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Experimental and Analytical Investigation of the Shallow-Flaw Effect in Reactor Pressure Vessels.

机译：反应堆压力容器浅层效应的实验与分析研究。

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The Heavy-Section Steel Technology (HSST) Program is investigating the increase in effective fracture toughness of A 533 B steel associated with shallow flaws and the implications of the shallow-flaw effect on reactor pressure vessel (RPV) life assessment ...

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作者
T. J. Theiss D. K. Shum S. T. Rolfe;
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年度 1992
页码 1-57
总页数 57
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Defects; Fracture properties; J-integral; Nuclear power plants; Pressure vessels; PWR type reactors; Q-stress; Service life; Shallow flaw effect; Steel-ASTM-A533-B; Strains; Stresses; Thermal shock; Toughness;

机译：缺陷;断裂性能; J-积分;核电站;压力容器;压水堆型反应堆; Q-应力;使用寿命;浅瑕疵效应;钢-asTm-a533-B;应变;应力;热冲击;韧性;

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8. Development of a methodology for the assessment of shallow-flaw fracture in nuclear reactor pressure vessels: Generation of biaxial shallow-flaw fracture toughness data [R] . McAfee, W. J. , Bass, B. R. , Bryson, J. W. 1998

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Experimental and Analytical Investigation of the Shallow-Flaw Effect in Reactor Pressure Vessels.

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