原子炉用ジルコニウム合金の溶解加工法とその諸性質

DOI

書誌事項

タイトル別名
  • On the Processing Method and Properties of Zircaloy-2 and -3

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説明

Zircaloy-2 and -3 are now most widely used for canning material of fuel elements as well as for structural material for various types of reactors. Therefore, study has been made to the establish the melting and fabrication technique of these alloys in this country and their properties has also been exammined. Using a newly designed and constructed vacuum arc melting furnace for the melting of zirconium alloys, ingots of Zircaloy-2 and -3 have been successfully produced by consumable electrode double arc melting method and sheets, bars, pipes and wires have been fabricated through hot and cold working such as forging, rolling, extrusion and drawing.<br> On the other hand, method of spectrochemical analysis of alloying elements and hafnium in those alloys has also been developed. Beside this, various properties of the zirconium products; such as tensile properties, creep rupture properties, corrosion properties and so on have been studied. It is proved from these tests that the properties of thus made zirconium alloys is quite satisfactorily compared with that of foreign made alloys, which has given fundamental informations to produce zirconium alloys for reactor applications in an industrial scale in this country.

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詳細情報 詳細情報について

  • CRID
    1390282681526734464
  • NII論文ID
    130003746230
  • DOI
    10.3327/jaesj.1.240
  • 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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