咨询与建议

限定检索结果

文献类型

  • 411 篇 会议
  • 215 篇 期刊文献

馆藏范围

  • 626 篇 电子文献
  • 0 种 纸本馆藏

日期分布

学科分类号

  • 552 篇 工学
    • 284 篇 动力工程及工程热...
    • 240 篇 核科学与技术
    • 173 篇 力学(可授工学、理...
    • 155 篇 计算机科学与技术...
    • 143 篇 软件工程
    • 137 篇 化学工程与技术
    • 131 篇 安全科学与工程
    • 104 篇 机械工程
    • 90 篇 材料科学与工程(可...
    • 86 篇 冶金工程
    • 58 篇 控制科学与工程
    • 42 篇 电气工程
    • 40 篇 交通运输工程
    • 34 篇 土木工程
    • 30 篇 仪器科学与技术
    • 20 篇 信息与通信工程
    • 19 篇 电子科学与技术(可...
    • 18 篇 生物工程
    • 11 篇 石油与天然气工程
    • 10 篇 建筑学
  • 430 篇 理学
    • 246 篇 物理学
    • 162 篇 化学
    • 155 篇 数学
    • 47 篇 统计学(可授理学、...
    • 21 篇 生物学
    • 16 篇 系统科学
    • 9 篇 地球物理学
  • 69 篇 管理学
    • 63 篇 管理科学与工程(可...
  • 7 篇 经济学
  • 5 篇 法学
  • 3 篇 农学
  • 3 篇 医学
  • 2 篇 教育学
  • 1 篇 文学
  • 1 篇 艺术学

主题

  • 33 篇 nuclear power pl...
  • 11 篇 finite element m...
  • 9 篇 silicon carbide
  • 9 篇 heat transfer
  • 8 篇 two phase flow
  • 8 篇 heat flux
  • 7 篇 pressurized wate...
  • 7 篇 sensitivity anal...
  • 6 篇 computational fl...
  • 6 篇 steam generators
  • 6 篇 loss of coolant ...
  • 5 篇 failure analysis
  • 5 篇 nuclear fuels
  • 5 篇 liquid metals
  • 5 篇 condensation
  • 5 篇 digital control ...
  • 5 篇 grain boundaries
  • 5 篇 numerical method...
  • 4 篇 uranium dioxide
  • 4 篇 coolants

机构

  • 411 篇 science and tech...
  • 57 篇 science and tech...
  • 37 篇 department of en...
  • 30 篇 nuclear power in...
  • 25 篇 nuclear power in...
  • 11 篇 key laboratory o...
  • 11 篇 fundamental scie...
  • 11 篇 school of nuclea...
  • 9 篇 national key lab...
  • 8 篇 college of nucle...
  • 8 篇 key laboratory o...
  • 8 篇 school of nuclea...
  • 6 篇 harbin engineeri...
  • 6 篇 state key labora...
  • 6 篇 science and tech...
  • 6 篇 national key lab...
  • 5 篇 cnnc key laborat...
  • 5 篇 state key labora...
  • 5 篇 college of energ...
  • 5 篇 college of physi...

作者

  • 39 篇 deng jian
  • 23 篇 wang kan
  • 23 篇 li qing
  • 22 篇 yu hongxing
  • 15 篇 peng xingjie
  • 15 篇 qiu suizheng
  • 14 篇 tian wenxi
  • 13 篇 yao dong
  • 13 篇 su guanghui
  • 12 篇 huang shanfang
  • 12 篇 gong helin
  • 12 篇 chen ping
  • 12 篇 chai xiaoming
  • 11 篇 yu yingrui
  • 11 篇 chen zhi
  • 11 篇 zhang xu
  • 11 篇 ma yugao
  • 10 篇 bai xiaoming
  • 10 篇 qiu zhifang
  • 10 篇 deng zhi-guang

语言

  • 591 篇 英文
  • 20 篇 中文
  • 11 篇 其他
  • 1 篇 法文
检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是191-200 订阅
排序:
Simulation and Calculation of Proximity Effect of Coils under Fast Transients  13
Simulation and Calculation of Proximity Effect of Coils unde...
收藏 引用
13th Asia-Pacific International Symposium on Electromagnetic Compatibility and Technical Exhibition, APEMC 2022
作者: Wang, Zongyang Song, Wenchang Xie, Yanzhao He, Xianjian Xi'An Jiaotong University State Key Laboratory of Electrical Insulation and Power Equipment School of Electrical Engineering Xi'an China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
Proximity effect over a broad frequency range plays an important role in analyzing transients in the coils. The frequency dependent characteristic makes proximity effect a tricky problem. This paper first introduces F... 详细信息
来源: 评论
The Influence of Suspension and Deposition on Pool Boiling Heat Transfer of Nanofluids: Experiment and Engineering Model Study
SSRN
收藏 引用
SSRN 2024年
作者: Peng, Cheng Song, Youya Deng, Jian Wu, Jiang Chen, Helin Liu, Fang College of Energy and Mechanical Engineering Shanghai University of Electric Power Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Applications including heat exchangers, high power electronic components, and nuclear reactors now require heat transfer technologies that can achieve both high efficiency and compact footprints. Because nanofluids ha... 详细信息
来源: 评论
High-Order Coupling Method of Reaction Rate-Nuclide Density Used in Kylin-2 Code
SSRN
收藏 引用
SSRN 2022年
作者: Hu, Yuying Liao, Hongkuan Yao, Dong Yu, Yingrui Zhou, Bingyan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China China
The Projected Prediction-Correction(PPC) method is the most widely used method coupled transport calculation with burnup calculation nowadays, with linear rate(LR) interpolation for normal nuclides and logarithmic lin... 详细信息
来源: 评论
Effect of Fission Defects on Tensile Strength of U3si2 Σ5(210) Grain Boundary from First-Principles Calculations
SSRN
收藏 引用
SSRN 2023年
作者: Zhao, Jiajun Sun, Dan Xi, Liu Chen, Ping Zhao, Jijun Wang, Yuanyuan Dalian University of Technology Liaoning Dalian China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
U3Si2 is regarded as a promising accident tolerant fuel (ATF) to replace the commercial fuel UO2;however, U3Si2 grain boundary (GB) embrittlement caused by irradiation-induced defect segregation remains to be clarifie... 详细信息
来源: 评论
Effect of AU Ion Irradiation on Microstructure, Mechanical, and Lead-Bismuth Eutectic Corrosion Properties of Zirconia Coatings with Different Y2o3 Content
SSRN
收藏 引用
SSRN 2024年
作者: Zhu, Changda Qu, Guofeng Zhou, Mingyang Qiu, Xi Gao, Yang Long, Ziyao Yang, Jijun Key Laboratory of Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu610064 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The yttria-stabilized zirconia (YSZ) coatings with 4 ~ 6 mol.% Y2O3 content was irradiated by 6 MeV Au ions with a fluence 6.0[[EQUATION]]1015 ions/cm2. The cubic to monoclinic transformation of ZrO2 is is identified ... 详细信息
来源: 评论
A Study of Flow Measurement Uncertainty Quantification Based on Sample Chunked Bayesian Inference
SSRN
收藏 引用
SSRN 2024年
作者: Lu, Zihan Zhu, Yudi Zhou, Xinzhi Yu, Junhui Dong, Chenlong Wang, Hailin College of Electronic Information Sichuan University Chengdu610000 China National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute of China Chengdu610213 China
The accuracy of coolant flow measurement of reactor Primary Circuit has a direct impact on the safety and stability of nuclear reactors. However, the presence of errors in the measurement method and instrumentation, a... 详细信息
来源: 评论
Relaxation and Crystallization of Amorphous Fecraltimo Coatings: Effects on Mechanical Properties and Lead-Bismuth Eutectic Corrosion Resistance
SSRN
收藏 引用
SSRN 2024年
作者: Yang, Jian Zhou, Mingyang Yang, Jijun Key Laboratory of Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu610064 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The microstructure evolution of amorphous FeCrAlTiMo coatings during annealing process, and the effects of structural relaxation and crystallization on its mechanical properties and LBE corrosion resistance are system... 详细信息
来源: 评论
Optimized Moderator design and Analysis of a Pin-Type Supercritical Carbon Dioxide reactor Based on reactor Monte Carlo Code
Optimized Moderator Design and Analysis of a Pin-Type Superc...
收藏 引用
作者: Zhao, Xingyu Liu, Minyun Cui, Rongyi Huang, Shanfang Wang, Kan Lu, Chuan Department of Engineering Physics Tsinghua University Beijing100084 China Department of Engineering Physics Tsinghua University Beijing100084 China China Nuclear Power Engineering Co. Ltd. Beijing100840 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
This study analyzed an yttrium hydride (YH2) moderated supercritical carbon dioxide cooled reactor loaded with pin-type, beryllium oxide diluted oxide fuel elements to reduce the critical enrichment. The impact of the... 详细信息
来源: 评论
Research on Cylindrical Linear Induction Motor for Drive Mechanism
Research on Cylindrical Linear Induction Motor for Drive Mec...
收藏 引用
International Symposium on Linear Drives for Industry Applications (LDIA)
作者: Xu Niu Tianda Yu Lu Zhang Qingzhao Li Siyu Huang Yanting Liu Hao Wu Yuan Tang School of Electrical Engineering Harbin Institute of Technology Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The control rod drive mechanism (CRDM) is a kind of servo mechanism for the reactor control system of the nuclear power plant. This paper presents a cylindrical linear induction motor suitable for the CRDM. First, the...
来源: 评论
Research on the Remaining Useful Life Prediction Model of Complex Equipment
Research on the Remaining Useful Life Prediction Model of Co...
收藏 引用
Artificial Intelligence and Intelligent Manufacturing (AIIM), International Symposium on
作者: Lei Tang Yifei Tang Junhao Zhang Mengjuan Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China School of Information and Software Engineering University of Electronic Science and Technology of China Chengdu China Glasgow College University of Electronic Science and Technology of China Chengdu China
With the rapid advancement of artificial intelligence technology, the development of intelligent manufacturing has become an inevitable trend. Utilizing AI technology to ensure the safe operation of factories is a cru... 详细信息
来源: 评论