核融合炉増殖ブランケット炉内照射試験の現状

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タイトル別名
  • カク ユウゴウロ ゾウショク ブランケットロ ナイ ショウシャ シケン ノ ゲンジョウ
  • Status of In-situ Irradiation Tests on Tritium Breeding Blanket for Fusion Reactor

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To develop a tritium breeding blanket for a fusion reactor, irradiation tests in fission reactors must be conducted to obtain data on tritium production / release / recovery performance of the blanket. In-situ various irradiation tests have been carried out in Japan (JMTR) and Europe (HFR) to investigate tritium release characteristics from ultra-small Li2TiO3 pebble (1 mm dia) bed. Tritium performance irradiation tests presently focus on Li2TiO3 ceramic considered promising as a new strong candidate for breeding material. This report shown the present status if in-situ irradiation tests carried out throughout the world. An in-situ irradiation test program on tritium release for partial breeding blanket module is presented.

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