Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Soon Dal Park"'
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 7, Pp 924-933 (2015)
The correlation of the isotopic composition of uranium, plutonium, neodymium, and cesium with the burnup for high burnup pressurized water reactor fuels irradiated in nuclear power reactors has been experimentally investigated. The total burnup was d
Externí odkaz:
https://doaj.org/article/5ab3f4e92cca44159f7514a74ff4e6c5
Publikováno v:
Journal of The Korean Society For Urban Railway. 5:1045-1051
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4e8a7ea10b32f932ff3fadf64a0a7f97
https://doi.org/10.24284/jkosur.2017.12.5.4.1045
https://doi.org/10.24284/jkosur.2017.12.5.4.1045
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 312:517-521
We quantitatively measured the amounts and isotopic distributions of the released and retained fission gases (Kr and Xe) from two irradiated metallic fuels (U–10Zr and U–10Zr–5Ce) at approximately 2.9 at.% burnup, using a gas chromatography and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::87f5735c3ed5ce48081bcc1ee1387350
https://doi.org/10.1007/s10967-017-5254-6
https://doi.org/10.1007/s10967-017-5254-6
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 7, Pp 924-933 (2015)
The correlation of the isotopic composition of uranium, plutonium, neodymium, and cesium with the burnup for high burnup pressurized water reactor fuels irradiated in nuclear power reactors has been experimentally investigated. The total burnup was d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::51256a1d2faf6668f236c32ed5d2ae69
https://doi.org/10.1016/j.net.2015.08.002
https://doi.org/10.1016/j.net.2015.08.002
Publikováno v:
Bulletin of the Korean Chemical Society. 36:2068-2072
Temperature-dependent variations of the interface between uranium dioxide and zirconium in UO2 -Zr systems were studied using X-ray photoelectron spectroscopy. The surface of the uranium dioxide sample was oxidized to hyperstoichiometric UO 2+x compo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ff1e57673087ef378bd11a46bed15485
https://doi.org/10.1002/bkcs.10403
https://doi.org/10.1002/bkcs.10403
Publikováno v:
Nuclear Engineering and Technology. 43:309-316
Molybdenum is the most abundant fission product since its fission yield is equivalent to that of xenon, and it has a very special role in the chemistry of nuclear fuel because it influences the oxygen potential of UO₂ fuel. In this study, the distr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c370d58a2ecbf3339f08202b967ad0c4
https://doi.org/10.5516/net.2011.43.3.309
https://doi.org/10.5516/net.2011.43.3.309
Publikováno v:
Analytical Science and Technology. 23:45-53
For the determination of chlorine in uranium compound, analytical methods by using a steam distillation and a pyrohydrolysis have been developed. The steam distillation apparatus was composed of steam generator, distilling flask and condenser etc. Th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27a0c5d4e62edfec922f0b8dc728f12f
https://doi.org/10.5806/ast.2010.23.1.045
https://doi.org/10.5806/ast.2010.23.1.045
Publikováno v:
Journal of Nuclear Science and Technology. 44:1015-1023
Destructive methods were used for the burnup determination of a PWR nuclear fuel irradiated to a high burnup in power reactors, and of a dry processed fuel fabricated from a spent PWR fuel and irradiated in the Hanaro research reactor. The total burn
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::316769e6e21672929da3829ed859d16e
https://doi.org/10.1080/18811248.2007.9711341
https://doi.org/10.1080/18811248.2007.9711341
Publikováno v:
Water and Environment Journal. 19:91-99
In this paper, the tritium levels in the leachates and methane gas condensates which have occurred at 13 sanitary landfills of municipal solid wastes (MSW) are investigated and reported. During the 6 months investigation period, the mean tritium conc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8f1565d0e3cddc1198b36954287d64c0
https://doi.org/10.1111/j.1747-6593.2005.tb00556.x
https://doi.org/10.1111/j.1747-6593.2005.tb00556.x
Publikováno v:
Journal of Nuclear Materials. 321:210-220
The growth behavior of reaction layers and heat generation during the reaction between U–Mo powders and the Al matrix in U–Mo/Al dispersion fuels were investigated. Annealing of 10 vol.% U–10Mo/Al dispersion fuels at temperatures from 500 to 55
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a04484a9f81fcade7b5f4faaa68cad61
https://doi.org/10.1016/s0022-3115(03)00251-4
https://doi.org/10.1016/s0022-3115(03)00251-4