〔56〕高速炉の吸収・制御材:ディミトロフグラード会議をめぐって Absorber Materials for Fast Reactor:Review of IWGFR Specialists' Meeting

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A review is presented of the IAEA-IWGFR Specialists' Meeting on the "Development and Application of Absorber Materials for Fast Reactors" which was held at Dimitrovgrad, USSR, June 4-8, 1973. At the meeting, attention was given mainly to the choice of absorbing materials for the control elements of fast reactors, to the design of absorbing rods and tests of their performance.<BR>About two thirds of the sessions were devoted to the oldest established and the most promising absorber-B<SUB>4</SUB>C. The pre-irradiation properties of B<SUB>4</SUB>C are considered to be fairly thoroughly known already. Good agreement has been seen on the results of compatibility studies. On the other hand, the irradiation behavior of B<SUB>4</SUB>C-specially swelling and He release-stimulated brisk discussion among the participants in respect of the appreciable discrepancy discerned in the results obtained so far and the possible explanations given therefore. Development of the vented control rod is being actively undertaken in most of the countries.<BR>Tantalum and Eu<SUB>2</SUB>O<SUB>3</SUB> attracted attention as promissing alternatives to B<SUB>4</SUB>C. There arises problems, however, on the compatibility of these two materials in the presence of Na. Another difficulty foreseen in the use of Ta rods is cooling during reactor shut-off. For Eu<SUB>2</SUB>O<SUB>3</SUB>, phase stability should be an important problem for future study.

収録刊行物

  • 日本原子力学会誌

    日本原子力学会誌 16(3), 128-136, 1974

    一般社団法人 日本原子力学会

各種コード

  • NII論文ID(NAID)
    130003908988
  • NII書誌ID(NCID)
    AN00188477
  • 本文言語コード
    JPN
  • ISSN
    0004-7120
  • NDL 記事登録ID
    7612141
  • NDL 雑誌分類
    ZN36(科学技術--原子力工学・工業)
  • NDL 請求記号
    Z16-434
  • データ提供元
    NDL  J-STAGE 
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