Computationally optimize microstructural investigation of austenitic steels for high strength–toughness properties
Author:
Funder
National Natural Science Foundation of China
Publisher
Springer Science and Business Media LLC
Subject
Mechanical Engineering,Mechanics of Materials,General Materials Science
Link
https://link.springer.com/content/pdf/10.1007/s10853-022-07933-y.pdf
Reference54 articles.
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2. Okada O, Nakata K, Kasahara S (1999) Effects of thermal sensitization on radiation-induced segregation in type 304 stainless steel irradiated with He-ions. J Nucl Mater 265:232–239. https://doi.org/10.1016/S0022-3115(98)00733-8
3. Deng P, Peng Q, Han EH (2021) Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor. Sci Rep 11:1–9. https://doi.org/10.1038/s41598-020-80600-x
4. Deng P, Peng Q, Han EH, Ke W (2017) Effect of the amount of cold work on corrosion of type 304 nuclear grade stainless steel in high-temperature water. Corrosion 73:1237–1249. https://doi.org/10.5006/2436
5. Li C, Shu G, Liu Y, Huang Y, Chen J, Duan Y, Liu W (2018) Effects of neutron irradiation on resistivity of reactor pressure vessel steel. J Nucl Mater 499:446–450. https://doi.org/10.1016/j.jnucmat.2017.12.007
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