Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel-Reference-Cited by-同舟云学术

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Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel

Published:2021-08 Issue:8 Volume:53 Page:2600-2609
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Gao Jun,Liu Chang,Tan Jibo,Zhang Ziyu,Wu Xinqiang,Han En-Hou,Shen Rui,Wang Bingxi,Ke Wei

Publisher

Elsevier BV

Reference41 articles.

1. ASME Boiler and Pressure Vessel Code Section III, New York;American Society Mechanical Engineers,2004

2. ASME Boiler and Pressure Vessel Code Section III, New York;American Society Mechanical Engineers,2015

3. Effect of LWR coolant environments on the fatigue life of reactor materials;Chopra;NUREG/CR (United States. Nucl. Regul. Comm.),2007

4. Effect of LWR coolant environments on the fatigue life of reactor materials;Chopra;NUREG/CR-6909 Rev,2018

5. Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions;Seifert;Corrosion Sci.,2012

Cited by 3 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 S N type environmental fatigue data of Ni-base alloy welds using weibull distribution;Nuclear Engineering and Technology;2023-05

2. Research Progress of Steels for Nuclear Reactor Pressure Vessels;Materials;2022-12-08

3. Effect of environmental media on the fatigue property of Chinese A508-3 steel of AP1000;International Journal of Fracture;2021-09-16

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