Subject
Mechanical Engineering,Mechanics of Materials,General Materials Science
Cited by
5 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
1. Statistical Analysis of Master Curve Sampling, Screening, and Weighting Methodologies;Journal of Testing and Evaluation;2024-01-29
2. Prediction of fracture toughness of SA738Gr.B steel in the ductile-brittle transition using master curve method and bimodal master curve method;International Journal of Pressure Vessels and Piping;2020-05
3. Study on fracture toughness evaluation method of SA738Gr.B steel heat affected zone in ductile-brittle transition region;Journal of Nuclear Science and Technology;2019-04-16
4. Application and validation of the notch master curve in medium and high strength structural steels;Journal of Mechanical Science and Technology;2015-10
5. Evaluating the fracture toughness of reactor pressure vessel (RPV) materials subject to embrittlement**Some portions of this chapter have been gleaned from Chapter 3 of: International Atomic Energy Agency, Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels, IAEA Nuclear Energy Series NP-T-3.11, IAEA, Vienna (2009), a chapter authored by the first author of this chapter (no attribution in the IAEA document)Notice: This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the US Department of Energy. The United States Government retains and the publisher by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.;Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants;2015