Modeling of fatigue crack growth rate for ferritic steels in light water reactor environments

Author:

Eason Ernest D.,E. Nelson Edward,D. Gilman Joe

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference42 articles.

1. Atkinson, J.D., Chen, Z., 1993. The effect of temperature on corrosion fatigue crack propagation in reactor pressure vessel steels. Proc. 6th Symp. on Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors, The Minerals, Metals and Materials Society, Warrendale, PA, pp. 29–33.

2. Atkinson, J., Tice, D., Scott, P.M., 1986. A review of the UK research programme on corrosion fatigue crack propagation in pressure vessel steels exposed to PWR environments. Proc. 2nd IAEA Specialists' Meeting on subcritical Crack Growth, vol. 1, Sendai, Japan, NUREG/CP-0067.

3. Technical basis for revised reference crack growth rate curves for pressure boundary steels in LWR environment;Bamford;J. Press. Vessel Technol., Trans. ASME,1980

4. Bamford, W.H., 1982. Environmental cracking of pressure boundary materials and the importance of metallurgical considerations. In: Aspects of Fracture in Pressure Vessels and Piping. ASME Publication PVP-58, New York.

5. Bamford, W.H., 1988. A summary of environmentally assisted crack-growth studies performed at Westinghouse Electric Corporation; under funding from the Heavy-Section Steel Technology Program, NUREG/CR-5020.

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