TY - JOUR
T1 - Performance of high-temperature gas-cooled reactor as a tritium production device for fusion reactors
AU - Matsuura, H.
AU - Kouchi, S.
AU - Nakaya, H.
AU - Yasumoto, T.
AU - Nakao, Y.
AU - Shimakawa, S.
AU - Goto, M.
AU - Nakagawa, S.
AU - Nishikawa, M.
N1 - Funding Information:
The authors acknowledge many researchers in the Japanese fusion community for fruitful discussions concerning the tritium supply problem in future fusion devices. This research was partially supported by the Ministry of Education, Science, Sports and Culture , Grant-in-Aid for challenging Exploratory Research, 23656574 .
PY - 2012/2
Y1 - 2012/2
N2 - The performance of a high-temperature gas-cooled reactor as a tritium production device is examined. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) is 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 is shown that gas-cooled reactors with thermal output power of 3 GW in all can produce 5-8 kg of tritium in a year.
AB - The performance of a high-temperature gas-cooled reactor as a tritium production device is examined. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) is 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 is shown that gas-cooled reactors with thermal output power of 3 GW in all can produce 5-8 kg of tritium in a year.
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U2 - 10.1016/j.nucengdes.2011.12.008
DO - 10.1016/j.nucengdes.2011.12.008
M3 - Article
AN - SCOPUS:84855830903
SN - 0029-5493
VL - 243
SP - 95
EP - 101
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
ER -