Engineering study of tritium production with high temperature gas-cooled reactor

Goto, Minoru  ; Nakagawa, Shigeaki  ; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Katayama, Kazunari*

A high temperature gas-cooled reactor (HTGR) is proposed as a tritium production device, which can produce a large amount of tritium by loading coated Li pebbles into the core without a major change of the original reactor core design. The engineering study was performed to clarify the problem of the tritium production system and assess the possibility of the resolution. As a result, it was assessed that all of the problems could be resolved from an engineering view point by using the HTTR (High Temperature engineering Test Reactor) experiences on the production of the coated fuel particles and deal of the fuels.