Role of research reactor for development of next generation nuclear reactor; Role of HTTR

Inagaki, Yoshiyuki

In this presentation, the outline of High Temperature engineering Test Reactor (HTTR) as role of a research reactor for development of a next generation nuclear reactor is described. The presentation includes features of High Temperature Gas-cooled Reactor (HTGR) such as inherent safety, research results with HTTR such as 50-days operation with a reactor outlet temperature of 950C and safety demonstration tests on loss of forced cooling, and a demonstration test plan with HTTR and heat utilization facilities such as a hydrogen production facility.