Zobrazeno 1 - 10
of 44
pro vyhledávání: '"SUNG WON BAE"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2023 (2023)
As an integrated computer code development for severe accident sequence analysis in Korea, CINEMA has been developing from an initiation event to a containment failure. The CINEMA computer code is composed of CSPACE, SACAP, and SIRIUS, which are capa
Externí odkaz:
https://doaj.org/article/2c5ec480b71542f8806460f4f0d9eb27
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 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:
Nuclear Engineering and Technology, Vol 54, Iss 1, Pp 152-161 (2022)
We analyzed mitigation strategies for steam generator tube rupture (SGTR) accidents using MARS code under both full-power and low-power and shutdown (LPSD) conditions. In general, there are two approaches to mitigating SGTR accidents: supplementing t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::60e7f66bde019f61d016fe05368d3b62
https://doi.org/10.1016/j.net.2021.07.032
https://doi.org/10.1016/j.net.2021.07.032
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
Publikováno v:
Annals of Nuclear Energy. 115:138-153
The safety analysis of nuclear power plants has been performed using conservative approach based on conservative assumptions and boundary conditions to evaluate the safety margin of plant operation. However, this conservative approach could lead to u
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c227e030895b476bf579ee4f38c8b3fd
https://doi.org/10.1016/j.anucene.2018.01.033
https://doi.org/10.1016/j.anucene.2018.01.033
Publikováno v:
Energy. 147:1030-1043
To develop a cycle operation strategy for a supercritical carbon dioxide (S-CO 2 ) Brayton cycle, a series of MARS code simulation results were compared to experimental data from an SCIEL compressor test, which was collected at both component and who
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6b13b8c816fc77641d657ead165f8ec6
https://doi.org/10.1016/j.energy.2017.12.092
https://doi.org/10.1016/j.energy.2017.12.092
Publikováno v:
Nuclear Engineering and Design. 312:239-247
Ballooning of the fuel rods has been an important issue, since it can influence the coolability of the rod bundle in a large-break loss-of-coolant accident (LBLOCA). Numerous past studies have investigated the effect of blockage geometry on the heat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8f4e6e9fe21fc655b034255f7939bd92
https://doi.org/10.1016/j.nucengdes.2016.08.034
https://doi.org/10.1016/j.nucengdes.2016.08.034
Publikováno v:
Nuclear Engineering and Design. 375:111090
An empirical correlation has been developed to accurately predict the onset of flow instability (OFI) in narrow rectangular channels under a wide thermal–hydraulic condition. The 242 sets of OFI experiments were collected, which cover a wide range
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bb2393f7ebe97a9299c350149704597e
https://doi.org/10.1016/j.nucengdes.2021.111090
https://doi.org/10.1016/j.nucengdes.2021.111090
Publikováno v:
Annals of Nuclear Energy. 149:107735
The demonstration of inherent safety during design extension conditions is essential for the design of an SFR. In this study, a best estimate plus uncertainty approach is applied to the pump run-up test performed in EBR-II. The initial test condition
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fae133705e6568915de4ff555bba5ac0
https://doi.org/10.1016/j.anucene.2020.107735
https://doi.org/10.1016/j.anucene.2020.107735