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Matsuura, Hideaki*; Kochi, Shohei*; Nakaya, Hiroyuki*; Yasumoto, Takashi*; Nakao, Yasuyuki*; Shimakawa, Satoshi; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
Nuclear Engineering and Design, 243, p.95 - 101, 2012/02
The performance of a high-temperature gas-cooled reactor as a tritium production device was examined. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) was assumed as the calculation target of a typical gas-cooled reactor, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the 3-dimensional entire-core region of GTHTR300 were carried out considering its unique double heterogeneity structure. It was shown that gas-cooled reactors with thermal output power of 3 GW in all can produce 6-10 kg of tritium in a year.
Goto, Minoru; Shimakawa, Satoshi; Yasumoto, Takashi*
JAEA-Conf 2011-002, p.11 - 16, 2011/09
In the past, benchmark calculations of the HTTR criticality approach, which is a Japanese HTGR, have been performed by several countries, and almost of the calculations have overestimated its excess reactivity. In Japan, the benchmark calculations were performed by JAEA, and the calculations also resulted in overestimation. JAEA improved this overestimation by revising the problem geometry and replacing nuclear data library with JENDL-3.3, which was the latest JENDL at that time. However, the overestimation remained and this problem had not been resolved until today. We performed the calculation of the HTTR criticality approach with several nuclear data libraries, and found the slightly difference of the capture cross section of carbon at thermal energy among the libraries causes the difference of the 
values to be not negligible. This cross section value had not been concerned in reactor neutronics calculation because of its small value on the order of 10
burn, and consequently the cross section value had not been revised for a long time even in the major nuclear data libraries: JENDL, ENDF/B and JEFF. We have thought the cross section value should be revised based on the latest measurement data to improve the accuracy of the neutronics calculations for HTTR. On May in 2010, the latest JENDL (JENDL-4) was released by JAEA, and the capture cross section of carbon was revised. Consequently, JENDL-4 yielded 0.4-0.9%
k smaller values than JENDL-3.3 in the calculation for the HTTR critical approach, and then the problem of the overestimation of the excess reactivity in the HTTR benchmark calculation was resolved.
Kochi, Shohei*; Nakaya, Hiroyuki*; Shimakawa, Satoshi; Matsuura, Hideaki*; Yasumoto, Takashi*; Nakao, Yasuyuki*; Goto, Minoru; Nakagawa, Shigeaki
no journal, ,
no abstracts in English
Yasumoto, Takashi*; Matsuura, Hideaki*; Shimakawa, Satoshi; Nakao, Yasuyuki*; Kochi, Shohei*; Nakaya, Hiroyuki*; Goto, Minoru; Nakagawa, Shigeaki
no journal, ,
no abstracts in English
Yasumoto, Takashi*; Goto, Minoru; Shimakawa, Satoshi; Nakagawa, Shigeaki; Seki, Yasuyoshi; Matsuura, Hideaki*; Nakao, Yasuyuki*
no journal, ,
Core calculation of the HTTR yielded overestimation of the excess reactivities to the experimental data, and this problem has not been resolved yet. It is one of the important issue to select nuclear data library, which was used for the core calculations, to obtain the calculation results with high accuracy. In the past, the effect of difference of nuclear data libraries on the HTTR core calculation results was evaluated using JENDL-3.3, ENDF/B-6.8 and JEFF-3.1. As a result, JENDL-3.3 yielded better excess reactivities than ENDF/B-6.8 and JEFF-3.1. In this study, the effect was reevaluated using the latest version of ENDF/B: ENDF/B-7.0 and the preliminary version of JENDL-4.
Matsuura, Hideaki*; Yasumoto, Takashi*; Shimakawa, Satoshi; Kochi, Shohei*; Nakaya, Hiroyuki*; Nakao, Yasuyuki*; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
no journal, ,
no abstracts in English
Matsuura, Hideaki*; Kochi, Shohei*; Nakaya, Hiroyuki*; Yasumoto, Takashi*; Nakao, Yasuyuki*; Shimakawa, Satoshi; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
no journal, ,
The performance of a high-temperature gas-cooled reactor as a tritium production device for fusion reactors was examined by performing a core burn-up calculation with the continuous-energy Monte Carlo code MVP-BURN. It was shown that the high-temperature gas cooled reactor can contribute to the tritium production for fusion reactors.
Yasumoto, Takashi*; Matsuura, Hideaki*; Shimakawa, Satoshi; Nakao, Yasuyuki*; Kochi, Shohei*; Nakaya, Hiroyuki*; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
no journal, ,
no abstracts in English
