Failure probability of nuclear piping due to IGSCC

Author:

Nilsson F.,Brickstad B.,Skånberg L.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference11 articles.

1. WASH-1400, Reactor safety study: An assessment of accident risks in US commercial nuclear power plants,1975

2. Statistics of pressure vessel and piping failures;Bush;J. Pressure Vessel Technol. Trans. ASME,1988

3. Probability of failure in BWR reactor coolant piping;Harris,1986

4. Technical report on material selection and processing guidelines for BWR coolant pressure boundary piping;Hazelton,1986

5. Evaluation of Flaws in Austenitic Steel Piping

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1. Fatigue Life Estimation of Welded Joints considering Statistical Characteristics of Multiple Surface Cracks;Transactions of the Korean Society of Mechanical Engineers A;2005-11-01

2. A probabilistic simulation of fluid leakage in multiple cracks situation;Fatigue & Fracture of Engineering Materials & Structures;2002-10-31

3. Multi-crack growth/coalescence simulation and its role in passive component leak-before-break concept;Nuclear Engineering and Design;1999-12

4. The effect of multiple cracks on the leak-before-break case of pipe;International Journal of Pressure Vessels and Piping;1998-03

5. A procedure for estimation of pipe break probabilities due to IGSCC;International Journal of Pressure Vessels and Piping;1997-12

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