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391-400 订阅
排序:
Analysis of PWR SBO scenarios under refueling condition using MAAP5
Analysis of PWR SBO scenarios under refueling condition usin...
收藏 引用
2019 Transactions of the American Nuclear Society, ANS 2019
作者: Yuan, Peng Wu, Xiaoli Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
The defect analysis technology study of reactor pressure vessel main bolt  27
The defect analysis technology study of reactor pressure ves...
收藏 引用
27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Zheng, Liangang Zhang, Rui Huang, Qian Bai, Xiaoming Yuan, Feng Lu, Xifeng Yuan, Yanli Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The existence of non conformances and defects are inescapable during the manufacture and in service of reactor pressure vessel (RPV). After being analyzed, most of the defects have no influence on the capability and s... 详细信息
来源: 评论
Acoustic performance of fluid-filled pipe with periodic helmholtz resonator considering lateral wall elasticity
Acoustic performance of fluid-filled pipe with periodic helm...
收藏 引用
2019 Transactions of the American Nuclear Society, ANS 2019
作者: Zeng, Qingna Wang, Donghui Zang, Fenggang Zhang, Yixiong Science and Technology on Reactor system Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
Improvement and optimization of naspic SVDU engineering design in nuclear power plant according to NUREG0700  27
Improvement and optimization of naspic SVDU engineering desi...
收藏 引用
27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Li, Yutong Xie, Weibo Ma, Quan Zhang, Yu Zhao, Yang Hu, Qingren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
Safety Video Display Unit (SVDU) provides the interface between operator and reactor protection system (RPS).SVDU not only displays the signals and parameters which related to safety function but also support the oper... 详细信息
来源: 评论
The sensitivity analysis of the core lower head molten pool model based on variance decomposition  27
The sensitivity analysis of the core lower head molten pool ...
收藏 引用
27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Li, Zhigang Liu, Wei Ming, Pingzhou Pan, Junjie An, Ping Liu, Dong Lu, Wei Yu, Hongxing Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory ChengDu610041 China
The lower head molten pool model is an important model for the In Vessel Retention (IVR) effectiveness evaluation. It has the characteristics of complex relationship, many input parameters and large uncertainty. The t... 详细信息
来源: 评论
Severe accident mitigation measure and severe accident sequence of SMR  27
Severe accident mitigation measure and severe accident seque...
收藏 引用
27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Yin, Shasha Yan, Sun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
Interest in evaluation of reactor response and off-site consequences following beyond design basis accidents has significantly increased after Fukushima. MELCOR is an advanced computational aid that has been widely us... 详细信息
来源: 评论
A calibration method for raman distributed temperature sensor in nuclear power plant
A calibration method for raman distributed temperature senso...
收藏 引用
2019 Transactions of the American Nuclear Society, ANS 2019
作者: Xiang, Meiqiong Liu, Yanyang Qing, Xianguo Zhu, Jialiang Wu, Qian Zhu, Biwei Xu, Sijie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
Research on boundary disposal of pipes decoupling based on PEPs  27
Research on boundary disposal of pipes decoupling based on P...
收藏 引用
27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Yanli, Yuan Feng, Yuan Xinjun, Wang Xiaoming, Bai Rui, Zhang Liangang, Zheng Xifeng, Lu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
Generally, one of the remarkable characteristics is: compared with the main pipe, the sizes of the auxiliary piping are smaller, which makes the auxiliary piping satisfy the criteria to be decoupled from the main pipi... 详细信息
来源: 评论
Preliminary evaluation of fecral-UN fuel rod performance  14
Preliminary evaluation of fecral-UN fuel rod performance
收藏 引用
14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Gao, Shixin Duan, Zhengang Zhou, Yi Chen, Ping He, Liang Liu, Shichao Zhang, Kun Qiu, Xi Zhang, Ruiqian Science and Technology on Reactor System Design Technology Laboratory No.328 Section 1 Changshun Road Shuangliu County Chengdu610213 China Nuclear Power Institute of China No.328 Section 1 Changshun Road Shuangliu County Chengdu610213 China
After the accident at the Fukushima Daiichi nuclear power plant, many institutions around the world developed the development of accident-tolerant fuel (ATF). Many institutions in China have been conducting research a... 详细信息
来源: 评论
Research on in-plane fluid-elastic instability of heat transfer tube in steam generator  48
Research on in-plane fluid-elastic instability of heat trans...
收藏 引用
48th International Congress and Exhibition on Noise Control Engineering, INTER-NOISE 2019 MADRID
作者: Qi, Huan-Huan Jiang, Nai-Bin Huang, Xuan Feng, Zhi-Peng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328 Changshun Avenue Chengdu China
Due to a small gap between the anti-vibration bars (AVBs) and the heat transfer tubes, and according to the position of AVBs and the number of continuous failures of the in-plane support, the in-plane restraint failur... 详细信息
来源: 评论