Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021)

被引：0
|
作者：
Deng, Ping [1 ]
Peng, Qunjia [1 ]
Han, En-Hou [1 ]
机构：
[1] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
来源：
SCIENTIFIC REPORTS | 2021年 / 11卷 / 01期
基金：
对外科技合作项目（国际科技项目）;
关键词：
D O I：
10.1038/s41598-021-88868-3
中图分类号：
O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];
学科分类号：
07 ; 0710 ; 09 ;
摘要：
An amendment to this paper has been published and can be accessed via a link at the top of the paper.
引用
收藏
页数：1
相关论文
共 24 条
  • [1] Author Correction: Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
    Ping Deng
    Qunjia Peng
    En-Hou Han
    [J]. Scientific Reports, 11
  • [2] A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water
    Kuang, Wenjun
    Feng, Xingyu
    Du, Donghai
    Song, Miao
    Wang, Mi
    Was, Gary S.
    [J]. CORROSION SCIENCE, 2022, 199
  • [3] Corrosion of phase and phase boundary in proton-irradiated 308L stainless steel weld metal in simulated PWR primary water
    Lin, Xiaodong
    Peng, Qunjia
    Mei, Jinna
    Han, En-Hou
    Ke, Wei
    Qiao, Lijie
    Jiao, Zhijie
    [J]. CORROSION SCIENCE, 2020, 165
  • [4] Grain Boundary Oxidation of Neutron Irradiated Stainless Steels in Simulated PWR Water
    Fukumura, Takuya
    Fukuya, Koji
    Fujii, Katsuhiko
    Miura, Terumitsu
    Kitsunai, Yuji
    [J]. PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018, : 937 - 947
  • [5] Improving the oxidation resistance of 316L stainless steel in simulated pressurized water reactor primary water by electropolishing treatment
    Han, Guangdong
    Lu, Zhanpeng
    Ru, Xiangkun
    Chen, Junjie
    Xiao, Qian
    Tian, Yongwu
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 467 : 194 - 204
  • [6] The intergranular oxidation behavior of low-angle grain boundary of alloy 600 in simulated pressurized water reactor primary water
    Feng, Xingyu
    Xie, Jiayu
    Huang, Mingzheng
    Kuang, Wenjun
    [J]. ACTA MATERIALIA, 2022, 224
  • [7] Fatigue Life of the Strain Hardened Austenitic Stainless Steel in Simulated Pressurized Water Reactor Primary Water
    Huin, Nicolas
    Tsutsumi, Kazuya
    Couvant, Thierry
    Henaff, Gilbert
    Mendez, Jose
    [J]. JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2014, 136 (03):
  • [8] Examinations of Oxidation and Sulfidation of Grain Boundaries in Alloy 600 Exposed to Simulated Pressurized Water Reactor Primary Water
    Schreiber, D. K.
    Olszta, M. J.
    Saxey, D. W.
    Kruska, K.
    Moore, K. L.
    Lozano-Perez, S.
    Bruemmer, S. M.
    [J]. MICROSCOPY AND MICROANALYSIS, 2013, 19 (03) : 676 - 687
  • [9] Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water
    Lin, Xiaodong
    Peng, Qunjia
    Han, En-Hou
    Ke, Wei
    [J]. JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2022, 120 : 36 - 52
  • [10] Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water
    Xiaodong Lin
    Qunjia Peng
    En-Hou Han
    Wei Ke
    [J]. Journal of Materials Science & Technology, 2022, (25) : 36 - 52
123