ＨＴＴＲ（高温工学試験研究炉）系統別・総合機能試験

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書誌事項

タイトル別名
  • Performance Test of the HTTR (High Temperature Engineering Test Reactor).

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説明

The High Temperature Engineering Test Reactor (HTTR), which is the first High Temperature Gas-cooled Reactor (HTGR) in Japan, is a graphite-moderated and helium-cooled reactor with a thermal output of 30MW and a maximum outlet gas temperature of 950℃ and has the capability to demonstrate nudear process heat utilization using an intermadiate heat exchanger.<BR>The construction of the HTTR was decided by Japanese Atomic Energy Commission (JAEC) in 1987 and started in March 1991 by the Japan Atomic Energy Research Institute (JAERI) to establish and upgrade the technology basis for an HTGR also to serve as a potential tool for new and innovative basic research on high temperature technologies.<BR>The construction of the HTTR almost ended in 1996, and the pre-operation and the commissioning tests had been carried out from 1996 till 1998 before fuel was loaded in the core.<BR>Divided into four steps depending on the hazards and interfaces involved, the pre-operation and the commissioning tests were performed. It was confirmed from test results that HTTR plant system was capable of fuel loading.

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詳細情報 詳細情報について

  • CRID
    1390282681526702720
  • NII論文ID
    130003910273
  • DOI
    10.3327/jaesj.41.686
  • ISSN
    21865256
    00047120
  • 本文言語コード
    ja
  • データソース種別
    • JaLC
    • Crossref
    • CiNii Articles
  • 抄録ライセンスフラグ
    使用不可

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