次世代炉開発における研究炉の役割; HTTRの役割

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

稲垣 嘉之

Inagaki, Yoshiyuki

次世代炉開発における研究炉の役割として、高温工学試験研究炉(HTTR)の概要を紹介する。高温ガス炉が持つ固有の安全性などの特長のほか、HTTRによる950Cの50日間運転、炉心強制冷却停止による安全性実証試験などの試験研究の成果、HTTRへ水素製造施設などの熱利用施設を接続した試験計画などについて述べる。

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.