Zobrazeno 1 - 10
of 83
pro vyhledávání: '"Dong-Seong Sohn"'
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 3, Pp 576-580 (2017)
A dynamic nanoindentation method was applied to study an Fe-18 at.% Gd alloy as a neutron-absorbing material prepared by vacuum arc-melting and cast in a mold. The Fe-18 at.% Gd cast alloy had a microstructure with matrix phases and an Fe-rich primar
Externí odkaz:
https://doaj.org/article/d18935bf809d4ca7a479f5dd0c87a90c
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 1, Pp 164-168 (2016)
Lean duplex stainless steels with 0.087 wt.% gadolinium (Gd) were inert arc-melted and cast in molds of size 10 mm × 10 mm × 20 mm. The micro-hardnesses of the rolling direction (RD), transverse direction (TD) and short transverse (ST) direction we
Externí odkaz:
https://doaj.org/article/f69dcc03acbf4ea4bd7514453fcd4bbb
FABRICATION OF GD CONTAINING DUPLEX STAINLESS STEEL SHEET FOR NEUTRON ABSORBING STRUCTURAL MATERIALS
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 5, Pp 689-694 (2013)
A duplex stainless steel sheet with 1 wt.% gadolinium was fabricated for a neutron absorbing material with high strength, excellent corrosion resistance, and low cost as well as high neutron absorption capability. The microstructure of the as-cast sp
Externí odkaz:
https://doaj.org/article/7bee2d113741453b85ddafd981715296
Autor:
Hyukjoo Kwon, Matthieu Lemaire, Dong-Seong Sohn, Wonkyeong Kim, Deokjung Lee, Mi Jin Kim, Hee-Jae Lee
Publikováno v:
Annals of Nuclear Energy. 130:107-117
This study presents the development of a new integral-type rack design, characterized by the use of gadolinium (Gd)-containing structure materials that enhances the capacity of spent fuel (SF) pool storage by exploiting the high neutron absorption ca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7cc52a520e7e55de7f143913989085b7
https://doi.org/10.1016/j.anucene.2019.02.027
https://doi.org/10.1016/j.anucene.2019.02.027
Publikováno v:
Annals of Nuclear Energy. 129:233-239
A concept of low-power research reactor (LPRR) with innovative design features is recently proposed by Korea Atomic Energy Research Institute (KAERI) in South Korea. A conventional UO2-Zircaloy 4 fuel rod is proposed to be used as a driver fuel for t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d5744d4f242c6eaaf9ca5f2f7572263c
https://doi.org/10.1016/j.anucene.2019.02.007
https://doi.org/10.1016/j.anucene.2019.02.007
Publikováno v:
Journal of Nuclear Materials. 515:80-90
The ductility of a zirconium alloy cladding tube pre-oxidized at 900, 1000, 1100, and 1200 °C was evaluated after subsequent oxidation at 1000 and 1100 °C by performing ring compression tests. For comparison, ring compression tests were also perfor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::45d647b8683a0cc37e7b3c7862d91613
https://doi.org/10.1016/j.jnucmat.2018.12.032
https://doi.org/10.1016/j.jnucmat.2018.12.032
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 1, Pp 207-213 (2019)
Corrosion and mechanical behavior of the hot-rolled 0.5%Gd-0.8%B-stainless steel to develop a spent nuclear fuel storage material was studied in a simulated nuclear waste treatment condition with rolling condition. The austenite and ferrite phases of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::06924a535ba252e59537f727ef5cc963
https://doi.org/10.1016/j.net.2018.08.017
https://doi.org/10.1016/j.net.2018.08.017
Publikováno v:
Journal of Nuclear Materials. 512:156-168
This study reports the size effect of U-7wt.%Mo (U-7Mo) substrates on the thickness, morphology, and crystallographic properties of Mo and ZrN coatings as a diffusion barrier. Each the coating was deposited on 45–90 μm sized U-7Mo particles by dir
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d3b4f1b79d6329de842849cfc295d56c
https://doi.org/10.1016/j.jnucmat.2018.10.012
https://doi.org/10.1016/j.jnucmat.2018.10.012
Publikováno v:
Journal of Nuclear Materials. 507:347-359
Zirconium nitride (ZrN) coating is used as a diffusion barrier layer on U-Mo powder surfaces to suppress interdiffusion layer formation. However, it has been reported that the structural integrity of the coating did not remain intact after fuel plate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4483330dc9df2e0bf909c5be0ea84f6a
https://doi.org/10.1016/j.jnucmat.2018.05.019
https://doi.org/10.1016/j.jnucmat.2018.05.019
Publikováno v:
Corrosion Science. 139:410-420
Zr-1Nb-1Sn-0.1Fe alloy was pre-oxidised at 1200 °C and subsequently oxidised at 1012, 1100, and 1200 °C. The preformed oxide enhanced the oxidation resistance at 1012 and 1100 °C, but not at 1200 °C. The microstructures of the preformed oxides su
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6618207375bef76e0149eca7d3a163bd
https://doi.org/10.1016/j.corsci.2018.05.022
https://doi.org/10.1016/j.corsci.2018.05.022