Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Jeong Sik Yim"'
Autor:
Jong Man Park, Young Wook Tahk, Yong Jin Jeong, Kyu Hong Lee, Heemoon Kim, Yang Hong Jung, Boung-Ok Yoo, Young Gwan Jin, Chul Gyo Seo, Seong Woo Yang, Hyun Jung Kim, Jeong Sik Yim, Yeon Soo Kim, Bei Ye, Gerard L. Hofman
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 5, Pp 1044-1062 (2017)
The construction project of the Kijang research reactor (KJRR), which is the second research reactor in Korea, has been launched. The KJRR was designed to use, for the first time, U–Mo fuel. Plate-type U–7 wt.% Mo/Al–5 wt.% Si, referred to as U
Externí odkaz:
https://doaj.org/article/7140bf7e3be84fa780c11713c8904f2f
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 911-919 (2021)
In this paper, the design stress intensity values for the plate-type fuel assembly for research reactor are presented. Through a tensile test, the material properties of the cladding (aluminum alloy 6061) and structural material (aluminum alloy 6061-
Externí odkaz:
https://doaj.org/article/bd3738c7cfaf4512a53013a9d744842b
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 911-919 (2021)
In this paper, the design stress intensity values for the plate-type fuel assembly for research reactor are presented. Through a tensile test, the material properties of the cladding (aluminum alloy 6061) and structural material (aluminum alloy 6061-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::aa0235d5683ba76e4a4af82bd182fd75
http://www.sciencedirect.com/science/article/pii/S1738573320308007
http://www.sciencedirect.com/science/article/pii/S1738573320308007
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 2, Pp 495-500 (2019)
When a new fuel is developed, various mechanical properties are absolutely necessary for a safety analysis of the fuel for the licensing and prediction of its mechanical behavior during operation and accident conditions. In this paper, a mechanically
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::345a606d75744b43cf902e3a4ed67c9b
https://doi.org/10.1016/j.net.2018.10.015
https://doi.org/10.1016/j.net.2018.10.015
Publikováno v:
Annals of Nuclear Energy. 120:581-592
U-Mo/Al plate-type dispersion fuel is a promising candidate for the conversion of research reactor fuels from highly enriched to low-enriched uranium due to its high uranium density. The fuel temperature is a very important parameter, as it affects t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a7cb115313f1c036f7bfa77adf05d6f
https://doi.org/10.1016/j.anucene.2018.06.026
https://doi.org/10.1016/j.anucene.2018.06.026
Autor:
Young Wook Tahk, Hyun-Jung Kim, Boung-Ok Yoo, Yang Hong Jung, Young Gwan Jin, Gerard L. Hofman, Kyu Hong Lee, Seong Woo Yang, Bei Ye, Jeong sik Yim, Jong Man Park, Heemoon Kim, Yeon Soo Kim, Jeong Yong Jin, Chul Gyo Seo
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 5, Pp 1044-1062 (2017)
The construction project of the Kijang research reactor (KJRR), which is the second research reactor in Korea, has been launched. The KJRR was designed to use, for the first time, U–Mo fuel. Plate-type U–7 wt.% Mo/Al–5 wt.% Si, referred to as U
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::116e0921ebaf63e32fd2b3a883d8d20d
https://doi.org/10.1016/j.net.2017.04.003
https://doi.org/10.1016/j.net.2017.04.003
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b6622b0f6c71c64fcfacde0fa35a6b65
https://doi.org/10.13182/t31288
https://doi.org/10.13182/t31288
Publikováno v:
Journal of Nuclear Materials. 473:68-74
The breakaway swelling in U–Mo/Al dispersion fuel is known to be caused by large pore formation enhanced by interaction layer (IL) growth between fuel particles and Al matrix. In this study, a critical IL thickness was defined as a criterion for th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b6237b6fbb11527092d3dc4ed4f14e18
https://doi.org/10.1016/j.jnucmat.2016.02.015
https://doi.org/10.1016/j.jnucmat.2016.02.015
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 4, Pp 529-540 (2014)
In this research, a drop impact analysis of a fuel assembly in a research reactor is carried out to determine whether the fuel plate integrity is maintained in a drop accident. A fuel assembly drop accident is classified based on where the accident o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2432566c04c582c2c4880330b12e5b5c
Publikováno v:
Key Engineering Materials. :186-189
A fuel channel, which is the major structure of a nuclear reactor, is excited by the flow of cooling water during the operation of the nuclear reactor. This flow of cooling water can cause excessive vibration of the structure by the resonance. So, in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2d5fa3f10036c6e3fe27fb4d85a945fa
https://doi.org/10.4028/www.scientific.net/kem.353-358.186
https://doi.org/10.4028/www.scientific.net/kem.353-358.186