咨询与建议

限定检索结果

文献类型

  • 457 篇 会议
  • 278 篇 期刊文献

馆藏范围

  • 735 篇 电子文献
  • 0 种 纸本馆藏

日期分布

学科分类号

  • 628 篇 工学
    • 296 篇 动力工程及工程热...
    • 247 篇 核科学与技术
    • 182 篇 力学(可授工学、理...
    • 182 篇 计算机科学与技术...
    • 163 篇 软件工程
    • 149 篇 化学工程与技术
    • 134 篇 安全科学与工程
    • 124 篇 机械工程
    • 107 篇 材料科学与工程(可...
    • 91 篇 冶金工程
    • 72 篇 控制科学与工程
    • 53 篇 电气工程
    • 44 篇 交通运输工程
    • 42 篇 土木工程
    • 34 篇 仪器科学与技术
    • 30 篇 信息与通信工程
    • 27 篇 电子科学与技术(可...
    • 25 篇 生物工程
    • 17 篇 建筑学
    • 12 篇 光学工程
  • 476 篇 理学
    • 263 篇 物理学
    • 172 篇 化学
    • 169 篇 数学
    • 50 篇 统计学(可授理学、...
    • 29 篇 生物学
    • 20 篇 系统科学
  • 85 篇 管理学
    • 71 篇 管理科学与工程(可...
    • 14 篇 工商管理
    • 13 篇 图书情报与档案管...
  • 10 篇 经济学
  • 8 篇 医学
  • 7 篇 法学
  • 3 篇 教育学
  • 3 篇 农学
  • 2 篇 文学
  • 1 篇 艺术学

主题

  • 37 篇 nuclear power pl...
  • 11 篇 finite element m...
  • 9 篇 heat flux
  • 9 篇 silicon carbide
  • 9 篇 heat transfer
  • 8 篇 two phase flow
  • 8 篇 sensitivity anal...
  • 7 篇 pressurized wate...
  • 7 篇 computational fl...
  • 6 篇 nuclear fuels
  • 6 篇 steam generators
  • 6 篇 loss of coolant ...
  • 5 篇 failure analysis
  • 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

  • 418 篇 science and tech...
  • 56 篇 science and tech...
  • 37 篇 department of en...
  • 30 篇 nuclear power in...
  • 26 篇 nuclear power in...
  • 12 篇 school of system...
  • 11 篇 key laboratory o...
  • 11 篇 fundamental scie...
  • 10 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 department of co...
  • 6 篇 state key labora...
  • 6 篇 science and tech...
  • 6 篇 state key labora...
  • 6 篇 national key lab...
  • 6 篇 school of nuclea...

作者

  • 38 篇 deng jian
  • 23 篇 wang kan
  • 22 篇 li qing
  • 21 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 chen ping
  • 11 篇 yu yingrui
  • 11 篇 chen zhi
  • 11 篇 gong helin
  • 11 篇 zhang xu
  • 11 篇 chai xiaoming
  • 11 篇 ma yugao
  • 10 篇 bai xiaoming
  • 10 篇 qiu zhifang
  • 10 篇 xu tao

语言

  • 602 篇 英文
  • 101 篇 其他
  • 31 篇 中文
  • 1 篇 法文
检索条件"机构=Science and Technology on Reactor System Design Technology Lab"
735 条 记 录,以下是351-360 订阅
Intra Fast Mode Decision Algorithm and Hardware design for AVS2
Intra Fast Mode Decision Algorithm and Hardware Design for A...
收藏 引用
2021 International Conference on Signal Processing and Machine Learning (CONF-SPML)
作者: Hao Xie Kaiyang Liu Yang Zhao Xiao Zheng Xianguo Qing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China School of Software and Microelectronics Peking University
AVS2 is a kind of video coding standard proposed by China,it adopts 33 intra prediction modes to improve coding performance,while the computational complexity has increased *** order to reduce the complexity of AVS2 i... 详细信息
来源: 评论
Study on irradiation damage of rpv steels based on coupling cluster dynamics and crystal plasticity finite element method
Study on irradiation damage of rpv steels based on coupling ...
收藏 引用
2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Wang, Xiaotong Luo, Ying Dong, Yuanyuan Yao, Weihua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China
Irradiation hardening is one of the most important aging effects of reactor pressure vessel (RPV) steel in long-term service. A number of studies have indicated that irradiation hardening is mainly caused by irradiati... 详细信息
来源: 评论
Burnup performance analysis for candidate materials of the LWR accident tolerant control rod  14
Burnup performance analysis for candidate materials of the L...
收藏 引用
14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Liu, Yong Li, Mancang Yu, Yingrui Xiao, Peng Wang, Xingbo Zhang, Bin Wang, Dongyong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328# Section 1 Changshun Avenue Chengdu China
The accident tolerant fuel (ATF) is considered to be one of the most advanced concepts to improve the safety of light water reactors (LWRs). The accident tolerant control rod (ATCR) is a significant aspect in the ATF ... 详细信息
来源: 评论
Optimal Spatial-Temporal Triangulation for Bearing-Only Cooperative Motion Estimation
arXiv
收藏 引用
arXiv 2023年
作者: Zheng, Canlun Mi, Yize Guo, Hanqing Chen, Huaben Lin, Zhiyun Zhao, Shiyu College of Computer Science and Technology Zhejiang University Hangzhou China WINDY Lab Department of Artificial Intelligence Westlake University Hangzhou China School of System Design and Intelligent Manufacturing Southern University of Science and Technology Shenzhen China Peng Cheng Laboratory Shenzhen China
Vision-based cooperative motion estimation is an important problem for many multi-robot systems such as cooperative aerial target pursuit. This problem can be formulated as bearing-only cooperative motion estimation, ... 详细信息
来源: 评论
DC-Side Decoupling Method of DC-link Capacitor Reduction for Single Phase PWM Rectifier
DC-Side Decoupling Method of DC-link Capacitor Reduction for...
收藏 引用
2020 IEEE Sustainable Power and Energy Conference, iSPEC 2020
作者: Wang, Jinxin Renyong, Peng Dai, Kailei Zhang, Zhiqiang Zhang, Ting Zhao, Junjie Chen, Qian Zhang, Jianjian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China
The integrated charging system of Electric vehicle consists of a single-phase PWM rectifier and a Buck converter. When the single-phase PWM rectifier works with unit power factor, the dc-link voltage contains a large ... 详细信息
来源: 评论
Study on the thermal-mechanical performance of SiC composites cladding under multiple conditions
Study on the thermal-mechanical performance of SiC composite...
收藏 引用
2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Yin, Chunyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No.328 section 1 changshun avenue Chengdu China
SiC has become a candidate cladding material of Accident Tolerant Fuels (ATF) due to its excellent irradiation stability and corrosion resistance. However, because SiC is a ceramic material with low toughness, brittle... 详细信息
来源: 评论
Experimental Study on Flow Patterns in Narrow Rectangular Channels
SSRN
收藏 引用
SSRN 2022年
作者: Lv, Xindi Zhang, Dalin Song, Gongle Su, Guanghui Tian, Wenxi Qiu, Suizheng State Key Laboratory of Multiphase Flow in Power Engineering Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
Plate fuel elements are commonly used in compact nuclear reactors due to the advantages of high fuel consumption. In this paper, the two-phase flow pattern in the coolant channel of plate fuel elements, i.e. the recta... 详细信息
来源: 评论
Effect of residual pore on the performance of UN kernel TRISO particle fuel  14
Effect of residual pore on the performance of UN kernel TRIS...
收藏 引用
14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Liu, Shichao Chen, Ping Zhou, Yi Pang, Hua Xi, Yong Tang, Changbing Zhao, Yanli Qiu, Xi Guo, Zixuan Nuclear power institute of China Science and Technology on Reactor System Design Technology Laboratory Changshun Stress No.1 Chengdu Sichuan610200 China
The thermal-mechanical performance of uranium nitride (UN) tri-isotropic (TRISO) particle with residual pore used in Light Water reactor (LWR) was investigated. The effect of pore size and location on the performance ... 详细信息
来源: 评论
Thermionic Conversion Performance Analysis of the Single-Cell Thermionic Fuel Element Based on Froba-Thermion Code
SSRN
收藏 引用
SSRN 2022年
作者: Lu, Kailin Yao, Hao He, Yanan Wu, Yingwei Zhang, Jing Liao, Haoyu Su, Guanghui H. Qiu, Suizheng School of Nuclear Science and Technology Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology State Key Laboratory of Multiphase Flow in Power Engineering Xi’an Jiaotong University Xi’an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
The thermionic conversion performance of the single-cell thermionic fuel element (TFE) is influenced by fuel mass transfer and other parameters. With the consideration of current flow and heat transfer, the thermionic... 详细信息
来源: 评论
design of Shocks & Vibrations Monitoring system for Long Distance Transportation in Confined Spaces
Design of Shocks & Vibrations Monitoring System for Long Dis...
收藏 引用
Chinese Automation Congress (CAC)
作者: Shiyong Huang Yuru Geng Yong Han Mingfei Gu Chengdu China Nuclear Haichuan Nuclear Technology Co. Ltd Nuclear Power Institute of China Chengdu China School of Network and Communication Engineering Chengdu Technological University Chengdu China Chengdu Vocational & Technical College of Industry Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In real life, many valuable products and highvalue important products are transported in long distances. Shocks and vibrations are caused during transportation, loading and unloading for various reasons. Any shock and...
来源: 评论