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上海大学 [34]
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期刊论文 [17]
会议论文 [16]
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The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 517, 页码: 179-191
作者:
Chen, Junjie[1]
;
Lu, Zhanpeng[2]
;
Meng, Fanjiang[3]
;
Xu, Xuelian[4]
;
Xiao, Qian[5]
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/04/22
Alloy 690
Pressurized water reactor
Secondary water
Hydrogen permeation
Oxide film
Characterization of microstructure of A508III/309L/308L weld and oxide films formed in deaerated high-temperature water
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 498, 页码: 227-240
作者:
Xiong, Qi[1]
;
Li, Hongjuan[2]
;
Lu, Zhanpeng[3]
;
Chen, Junjie[4]
;
Xiao, Qian[5]
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2019/04/24
Microstructure
Ferrite
Low alloy steel
Stainless steel
Oxide film
High temperature water
Distribution and Characteristics of Oxide Films Formed on Stainless Steel Cladding on Low Alloy Steel in Simulated PWR Primary Water Environments
会议论文
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018-01-01
作者:
Xiong, Qi[1]
;
Li, Hongjuan[2]
;
Lu, Zhanpeng[3]
;
Chen, Junjie[4]
;
Xiao, Qian[5]
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2019/04/22
Stainless steel cladding
Pressurized water reactor
Low alloy steel
Oxide film
High temperature water
Properties of Oxide Films on Ni-Cr-xFe Alloys in a Simulated PWR Water Environment
会议论文
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018-01-01
作者:
Ru, Xiangkun[1]
;
Lu, Zhanpeng[2]
;
Chen, Junjie[3]
;
Han, Guangdong[4]
;
Zhang, Jinlong[5]
收藏
  |  
浏览/下载:17/0
  |  
提交时间:2019/04/22
Nickel-based alloys
Simulated PWR water
TEM
Iron content
Oxide film
Local oxidation penetration
Effects of iron content in Ni-Cr-Fe alloys on the oxide films formed in an oxygenated simulated PWR water environment
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 509, 页码: 29-42
作者:
Ru, Xiangkun[1]
;
Ma, Jiarong[2]
;
Lu, Zhanpeng[3]
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2019/04/22
Nickel-based alloys
Simulated PWR water
TEM
Iron content
Oxide film
MICROSTRUCTURE ANALYSIS OF STAINLESS STEEL CLADDING ON LOW ALLOY STEEL WELD IN A PWR SAFE END NOZZLE AND CORROSION IN HIGH TEMPERATURE WATER
会议论文
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017-01-01
作者:
Xiong, Qi[1]
;
Lu, Zhanpeng[2]
;
Chen, Junjie[3]
;
Ru, Xiangkun[4]
;
Li, Hongjuan[5]
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/04/24
THE FRACTURE BEHAVIOR OF HYDROGEN-CHARGED A508III LOW ALLOY STEEL IN THE PROCESS OF NATURAL HYDROGEN-ESCAPING
会议论文
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017-01-01
作者:
Xiao, Qian[1]
;
Lu, Zhanpeng[2]
;
Chen, Junjie[3]
;
Peng, Hao[4]
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/04/24
DATA COMPILING AND ANALYSIS OF OXIDE FILM GROWTH ON NICKEL-BASE ALLOYS IN HIGH TEMPERTURE WATER
会议论文
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017-01-01
作者:
Ru, Xiangkun[1]
;
Lu, Zhanpeng[2]
;
Chen, Junjie[3]
;
Peng, Hao[4]
;
Xiong, Qi[5]
收藏
  |  
浏览/下载:20/0
  |  
提交时间:2019/04/24
EFFECTS OF CHARGED HYDROGEN ON OXIDATION BEHAVIOR OF ALLOY 690 IN HIGH TEMPERATURE WATER ENVIRONMENTS
会议论文
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017-01-01
作者:
Peng, Hao[1]
;
Lu, Zhanpeng[2]
;
Ru, Xiangkun[3]
;
Chen, Junjie[4]
;
Ma, Jiarong[5]
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/04/24
Retarding effect of prior-overloading on stress corrosion cracking of cold rolled 316L SS in simulated PWR water environment
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 496, 页码: 313-324
作者:
Chen, Junjie[1]
;
Lu, Zhanpeng[2]
;
Xiao, Qian[3]
;
Ru, Xiangkun[4]
;
Ma, Jiarong[5]
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2019/04/24
Stress corrosion cracking
316L stainless steel
Pressurized water reactor
Single tensile overloading
Cold rolling
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