IRRADIATED

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Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water被引量：1
《Journal of Materials Science & Technology》2022年第25期36-52,共17页Xiaodong Lin Qunjia Peng En-Hou Han Wei Ke 
financially supported by the Jiangsu Natural Science Foundation (No. BK20191178);the National Natural Science Foundation of China (No. 52071018);the China Postdoctoral Science Foundation (No. 2021M692018)。
The proton-irradiated 308L stainless steel weld metal was strained by using constant extension rate tensile testing in simulated PWR primary water, and its deformation microstructures and irradiation assisted stress c...
关键词：Stainless steel weld metal Proton irradiation Deformation microstructures Irradiation assisted stress corrosion cracking Grain and phase boundaries 
Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water被引量：2
《Acta Metallurgica Sinica(English Letters)》2021年第2期174-186,共13页Ping Deng En-Hou Han Qunjia Peng Chen Sun 
financially supported by the International Science&Technology Cooperation Program of China(No.2014DFA50800);partly supported by the Essential Research Fundby SNPTC(No.2015 SN010-007)。
Corrosion behavior and mechanism of irradiated 304 nuclear grade stainless steel were studied in simulated pressurized water reactor primary water.The microstructure of the oxide formed on the steel irradiated to diff...
关键词：Stainless steel IRRADIATION High-temperature corrosion Intergranular corrosion 
Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions
《Acta Metallurgica Sinica(English Letters)》2017年第1期89-96,共8页Zhong-Cheng Zheng Yan-Xia Yu Wei-Ping Zhang Zhen-Yu Shen Feng-Feng LUO Li-Ping Guo Yao-Yao Ren Rui Tang 
financial supports from the International Science and Technology Cooperation Program of China (No. 2015DFR60370);the National Natural Science Foundation of China (Nos. 11275140 and U1532134)
AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2＋ ions at 290 and 380 ℃. Microstructures were characterized...
关键词：Supercritical water-cooled reactor Austenitic stainless steels Ion irradiation Dislocation loops HYDROGEN 
Bubble Production and Evolution in Stainless Steel Irradiated With Protons
《Annual Report of China Institute of Atomic Energy》2004年第1期17-18,共2页ZHENG Yong-nan, ZHOU Dong-mei, DU En-peng, YUAN Da-qing, ZUO Yi, HU Yue-ming, DUAN Xiao, WANG Zhao-hui, ZHU Sheng-yun 
SupportedbytheStateMajorBasicResearchDevelopmentPrograminChina(No.G1999022600)
关键词：ADS 次临界系统 束窗材料 不锈钢 结构材料 
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