Reactor surveillance test and fracture mechanics evaluation of irradiation embrittlement in reactor pressure vessel steels

Hideaki Takahashi, Kiyoshi Saito, Tetsuo Shoji, Kazuhiro Date, Masahiko Suzuki

研究成果: Article査読

3 被引用数 (Scopus)

抄録

With special reference to a nuclear reactor surveillance test, a new evaluation procedure for the fracture toughness from Charpy Vee-notch data is developed. This procedure utilizes a recrystallization-etch technique to determine the crack tip energy dissipation (Wp) within an intense strain region or the dissipation rate (dWp/da). These two parameters serve to characterize the crack tip resistance to cleavage-controlled fracture initiation. The effects of specimen geometry, strain rate, temperature and notch acuity on the cleavage-controlled fracture toughness transition are explained using a critical value of Wp or dWp/da and a modified rate parameter. A feasibility of the new surveillance test procedure for evaluating the irradiation embrittlement of reactor pressure vessel steel, such as SA533B-1, is here verified experimentally, utilizing the Charpy or small compact tension specimen irradiated in a test reactor.

本文言語English
ページ(範囲)317-326
ページ数10
ジャーナルJournal of Engineering Materials and Technology, Transactions of the ASME
102
4
DOI
出版ステータスPublished - 1980 10
外部発表はい

ASJC Scopus subject areas

  • 材料科学(全般)
  • 凝縮系物理学
  • 材料力学
  • 機械工学

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