中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
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CAS IR Grid
机构
合肥物质科学研究院 [4]
金属研究所 [3]
采集方式
OAI收割 [7]
内容类型
期刊论文 [7]
发表日期
2021 [1]
2020 [2]
2018 [3]
2015 [1]
学科主题
Materials ... [2]
Metallurgy... [1]
Nanoscienc... [1]
Nuclear Sc... [1]
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Occupational Radiation Exposure Estimated for Fusion Demonstration Reactors and Beyond
期刊论文
OAI收割
FUSION SCIENCE AND TECHNOLOGY, 2021
作者:
Guo, Dingqing
;
Chen, Chao
;
Wang, Zhen
;
Lin, Jian
;
Zhang, Bing
  |  
收藏
  |  
浏览/下载:68/0
  |  
提交时间:2022/01/10
Occupational radiation exposure
risk assessment
collective dose
fusion demonstration reactors
Concept design of 100 kA hybrid DC breaker on China fusion engineering test reactor
期刊论文
OAI收割
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 158
作者:
Hu, Xingguang
;
Li, Hua
;
Song, Zhiquan
;
Ren, Zhigang
;
Wang, Shusheng
  |  
收藏
  |  
浏览/下载:36/0
  |  
提交时间:2020/11/30
Fusion reactors
Superconducting magnets
DC circuit breaker
Power semiconductor switches
Engineering Design and Analysis of the CFETR Divertor Remote Maintenance System
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
Zhao, W. L.
;
Li, Y.
;
Lu, K.
;
Cheng, Y.
;
Gao, X.
  |  
收藏
  |  
浏览/下载:30/0
  |  
提交时间:2020/10/26
Maintenance engineering
Reliability
Remote handling
Plasmas
Manipulators
Stress
Rails
Engineering
fusion reactors
maintenance
remote handling (RH)
tokamak
Current Status and Progress on the Shielding Blanket of CFETR
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1417-1421
作者:
Liu, Changle
;
Yang, Hao
;
Zhang, Jie
;
Zhang, Jianzhong
;
Li, Lei
  |  
收藏
  |  
浏览/下载:18/0
  |  
提交时间:2019/08/23
Chinese fusion engineering test reactor (CFETR)
demonstration reactors (DEMO)
neutronics
shielding blanket (SB)
Effect of Fe2Zr phase on the mechanical properties and fracture behavior of Fe-Cr-W-Zr ferritic alloy
期刊论文
OAI收割
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2018, 卷号: 722, 页码: 173-181
作者:
Jin, XJ
;
Chen, SH
;
Rong, LJ
;
Rong, LJ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, 72 Wenhua Rd, Shenyang 110016, Liaoning, Peoples R China.
  |  
收藏
  |  
浏览/下载:31/0
  |  
提交时间:2018/06/05
Martensitic Steels
Fusion-reactors
Ods Steel
Strength
Deformation
Microstructure
Stability
Zirconium
System
Temperatures
Structural, mechanical and corrosion studies of Cr-rich inclusions in 152 cladding of dissimilar metal weld joint
期刊论文
OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 498, 页码: 9-19
作者:
Li, YF
;
Wang, JQ
;
Han, EH
;
Yang, CD
;
Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China.
  |  
收藏
  |  
浏览/下载:55/0
  |  
提交时间:2018/06/05
Pressurized-water Reactors
Environmentally-assisted Cracking
Safe-end
Quantitative Assessment
Secondary-side
Residual-stresses
High-temperature
Fusion Boundary
Base Alloys
Part 1
Effect of silicon on the microstructure and mechanical properties of reduced activation ferritic/martensitic steel
期刊论文
OAI收割
Journal of Nuclear Materials, 2015, 卷号: 459, 页码: 13-19
S. H.
;
Rong Chen, L. J.
收藏
  |  
浏览/下载:25/0
  |  
提交时间:2015/05/08
ferritic-martensitic steel
laves phase
precipitation behavior
tensile
properties
rafm steel
reactors
deformation
tungsten
fusion
energy