Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Young-Wook Tahk"'
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 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://doaj.org/article/d6aa222e2b234db28290aaaf6bf0b8e0
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:
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:
Progress in Nuclear Energy. 91:153-158
The effect of the oxide layer formed on the mini fuel plates is studied to evaluate fuel centerline temperature. For a part of U-Mo fuel qualification program, mini fuel plates, double-stacked as upper and lower plates, will be irradiated in the HANA
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5248d44b4c8450f56284ef68199f4da9
https://doi.org/10.1016/j.pnucene.2016.04.013
https://doi.org/10.1016/j.pnucene.2016.04.013
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. 43:499-508
The paper briefs a fuel performance code, COSMOS, which can be utilized for an analysis of the thermal behavior and fission gas release of fuel, up to a high burnup. Of particular concern are the models for the fuel thermal conductivity, the fission
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ed20a47eb61de1fb32043e331fea81b5
https://doi.org/10.5516/net.2011.43.6.499
https://doi.org/10.5516/net.2011.43.6.499
Publikováno v:
Journal of Nuclear Materials. 414:320-323
This paper evaluated the effects of porosity on the effective thermal conductivity of UO2 fuel by combining the Potts model and the finite difference method (FDM). Two types of microstructures representing irradiated UO2 microstructures were simulate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::57a44143e984af603a224e6309f3d85f
https://doi.org/10.1016/j.jnucmat.2011.04.059
https://doi.org/10.1016/j.jnucmat.2011.04.059
Publikováno v:
Journal of Nuclear Materials. 405:33-43
A fission gas release (FGR) model was developed by using an artificial neural network method to predict fission gas release in UO2 fuel under reactivity initiated accident (RIA) conditions. Based on the test data obtained in the CABRI test reactor an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be12d4735540b045f07cc3a03997bec5
https://doi.org/10.1016/j.jnucmat.2010.07.032
https://doi.org/10.1016/j.jnucmat.2010.07.032