Evaluation of radiation damage in reactor pressure vessel steel by elastic-plastic fracture mechanics

M. A. Khan, T. Shoji, H. Takahashi, M. Suzuki

研究成果: Article査読

3 被引用数 (Scopus)

抄録

Elastic-plastic toughness characterization of SA533B nuclear pressure vessel steel is described in terms of the J integral approach. A simple test procedure has been proposed from which the JIC value at crack extension can be estimated for both unirradiated and irradiated steels using a single compact tension specimen. The values of JIC determined by the proposed method are compared with those determined by the single specimen compliance method. The JIC fracture toughness of the pressure vessel steel irradiated at 200°C to a neutron flux density ranging from 6.2 × 1017 to 2.34 × 1019 n/cm2 (E>1 MeV) has been explored for different test temperatures. It is shown that irradiation significantly reduces the JIC fracture toughness of this material. These results are compared with the data available in the literature.

本文言語English
ページ(範囲)276-281
ページ数6
ジャーナルJournal of Engineering Materials and Technology, Transactions of the ASME
103
4
DOI
出版ステータスPublished - 1981 10

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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