Crack growth prediction for irradiated stainless steels under the combined fatigue-creep loading

Author:

Fuller Robert W.,Simsiriwong Jutima,Shamsaei Nima

Publisher

Elsevier BV

Subject

Applied Mathematics,Mechanical Engineering,Condensed Matter Physics,General Materials Science

Reference45 articles.

1. B.K. Grimes, US Nuclear Regulatory Commission Washington DC, Information Notice No. 93-101: Jet Pump Hold-Down Beam Failure, December 1993.

2. Formation and growth of cracking in feed water pipes and RPV nozzles;Kussmaul;Nucl. Eng. Des.,1984

3. A review of fatigue failures in LWR plants in Japan;Lida;Nucl. Eng. Des.,1992

4. Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments NUREG/CR-6787 ANL-01/25;Chopra;Nucl. Regulat. Commission,2001

5. American Society of Mechanical Engineers (ASME). Rules for Construction of Nuclear Power Plant Components. ASME Boiler and Pressure Vessel Code, Section III, Division 1 - Subsection NE, Class MC Components, ASME, New York, New York, 1992.

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