年次大会講演論文集
Online ISSN : 2433-1325
会議情報
2320 高温工学試験研究炉 (HTTR) の出力上昇試験計画
馬場 治国富 一彦伊与久 達夫茂木 春義
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会議録・要旨集 フリー

p. 399-400

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抄録
The HTTR (High Temperature Engineering Test Reactor) is a graphite-moderated and helium-cooled reactor with 30 MW in thermal output and outlet gas temperature of 850℃ for rated power operation and 950℃ for high temperature operation. It was successfully constructed, and its power up operation has been carried out since September 1999 according to a rise to power test program. At present (May 2000), the 9 MW operation was almost finished without any major problem. The rise to power test program was designed to confirm basic performance of the HTTR such as core physics, radiation shield performance, thermal performance, fuel integrity and so on. Also, it includes commissioning tests by the Science and Technology Agency (STA). This paper describes contents of the rise to power test program and preliminary results of the 9MW operation.
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© 2000 一般社団法人日本機械学会
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