Irradiation -assisted stress corrosion cracking of Type 347 and Type 316 steels irradiated in commercial pressurized water reactors *

Ickes Michael R.; McKinley Joshua; Lee Jung-Kun; Smith Jean M.; Ruminski Andrew M.; Burke Michael A.

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Irradiation -assisted stress corrosion cracking of Type 347 and Type 316 steels irradiated in commercial pressurized water reactors *

机译：347型和型316型施用商业加压水反应器中的辐照腐蚀腐蚀开裂*

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《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion》 |2020年第1期|共19页
作者
Ickes Michael R.; McKinley Joshua; Lee Jung-Kun; Smith Jean M.; Ruminski Andrew M.; Burke Michael A.;
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作者单位

Westinghouse Elect Co Pittsburgh PA 15222 USA;

Westinghouse Elect Co Pittsburgh PA 15222 USA;

Univ Pittsburgh Pittsburgh PA 15260 USA;

Elect Power Res Inst Palo Alto CA USA;

NobelClad Broomfield CO USA;

Elect Power Res Inst Palo Alto CA USA;

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正文语种 eng
中图分类原子能技术;
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1. Irradiation -assisted stress corrosion cracking of Type 347 and Type 316 steels irradiated in commercial pressurized water reactors * [J] . Ickes Michael R., McKinley Joshua, Lee Jung-Kun, Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2020,第1期

机译：347型和型316型施用商业加压水反应器中的辐照腐蚀腐蚀开裂*
2. Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility [J] . McMurtrey M., Sun C., Rupp R. E., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2021,第1期

机译：辐照效应的调查导致辐照辅助应力腐蚀裂解敏感性降低
3. Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals [J] . Wang Mi, Song Miao, Lear Calvin R., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2019,第期

机译：辐照辅助应力腐蚀腐蚀开裂，用于轻型水反应器核心内部的商用和先进合金
4. APPLICABILITY OF FORMULA OF THE IRRADIATION ASSISTED STRESS CORROSION CRACKING RATES FOR NEUTRON-IRRADIATED TYPE 316L STAINLESS STEELS TO VARIOUS TYPES OF STAINLESS STEELS UNDER BOILING WATER REACTOR CONDITION [C] . Masato Koshiishi, Shigeaki Tanaka, Hitoshi Seto, ASME Pressure Vessels and Piping Conference . 2020

机译：在沸水反应器条件下，对中子辐照型316L不锈钢的辐射辅助应力腐蚀裂解速率的公式适用于中子辐照型316L不锈钢速度
5. Isolation of the role of radiation-induced segregation in irradiation-assisted stress corrosion cracking of proton-irradiated austenitic stainless steels. [D] . Busby, Jeremy Todd. 2001

机译：隔离辐射诱发的偏析在质子辐照奥氏体不锈钢的辐照辅助应力腐蚀开裂中的作用。
6. Corrosion and microstructural analysis data for AISI 316L and AISI 347H stainless steels after exposure to a supercritical water environment [O] . A. Ruiz, T. Timke, A. van de Sande, 2016

机译：AISI 316L和AISI 347H不锈钢在超临界水环境中暴露后的腐蚀和微观结构分析数据
7. Corrigendum to “A mechanistic study of the temperature dependence of the stress corrosion crack growth rate in SUS316 stainless steels exposed to pressurized water reactor primary water” Acta Mater. 114 (2016) 15–24 [O] . Martina Meisnar, Arantxa Vilalta-Clemente, Michael Moody, 2016

机译：勘探为“应力腐蚀裂纹裂纹率温度依赖性的机械研究，暴露于加压水反应器初级水”Acta Mater。 114（2016）15-24
8. Chloride-Assisted Stress-Corrosion Cracking in Type 316 Stainless Steel Water and Gas-Sampling Tubes from the HYGAS Pilot Plant: Failure Analysis Report [R] . Danyluk, S., Dragel, G. M. 1977

机译：HYGas试验工厂316型不锈钢水和气体采样管中氯离子辅助应力腐蚀开裂：失效分析报告

Irradiation -assisted stress corrosion cracking of Type 347 and Type 316 steels irradiated in commercial pressurized water reactors *

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