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American Society of Mechanical Engineers (2007) Rules for Construction of Nuclear Power Plant Components, Section III, ASME Boiler and Pressure Vessel Code.
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2 |
Chopra, O.K., Shack, W.J. (2007) Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, NUREG/CR-6909, Appendix pp. A.1-4.
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3 |
Higuchi, M. (2008) Comparisons of Environmental Fatigue Evaluation Methods in LWR Water, Proceedings of the ASME 2008 Pressure Vessels and Piping Division Conference, PVP2008-61087.
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4 |
Higuchi, M., Hirano, T., Sakaguchi, K. (2004) Evaluation of Fatigue Damage on Operating Plant Components in LWR Water, ASME PVP-Vol. 480, pp.129-138.
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5 |
Johnson, R.E., Anderson, P.L., Han, S.B. (1989) Comparison of Finite Element Methods for Determining Stress Indices in Reactor Vessel Nozzles, 4th KAIF/KNS Annual Conference, International Symposium on Pressure Vessel Technology and Nuclear Codes and Standards.
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6 |
Tom, E., Dong, M., Lee, H. (2009) Study of the Effects of Environment in the Fatigue Analysis on Existing LWR As Proposed in USNRC RG 1.207, Proceedings of the ASME 2009 Pressure Vessels and Piping Division Conference, PVP2009-77915.
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7 |
United States Nuclear Regulatory Commission (U.S. NRC) (2007) Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components due to the Effects of the Light-Water Reactor Environment for New Reactors, Regulatory Guide 1.207.
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8 |
United States Nuclear Regulatory Commission (U.S. NRC) (1997) 10 Code of Federal Regulations (CFR) Part 50, Appendix S, Earthquake Engineering Criteria for Nuclear Power Plants.
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