421
https://doi.org/10.2139/ssrn.4264421
Publikováno v:
Annals of Nuclear Energy. 182:109598
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c38e8ca7e91aacbd30fce1d74677937b
https://doi.org/10.1016/j.anucene.2022.109598
https://doi.org/10.1016/j.anucene.2022.109598
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 8, Pp 1916-1938 (2019)
The objective of this paper is to discuss the modeling principles of phenomena governing core degradation/melting and in-vessel melt relocation during severe accidents in light water reactors. The proposed modeling approach has been applied in the de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::00ae815a356fc81823a02f2bbdc10ecd
https://doi.org/10.1016/j.net.2019.06.008
https://doi.org/10.1016/j.net.2019.06.008
Publikováno v:
Nuclear Engineering and Design. 384:111447
The complexity of phenomena occurring during severe accidents in nuclear reactors, combined with a limited amount of experimental evidence, do not allow for formulating detailed reliable models or making highly accurate predictions of accident progre
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cd20eecff725ffacbee3450a02ee0895
https://doi.org/10.1016/j.nucengdes.2021.111447
https://doi.org/10.1016/j.nucengdes.2021.111447
Autor:
Dong Gun Son, Rae Joon Park, Michael Z. Podowski, Jun Ho Bae, JinHo Song, Dong Ha Kim, Jong Hwa Park, Jongtae Kim
Publikováno v:
Nuclear Engineering and Design. 320:258-268
As a part of the integrated severe accident code development project in Korea, KAERI (Korea Atomic Energy Research Institute) has been developing a stand-alone severe accident analysis code, COMPASS (COre Meltdown Progression Accident Simulation Soft
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::39949367c444db96732c6015fd2d3d63
https://doi.org/10.1016/j.nucengdes.2017.05.030
https://doi.org/10.1016/j.nucengdes.2017.05.030
Autor:
Jong Yeob Jeong, Jun Ho Bae, Dong Gun Son, Sang Ho Kim, Jun Young Kang, Ki Hyun Kim, Yong Mann Song
Publikováno v:
Annals of Nuclear Energy. 150:107820
Due to the demands for an accurate and realistic severe accident code in the PHWR safety analysis, a new severe accident code called CAISER is being developed at Korea Atomic Energy Research Institute (KAERI). The CAISER code simulates core degradati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0cdfb066703d671b0f1c91adcb7026e0
https://doi.org/10.1016/j.anucene.2020.107820
https://doi.org/10.1016/j.anucene.2020.107820