高温ガス冷却炉材料としての酸化ベリリウム

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書誌事項

タイトル別名
  • Utilization of BeO in High Temperature Gas Cooled Reactor

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説明

Informations on BeO as nuclear material from all the papers that were published at the international conference on BeO held in Australia last year are described in this paper.<br>BeO possesses outstandingly attractive nuclear and high temperature properties as fuel matrix material. Therefore, BeO is planned to be used in the Australian High Temperature Gas Cooled Reactor Project (HTGCR) and the General Atomic's High Temperature Gas Cooled Reactor system (HTGR) in U.S.A. The use of BeO in reactor has the following excellent merits:<br>(1) High gas outlet temperature is realized.<br>(2) BeO has a low capture cross section and offers the additional advantage of neutron re-production from the (n, 2n) reaction.<br>(3) A dispersion type fuel permits high power density and high fissile material heat rating.<br>(4) BeO shows a satisfying properties in retaining fission product release.

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詳細情報 詳細情報について

  • CRID
    1390282681527649152
  • NII論文ID
    130003747576
  • DOI
    10.3327/jaesj.6.583
  • 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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