Zobrazeno 1 - 10
of 10
pro vyhledávání: '"JaeHyun Ham"'
Autor:
Sang Ho Kim, Jaehyun Ham, Byeonghee Lee, Sung Il Kim, Hwan Yeol Kim, Rae-Joon Park, Jaehoon Jung
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4551-4559 (2022)
The aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART. First, a severe accident sequence under conservative conditions
Externí odkaz:
https://doaj.org/article/379b78f90d334acf9c9a28309d9aebc1
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 2, Pp 402-409 (2019)
When a loss of coolant accident (LOCA) occurs in a nuclear power plant, accident scenarios which can prevent core damage are defined based on break size. Current probabilistic safety assessment evaluates that core damage can be prevented under small-
Externí odkaz:
https://doaj.org/article/2fcf662ece094b87abd3b4e0ae410907
Autor:
Jaehyun Ham, Sang Ho Kim, Sung Il Kim, Byeonghee Lee, Jong-Hwa Park, Rae-Joon Park, Jaehoon Jung
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2021 (2021)
The SMART is a system-integrated modular reactor in which a nuclear steam supply system with a thermal power of 365 MW is contained inside of the reactor vessel. Although the probability is very low, the reactor core can be damaged during a small bre
Externí odkaz:
https://doaj.org/article/c152b8ee1f704d8d868dabceac9df99e
Autor:
Mirae Yun, Robby Christian, Bo Gyung Kim, Belal Almomani, Jaehyun Ham, Sanghoon Lee, Hyun Gook Kang
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 4, Pp 721-733 (2017)
When temporary spent fuel storage pools at nuclear power plants reach their capacity limit, the spent fuel must be moved to an alternative storage facility. However, radioactive materials must be handled and stored carefully to avoid severe consequen
Externí odkaz:
https://doaj.org/article/7bf7e8a40e31468da736b28d378c0d5b
Publikováno v:
International Journal of Distributed Sensor Networks, Vol 13 (2017)
In wireless sensor networks, the accurate estimation of distances between sensor nodes is essential. In addition to the distance information available for immediate neighbors within a sensing range, the distance estimation of two-hop neighbors can be
Externí odkaz:
https://doaj.org/article/77124c5544244bd2807d69cc6e707673
Autor:
JinHo Song, DongGun Son, JaeHyun Ham, JunHo Bae, SungWon Bae, Kwangsoon Ha, ByungJo Kim, Sun Hong Yoon, BubDong Chung, SoonHo Park, ChangHwan Park, JaeHwan Park, YuJung Choi
Publikováno v:
Nuclear Engineering and Design. 404:112181
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2bf07397c22bb027e9cba825431b6008
https://doi.org/10.1016/j.nucengdes.2023.112181
https://doi.org/10.1016/j.nucengdes.2023.112181
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 2, Pp 402-409 (2019)
When a loss of coolant accident (LOCA) occurs in a nuclear power plant, accident scenarios which can prevent core damage are defined based on break size. Current probabilistic safety assessment evaluates that core damage can be prevented under small-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e57364f3357f33d87790755075ad03d3
http://www.sciencedirect.com/science/article/pii/S1738573318306089
http://www.sciencedirect.com/science/article/pii/S1738573318306089
Autor:
Byeonghee Lee, Sang-Ho Kim, Sung Il Kim, Jaehyun Ham, Jong-Hwa Park, Rae-Joon Park, Jaehoon Jung
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2021 (2021)
The SMART is a system-integrated modular reactor in which a nuclear steam supply system with a thermal power of 365 MW is contained inside of the reactor vessel. Although the probability is very low, the reactor core can be damaged during a small bre
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0c0ffcba23cea8c1a87ea331e8c4b723
Autor:
Jaehyun Ham, Hyun Gook Kang, Sang Hoon Lee, Robby Christian, Belal Almomani, Bo Gyung Kim, Mirae Yun
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 4, Pp 721-733 (2017)
When temporary spent fuel storage pools at nuclear power plants reach their capacity limit, the spent fuel must be moved to an alternative storage facility. However, radioactive materials must be handled and stored carefully to avoid severe consequen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::33e34e9a136906e28f6be5231b06b171
https://doi.org/10.1016/j.net.2017.01.017
https://doi.org/10.1016/j.net.2017.01.017
Publikováno v:
Nuclear Engineering and Design. 374:111061
Severe accident mitigation technology was developed and evaluated for a small integral reactor of SMART. The containment pressure and hydrogen behavior were analyzed using MELCOR computer code (Sandia National Laboratory, 2018) in the SBO (Station Bl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dc9706247bb638d28aeb67d7ee0e7a20
https://doi.org/10.1016/j.nucengdes.2021.111061
https://doi.org/10.1016/j.nucengdes.2021.111061