Study of tritium production with high temperature gas cooled reactor, 1; Study of operation scenario

Nakaya, Hiroyuki*; Matsuura, Hideaki*; Nakao, Yasuyuki*; Nishikawa, Masabumi*; Goto, Minoru  ; Shimakawa, Satoshi; Nakagawa, Shigeaki  

111The performance of the tritium production by High Temperature Gas-cooled Reactor (HTGR) was evaluated in case of using GTHTR300 as a HTGR. In the evaluation, parametric study was performed for the fuel exchange period and the operation period for one batch. The amount of tritium production was calculated by whole core burnup calculation using the continuous-energy Monte Carlo transport code MVP-BURN. As a result, 23 kg of tritium, which is required for a fusion reactor as fuel, is produced for 1.7 year with the condition in which the fuel exchange period and the operation period are set to 30 days and 240 days, respectively.