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Corrosion resistance of 316 stainless steel in a simulated pressurized water reactor improved by laser cladding with chromium
期刊论文
Surface and Coatings Technology, 2022, 卷号: 441
作者:
Gu, Yufen
;
Xu, Youwei
;
Shi, Yu
;
Feng, Changgen
;
Volodymyr, Korzhyk
收藏
  |  
浏览/下载:42/0
  |  
提交时间:2022/06/20
Austenitic stainless steel
Chromium compounds
Corrosion resistance
Corrosion resistant coatings
Laser cladding
Light water reactors
Morphology
Nuclear fuels
Oxide films
Pressurized water reactors
Steel corrosion
316 austenitic stainless steel
316 stainless steel
Cr coatings
Electrochemical behaviors
Element distribution
Oxidation behaviours
Powder bed
Powder bed fusion
Pressurised water reactor
Stress-corrosion
Optimal Tracking Control for a Discrete Time Nonlinear Nuclear Power System
期刊论文
MATHEMATICAL PROBLEMS IN ENGINEERING, 2022, 卷号: 2022, 页码: 9
作者:
Luan, Zhenhua
;
Wang, Mengxuan
;
Zhang, Yuzhen
;
Wei, Qinglai
;
Zhou, Tianmin
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  |  
浏览/下载:7/0
  |  
提交时间:2023/02/22
Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management
期刊论文
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2022, 卷号: 2022
作者:
Guo, Dingqing
;
Wang, Jinkai
;
Chen, Chao
;
Xia, Dongqin
;
Yong, Nuo
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  |  
浏览/下载:7/0
  |  
提交时间:2022/12/23
A New Neuro-Optimal Nonlinear Tracking Control Method via Integral Reinforcement Learning with Applications to Nuclear Systems
期刊论文
NEUROCOMPUTING, 2022, 卷号: 483, 页码: 361-369
作者:
Zhong, Weifeng
;
Wang, Mengxuan
;
Wei, Qinglai
;
Lu, Jingwei
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  |  
浏览/下载:14/0
  |  
提交时间:2022/06/10
Integral reinforcement learning
Nuclear power reactor
Nonlinear system
Optimal tracking control
Neural networks
Effect of the frequency on fretting corrosion behavior between Alloy 690TT tube and 405 stainless steel plate in high temperature pressurized water
期刊论文
TRIBOLOGY INTERNATIONAL, 2021, 卷号: 164, 页码: 16
作者:
Zhang, Yusheng
;
Ming, Hongliang
;
Tang, Lichen
;
Wang, Jianqiu
;
Qian, Hao
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  |  
浏览/下载:16/0
  |  
提交时间:2021/11/22
Fretting corrosion
Fretting frequency
Alloy 690TT
High temperature pressurized water
Environmentally assisted cracking in the fusion boundary region of a SA508-Alloy 52M dissimilar weld joint in simulated primary pressurized water reactor environments
期刊论文
CORROSION SCIENCE, 2021, 卷号: 190, 页码: 13
作者:
Dong, Lijin
;
Zhang, Yan
;
Han, Yaolei
;
Peng, Qunjia
;
Han, En-Hou
收藏
  |  
浏览/下载:21/0
  |  
提交时间:2021/10/15
A
Nickel
A
Low alloy steel
B
TEM
C
Stress corrosion
C
Corrosion fatigue
C
Welding
Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021)
期刊论文
SCIENTIFIC REPORTS, 2021, 卷号: 11, 期号: 1, 页码: 1
作者:
Deng, Ping
;
Peng, Qunjia
;
Han, En-Hou
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  |  
浏览/下载:2/0
  |  
提交时间:2021/10/15
Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
期刊论文
SCIENTIFIC REPORTS, 2021, 卷号: 11, 期号: 1, 页码: 9
作者:
Deng, Ping
;
Peng, Qunjia
;
Han, En-Hou
收藏
  |  
浏览/下载:20/0
  |  
提交时间:2021/10/15
Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10
作者:
Tan, Jibo
;
Zhang, Ziyu
;
Zheng, Hui
;
Wang, Xiang
;
Gao, Jun
收藏
  |  
浏览/下载:17/0
  |  
提交时间:2021/02/02
Corrosion fatigue
Austenitic stainless steel
High temperature corrosion
Model
Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10
作者:
Tan, Jibo
;
Zhang, Ziyu
;
Zheng, Hui
;
Wang, Xiang
;
Gao, Jun
收藏
  |  
浏览/下载:15/0
  |  
提交时间:2021/02/02
Corrosion fatigue
Austenitic stainless steel
High temperature corrosion
Model
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