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Simanullang, I. L.*; Nakagawa, Naoki*; Ho, H. Q.; Nagasumi, Satoru; Ishitsuka, Etsuo; Iigaki, Kazuhiko; Fujimoto, Nozomu*
Annals of Nuclear Energy, 177, p.109314_1 - 109314_8, 2022/11
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)Ho, H. Q.; Ishii, Toshiaki; Nagasumi, Satoru; Ono, Masato; Shimazaki, Yosuke; Ishitsuka, Etsuo; Goto, Minoru; Simanullang, I. L.*; Fujimoto, Nozomu*; Iigaki, Kazuhiko
Nuclear Engineering and Design, 396, p.111913_1 - 111913_9, 2022/09
Times Cited Count:1 Percentile:31.61(Nuclear Science & Technology)Simanullang, I.; Yamane, Yuichi; Kikuchi, Takeo; Tonoike, Kotaro
Annals of Nuclear Energy, 147, p.107675_1 - 107675_6, 2020/11
Times Cited Count:2 Percentile:24.28(Nuclear Science & Technology)Simanullang, I. L.*; Honda, Yuki; Fukaya, Yuji; Goto, Minoru; Shimazaki, Yosuke; Fujimoto, Nozomu*; Takada, Shoji
JAEA-Technology 2015-032, 26 Pages, 2016/01
Decay heat of the High Temperature Engineering Test Reactor had been evaluated by the Shure Equation and/or ORIGEN code based on the LWR's data. However, to evaluate more accurately, a suitable method must be considered because of the differences neutron spectrums from the LWRs. Therefore, the decay heat and the generated nuclides for the neutron spectrums of the core with different graphite moderator amount were calculated by the ORIGEN2 code. As a result, it is clear that the calculated decay heats are similar value with LWRs for about one year after the reactor shutdown, and that the significant differences are observed on the longer period affected by the generated nuclides such as Y, Cs, Pr, Rh, Am etc. It is also clear that the dose is affected by Pu on the initial stage after the reactor shutdown.
Simanullang, I.; Yamane, Yuichi; Tonoike, Kotaro
no journal, ,
Effect of initially-loaded amount of burnable poison (BP) on consequences of postulated criticality events in a BWR spent fuel pool has been investigated. Calculations of fission numbers showed that fuel model without BP did not cause a conservative result, while such model is generally used in criticality safety design.
Simanullang, I.; Yamane, Yuichi; Kikuchi, Takeo; Tonoike, Kotaro
no journal, ,
Simanullang, I.; Yamane, Yuichi; Kikuchi, Takeo; Tonoike, Kotaro
no journal, ,
Fukuhara, Katsuki*; Fujimoto, Nozomu*; Simanullang, I. L.*; Fukaya, Yuji; Ho, H. Q.; Nagasumi, Satoru; Ishii, Toshiaki; Hamamoto, Shimpei; Ishitsuka, Etsuo
no journal, ,
no abstracts in English
Simanullang, I. L.*; Fukuhara, Katsuki*; Morita, Keisuke; Fukaya, Yuji; Ho, H. Q.; Nagasumi, Satoru; Iigaki, Kazuhiko; Ishitsuka, Etsuo; Fujimoto, Nozomu*
no journal, ,
Ho, H. Q.; Nagasumi, Satoru; Shimazaki, Yosuke; Hamamoto, Shimpei; Iigaki, Kazuhiko; Goto, Minoru; Simanullang, I. L.*; Fujimoto, Nozomu*; Ishitsuka, Etsuo
no journal, ,
Ho, H. Q.; Goto, Minoru; Nagasumi, Satoru; Ishii, Toshiaki; Shimazaki, Yosuke; Simanullang, I. L.*; Fujimoto, Nozomu*; Ishitsuka, Etsuo; Iigaki, Kazuhiko
no journal, ,