Zobrazeno 1 - 10
of 37
pro vyhledávání: '"Chiwoong Choi"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2013 (2013)
Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor syste
Externí odkaz:
https://doaj.org/article/7fd7a68b6a7e49288ab731fdccbc995f
Publikováno v:
Annals of Nuclear Energy. 117:333-342
KAERI has developed a prototype Gen-IV sodium cooled fast reactor (PGSFR), which is a pool type and metallic fueled fast reactor in Korea. Recently, a reactor vault cooling system (RVCS) was designed as a mitigation feature for severe accidents in th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::49a4ce6a4446e0c29bbfe7434e4a2878
https://doi.org/10.1016/j.anucene.2018.02.026
https://doi.org/10.1016/j.anucene.2018.02.026
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:
Annals of Nuclear Energy. 110:1232-1241
In this research, sensitivity and uncertainty analyses for 23 parameters were performed for unprotected loss of flow (ULOF) for the prototype Gen-IV sodium-cooled fast reactor (PGSFR) by using the parallel computing platform integrated for uncertaint
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::615d21afec9ccf3239a2310c886e4d16
https://doi.org/10.1016/j.anucene.2017.08.041
https://doi.org/10.1016/j.anucene.2017.08.041
Autor:
Chulmin Park, Ho Jae Kwak, Narayan Pandurang Sapkal, Chiwoong Choi, Jiwoo Hong, Moo Hwan Kim, Dong In Yu
Publikováno v:
Langmuir : the ACS journal of surfaces and colloids. 35(10)
In this study, the existing knowledge on the wetting criterion, that is, the intrinsic contact angle, for distinguishing between hydrophilic and hydrophobic textured surfaces is verified experimentally. A precise apparent contact angle is measured on
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e4ef114b22fceef8cf3c714a52ffb6a0
https://pubmed.ncbi.nlm.nih.gov/30776243
https://pubmed.ncbi.nlm.nih.gov/30776243
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
Publikováno v:
Nuclear Engineering and Design. 308:269-282
The MARS-LMR code has been developed by the Korea Atomic Energy Research Institute (KAERI) to analyze transients in a pool-type sodium-cooled fast reactor (SFR). Currently, KAERI is developing a prototype Gen-IV SFR (PGSFR) with metallic fuel. The de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b971bc7bbf9be2c66cc63762c7b6483
https://doi.org/10.1016/j.nucengdes.2016.08.044
https://doi.org/10.1016/j.nucengdes.2016.08.044
Autor:
Kwi-Seok Ha, Taekyeong Jeong, Seung Won Lee, Sang June Ahn, Seok Hun Kang, Won-Pyo Chang, Kwi Lim Lee, Chiwoong Choi, Jae-Ho Jeong, Jaewoon Yoo
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 5, Pp 1071-1082 (2016)
Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR). To assess the effectiveness of the inherent safety features of the PGSFR, the system transie
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2e6722346e0b9f95f06ff0667f4a96fd
Publikováno v:
Annals of Nuclear Energy. 96:422-431
KAERI has been developing a prototype Gen-IV sodium cooled fast reactor (PGSFR), which is a pool type and metallic fueled fast reactor in Korea. Unprotected event is an accident accompanying by failure of a reactor protection system. PGSFR is feature
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0944acbc357fa27e9c47ddc12e9dfd26
https://doi.org/10.1016/j.anucene.2016.06.035
https://doi.org/10.1016/j.anucene.2016.06.035
Autor:
Chiwoong Choi, Kwi-Seok Ha
Publikováno v:
Nuclear Engineering and Design. 307:10-29
KAERI has designed a prototype Gen-IV SFR (PGSFR) with metallic fuel. And the safety analysis code for the PGSFR, MARS-LMR, is based on the MARS code, and supplemented with various liquid metal related features including sodium properties, heat trans
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7bbe1864326986dca631f8723ebad2b3
https://doi.org/10.1016/j.nucengdes.2016.05.026
https://doi.org/10.1016/j.nucengdes.2016.05.026