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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:54/0
  |  
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
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
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2022/06/10
Integral reinforcement learning
Nuclear power reactor
Nonlinear system
Optimal tracking control
Neural networks
A new method for safety classification of structures, systems and components by reflecting nuclear reactor operating history into importance measures
期刊论文
NUCLEAR ENGINEERING AND TECHNOLOGY, 2022, 卷号: 54
作者:
Cheng, Jie
;
Liu, Jie
;
Chen, Shanqi
;
Li, Yazhou
;
Wang, Jin
收藏
  |  
浏览/下载:12/0
  |  
提交时间:2022/05/05
Safety classification
Nuclear reactor
Plant operating mode
Plant configuration
Operating history
Importance measure
Research for axial power distribution control of a space nuclear reactor based on nonlinear model
期刊论文
ANNALS OF NUCLEAR ENERGY, 2022, 卷号: 168
作者:
Zhao, Chengxuan
;
Yang, Xiao
;
Yang, Minghan
;
Wang, Jianye
;
Chen, Shuai
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2022/12/23
Power distribution control
Integral Lyapunov function
Distributed parameter control
Exponential stability
Space nuclear reactor
Influence of the Impeller/Guide Vane Clearance Ratio on the Performances of a Nuclear Reactor Coolant Pump
期刊论文
FDMP-FLUID DYNAMICS & MATERIALS PROCESSING, 2022, 卷号: 18, 期号: 1, 页码: 93-107
作者:
Cheng, Xiaorui
;
Liu, Xiang
;
Lv, Boru
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2022/03/01
Nuclear reactor coolant pump
clearance ratio
fluid-solid coupling
stress and strain
numerical calculation
Design of Coordination System for Composite Mobile Robot Platform Oriented to Nuclear Fusion Vessel
期刊论文
JOURNAL OF FUSION ENERGY, 2021, 卷号: 40
作者:
Zhang, Qiang
;
Song, Bo
;
Cai, Bin
;
Sun, Yuxiang
收藏
  |  
浏览/下载:54/0
  |  
提交时间:2021/11/16
EAST nuclear fusion reactor vessel
Multi-joint remote control system
Composite multi-joint remote operation robot platform
Bidirectional coordinated control
Load-bearing performance test
A study on nuclear analysis of the divertor region of the CFETR
期刊论文
PLASMA SCIENCE & TECHNOLOGY, 2021, 卷号: 23
作者:
Saidahmed, Rayyan
;
Yao, Damao
;
Wu, Qiuran
;
Liu, Songlin
;
Xu, Tiejun
收藏
  |  
浏览/下载:26/0
  |  
提交时间:2021/11/15
CFETR
fusion reactor
divertor
nuclear analysis
divertor region
Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data
期刊论文
ANNALS OF NUCLEAR ENERGY, 2021, 卷号: 154, 页码: 8
作者:
Jiang, Wei
;
Gu, Long
;
Zhu, Qing-Fu
;
Zhou, Qi
;
Ma, Fei
收藏
  |  
浏览/下载:52/0
  |  
提交时间:2021/12/10
Lead reactivity worth
VENUS-II light water reactor
Period method
Monte Carle
Nuclear data library
Review of fuel assembly design in lead-based fast reactors and research progress in fuel assembly of China initiative accelerator driven system
期刊论文
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 页码: 12
作者:
Yu, Rui
;
Gu, Long
;
Sheng, Xin
;
Li, Jinyang
;
Zhu, Yanlei
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2021/12/10
China initiative accelerator driven system
fourth‐
generation nuclear energy systems
fuel assembly
lead‐
based fast reactor
Investigation on the Nuclear Heat Deposition of Shielding Blanket for CFETR Phase I
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
收藏
  |  
浏览/下载:25/0
  |  
提交时间:2020/11/26
Computational fluid dynamics (CFD)
China Fusion Engineering Test Reactor (CFETR)
divertor
nuclear heat deposition
shielding blanket (SB)
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