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Journal Articles

Evaluation of power distribution calculation of the very high temperature reactor critical assembly (VHTRC) with Monte Carlo MVP3 code

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)

Journal Articles

Calculation of shutdown gamma distribution in the high temperature engineering test reactor

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)

Journal Articles

Consequence analysis of a postulated nuclear excursion in BWR spent fuel pool using 1/$$f^{beta}$$ spectrum model of randomization

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)

JAEA Reports

Calculation of decay heat by new ORIGEN libraries for high temperature engineering test reactor

Simanullang, I. L.*; Honda, Yuki; Fukaya, Yuji; Goto, Minoru; Shimazaki, Yosuke; Fujimoto, Nozomu*; Takada, Shoji

JAEA-Technology 2015-032, 26 Pages, 2016/01

JAEA-Technology-2015-032.pdf:2.07MB

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 $$^{90}$$Y, $$^{134}$$Cs, $$^{144}$$Pr, $$^{106}$$Rh, $$^{241}$$Am etc. It is also clear that the dose is affected by $$^{241}$$Pu on the initial stage after the reactor shutdown.

Oral presentation

Effect of $$Gd_{2}O_{3}$$ to a fission number in the first pulse of a postulated nuclear excursion

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 $$UO_{2}$$ fuel model without BP did not cause a conservative result, while such model is generally used in criticality safety design.

Oral presentation

Consequence analysis of postulated criticality in SFP using the randomized model of fuel debris

Simanullang, I.; Yamane, Yuichi; Kikuchi, Takeo; Tonoike, Kotaro

no journal, , 

Oral presentation

Consequence analysis of a postulated nuclear excursion in BWR spent fuel pool using 1/$$f^{beta}$$ spectrum model of randomization

Simanullang, I.; Yamane, Yuichi; Kikuchi, Takeo; Tonoike, Kotaro

no journal, , 

Oral presentation

Study of ORIGEN library preparation method for high temperature gas cooled reactors

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

Oral presentation

Preparation method of ORIGEN2 library for high temperature gas-cooled reactors

Simanullang, I. L.*; Fukuhara, Katsuki*; Morita, Keisuke; Fukaya, Yuji; Ho, H. Q.; Nagasumi, Satoru; Iigaki, Kazuhiko; Ishitsuka, Etsuo; Fujimoto, Nozomu*

no journal, , 

Oral presentation

Prediction of the operating control rod position of the HTTR with supervised machine learning

Ho, H. Q.; Nagasumi, Satoru; Shimazaki, Yosuke; Hamamoto, Shimpei; Iigaki, Kazuhiko; Goto, Minoru; Simanullang, I. L.*; Fujimoto, Nozomu*; Ishitsuka, Etsuo

no journal, , 

Oral presentation

High-temperature operation mode of HTTR for hydrogen production facility

Ho, H. Q.; Goto, Minoru; Nagasumi, Satoru; Ishii, Toshiaki; Shimazaki, Yosuke; Simanullang, I. L.*; Fujimoto, Nozomu*; Ishitsuka, Etsuo; Iigaki, Kazuhiko

no journal, , 

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