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Development of a methodology for the assessment of shallow-flaw fracture in nuclear reactor pressure vessels: Generation of biaxial shallow-flaw fracture toughness data

机译：开发一种评估核反应堆压力容器浅裂缝的方法：生成双轴浅裂缝断裂韧性数据

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McAfee, W.J.; Bass, B.R.; Bryson, J.W.;
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1. Weibull statistical models of K_(Ic)/K_(Ia) fracture toughness databases for pressure vessel steels with an application to pressurized thermal shock assessments of nuclear reactor pressure vessels [J] . P.T. Williams, K.O. Bowman, B.R. Bass International Journal of Pressure Vessels and Piping . 2001,第2a3期

机译：压力容器用钢的K_（Ic）/ K_（Ia）断裂韧性数据库的威布尔统计模型及其在核反应堆压力容器的加压热冲击评估中的应用
2. Weibull statistical models of K{sub}(Ic)/K{sub}(Ia) fracture toughness databases for pressure vessel steels with an applicaiton to pressurized thermal shock assessments of nuclear reactor pressure vessels [J] . P. T. Williams, K. O. Bowman, B. R. Bass, International Journal of Pressure Vessels and Piping . 2001,第2a3期

机译：压力容器钢K {sub}（Ic）/ K {sub}（Ia）断裂韧性数据库的威布尔统计模型，用于核反应堆压力容器的加压热冲击评估
3. Analysis of the Effect of Biaxial Loading on the Fracture Toughness of Reactor Pressure-Vessel Steels [J] . B.Z.Margolin, V.I.Kostylev Strength of Materials . 2000,第5期

机译：双轴载荷对反应堆压力容器钢断裂韧性的影响分析
4. Development of a methodology for the assessment of shallow-flaw fracture in nuclear reactor pressure vessels [C] . W. J. McAfee, B. R. Bass, J. W. Bryson ASME Pressure Vessels and Piping Conference . 1997

机译：核反应堆压力容器中浅缺陷骨折评估方法的发展
5. The development of a curved centre cracked specimen for fracture toughness testing of CANDU reactor pressure tubes. [D] . Wallace, A.C. 1988

机译：弯曲中心裂纹试样的开发，用于测试CANDU反应堆压力管的断裂韧性。
6. Effect of the Shape of Styrene–Acrylonitrile Water-Filter Housings on the Destructive Pressure Crack-Initiation Propagation Conditions and Fracture Toughness of Styrene–Acrylonitrile [O] . Borut Zorc, Matija Zorc, Borut Kosec, 2020

机译：苯乙烯-丙烯腈滤水器壳体的形状对苯乙烯-丙烯腈的破坏压力裂纹萌生扩展条件和断裂韧性的影响
7. Biaxial loading effects on fracture toughness of reactor pressure vessel steel [O] . McAfee, W.J., Bass, B.R., Bryson, J.W. Jr., 1995

机译：双轴加载对反应堆压力容器钢断裂韧性的影响
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

机译：开发一种评估核反应堆压力容器浅裂缝的方法：生成双轴浅裂缝断裂韧性数据

Development of a methodology for the assessment of shallow-flaw fracture in nuclear reactor pressure vessels: Generation of biaxial shallow-flaw fracture toughness data

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