Author:
Park Jae Phil,Ham Junhyuk,Kim Ji Hyun,Oh Young-Jin,Bahn Chi Bum
Publisher
Springer Science and Business Media LLC
Subject
Mechanical Engineering,Mechanics of Materials
Reference41 articles.
1. M. Benson, D. Rudland and A. Csontos, Weld Residual Stress Finite Element Analysis Validation: Part 1 - Data Development Effort (NUREG-2162), U.S.NRC, Washington DC (2014).
2. T. Maeguchi et al., PWSCC susceptibility of Alloy 690, 52 and 152, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Springer (2019) 485–500.
3. S. Mohanty et al., Tensile behavior of 82/182 filler, butter and heat-affected-zones in a 508 LAS-316 SS dissimilar weld: tensile test, Material Model and Finite Element Model Validation, in Pressure Vessels and Piping Conference, American Society of Mechanical Engineers (2019) V001T01A024.
4. ASME, Rules for Construction on Nuclear Facility Components: Supports III Division 1-Subsection NF, American Society of Mechanical Engineers (2013).
5. O. K. Chopra and G. L. Stevens, Effect of LWR Water Environments on the Fatigue Life of Reactor Materials (NUREG/CR-6909, Rev 1), United States Nuclear Regulatory Commission, Office of Nuclear Regulatory (2018).
Cited by
2 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献