咨询与建议

限定检索结果

文献类型

  • 690 篇 会议
  • 585 篇 期刊文献
  • 1 册 图书

馆藏范围

  • 1,276 篇 电子文献
  • 0 种 纸本馆藏

日期分布

学科分类号

  • 1,024 篇 工学
    • 358 篇 动力工程及工程热...
    • 279 篇 计算机科学与技术...
    • 267 篇 核科学与技术
    • 247 篇 软件工程
    • 228 篇 力学(可授工学、理...
    • 219 篇 化学工程与技术
    • 186 篇 机械工程
    • 162 篇 材料科学与工程(可...
    • 147 篇 安全科学与工程
    • 121 篇 控制科学与工程
    • 117 篇 冶金工程
    • 112 篇 电气工程
    • 78 篇 土木工程
    • 70 篇 电子科学与技术(可...
    • 64 篇 仪器科学与技术
    • 62 篇 交通运输工程
    • 49 篇 信息与通信工程
    • 44 篇 航空宇航科学与技...
    • 41 篇 生物工程
    • 36 篇 光学工程
  • 710 篇 理学
    • 372 篇 物理学
    • 239 篇 化学
    • 238 篇 数学
    • 73 篇 统计学(可授理学、...
    • 55 篇 生物学
    • 27 篇 海洋科学
    • 24 篇 系统科学
  • 130 篇 管理学
    • 116 篇 管理科学与工程(可...
  • 23 篇 医学
  • 14 篇 经济学
  • 10 篇 法学
  • 9 篇 农学
  • 6 篇 教育学
  • 2 篇 军事学
  • 2 篇 艺术学
  • 1 篇 文学

主题

  • 35 篇 nuclear power pl...
  • 16 篇 finite element m...
  • 11 篇 pressurized wate...
  • 10 篇 heat transfer
  • 9 篇 two phase flow
  • 9 篇 heat flux
  • 9 篇 optimization
  • 9 篇 predictive model...
  • 9 篇 silicon carbide
  • 8 篇 simulation
  • 8 篇 sensitivity anal...
  • 8 篇 analytical model...
  • 8 篇 training
  • 7 篇 deep learning
  • 7 篇 computational mo...
  • 7 篇 control systems
  • 7 篇 loss of coolant ...
  • 7 篇 sensors
  • 6 篇 corrosion resist...
  • 6 篇 computational fl...

机构

  • 409 篇 science and tech...
  • 57 篇 science and tech...
  • 39 篇 department of en...
  • 38 篇 school of system...
  • 32 篇 nuclear power in...
  • 26 篇 tianjin key labo...
  • 26 篇 cas key laborato...
  • 25 篇 nuclear power in...
  • 16 篇 national demonst...
  • 12 篇 henan key labora...
  • 11 篇 key laboratory o...
  • 11 篇 fundamental scie...
  • 11 篇 shenzhen key lab...
  • 11 篇 school of nuclea...
  • 10 篇 school of mechat...
  • 10 篇 peng cheng labor...
  • 9 篇 national key lab...
  • 9 篇 college of nucle...
  • 9 篇 key laboratory o...
  • 8 篇 national key lab...

作者

  • 39 篇 deng jian
  • 23 篇 wang kan
  • 23 篇 li qing
  • 21 篇 yu hongxing
  • 17 篇 qiu suizheng
  • 17 篇 tian wenxi
  • 15 篇 peng xingjie
  • 14 篇 su guanghui
  • 13 篇 chen zhi
  • 13 篇 chen ping
  • 13 篇 yao dong
  • 12 篇 huang shanfang
  • 12 篇 zhang dalin
  • 12 篇 gong helin
  • 12 篇 li jishun
  • 11 篇 yu yingrui
  • 11 篇 zhang xu
  • 11 篇 chai xiaoming
  • 11 篇 ma yugao
  • 10 篇 wu dan

语言

  • 1,190 篇 英文
  • 46 篇 中文
  • 31 篇 其他
  • 3 篇 日文
  • 1 篇 法文
检索条件"机构=Science and Technology on Reactor system Design Technology Laboratory"
1276 条 记 录,以下是81-90 订阅
排序:
Research Progress of Metal-Based Shielding Materials for Neutron and Gamma Rays
收藏 引用
Acta Metallurgica Sinica(English Letters) 2021年 第12期34卷 1609-1617页
作者: Bin Gan Shichang Liu Zhen He Fucai Chen Haoxuan Niu Jingchang Cheng Bo Tan Bo Yu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu610213China State Key Laboratory of Light Alloy Casting Technology for High-End Equipment Shenyang Research Institute of Foundry Co.Ltd.Shenyang110022China
The radiation generated by nuclear reaction is harmful to human body and equipment,thus the radiation shielding materials that employ the shielding ability from neutron and gamma rays are the best candidates according... 详细信息
来源: 评论
Sensitivity analysis for dynamical response of reactor coolant system based on optimus
Sensitivity analysis for dynamical response of reactor coola...
收藏 引用
2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Yanli, Yuan Xianhui, Ye Lijuan, Li Feng, Yuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The sensitivity analysis of the dynamical response of reactor coolant system to the input parameters is an important precondition for the design optimization. In this paper, the sensitivity of the dynamical loads at t... 详细信息
来源: 评论
A NUMERICAL SIMULATION METHOD FOR THE VIBRATION REDUCTION OF MR ISOLATOR BASED ON IMPEDANCE TEST  30
A NUMERICAL SIMULATION METHOD FOR THE VIBRATION REDUCTION OF...
收藏 引用
30th International Congress on Sound and Vibration, ICSV 2024
作者: Wenzheng, Zhang Peng, Xiangfeng Zhihao, Yuan Guojiang, Liao Xiaozhou, Jiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
It’s important to choose suitable method to simulate the vibration reduction of the isolators. For a long time, scholars and engineers have been working hard to reduce the error between numerical simulation and exper... 详细信息
来源: 评论
STUDY ON HYDROGEN RISK VENTING MITIGATION MEASURE OF SMALL STEEL CONTAINMENT DURING SEVERE ACCIDENT  29
STUDY ON HYDROGEN RISK VENTING MITIGATION MEASURE OF SMALL S...
收藏 引用
2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Zou, Zhiqiang Zhang, Hang Zhang, Ming Peng, Huanhuan Xu, Youyou Deng, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The hydrogen risk in small steel containment is one of the most important safety problems of small modular reactor (SMR), effective measures need to be taken to mitigate the risk of high concentration hydrogen in a sm... 详细信息
来源: 评论
SGTR ANALYSIS OFSMR ONCE-THROUGH STEAM GENERATOR  29
SGTR ANALYSIS OFSMR ONCE-THROUGH STEAM GENERATOR
收藏 引用
2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Zhu, Ye Xiang, Cheng Wei, Liu Zhiyun, Cai Yun, Ren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The steam generator tube rupture (SGTR) of a nuclear power plant is a transient that is subject to numerous studies. The casing once-through steam generator has great heat-transfer capacity due to its dual-layer heat ... 详细信息
来源: 评论
Determination of Hardware Logic Drawing Simulation Modeling Criteria and Its Application in Nuclear Safety-Class DCS  6th
Determination of Hardware Logic Drawing Simulation Modeling ...
收藏 引用
6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021
作者: Zhang, Xu Chen, Shi-Yong Yao, Zhang Deng, Zhi-Guang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In digital control system (DCS) design, independent hardware logic circuit design is usually used to deal with common causes failures of software. Due to the distinct difference between the design criteria of electric... 详细信息
来源: 评论
Development and verification of SNTA code system for SCWR core steady state analysis  23
Development and verification of SNTA code system for SCWR co...
收藏 引用
23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Wang, Lianjie Zhao, Wenbo Yang, Ping Ma, Yongqiang Lu, Di Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
A coupled neutronics/thermal-hydraulics three dimensional code system SNTA is developed for SCWR core steady state analysis by modular coupling the improved neutronics nodal methodological code and SCWR thermal-hydrau... 详细信息
来源: 评论
A revised method to simulate the dynamic characteristic of vibration isolator of main pump  27
A revised method to simulate the dynamic characteristic of v...
收藏 引用
27th International Congress on Sound and Vibration, ICSV 2021
作者: Zhang, Wenzheng Xiong, Furui Liu, Shuai Yuan, Zhihao Jiang, Xiaozhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
It's important to choose suitable kinetic parameters for vibration isolators to simulate the dynamic characteristic. The kinetic parameters have significant influence on the vibration reduction of vibration isolat... 详细信息
来源: 评论
DATA DRIVEN METHODS FOR BREAK SIZE AND LOCATION ESTIMATION IN LOCA BASED ON DEEP LEARNING  29
DATA DRIVEN METHODS FOR BREAK SIZE AND LOCATION ESTIMATION I...
收藏 引用
2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Yuan, Peng Deng, Jian Qiu, Zhifang Zhu, Dahuan Huang, Tao Li, Zhongchun Du, Peng Xu, Qinglan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Loss of coolant accident (LOCA) is one of the most important accidents in thermal hydraulic design of nuclear power plant. The traditional analysis method is difficult to realize the rapid prediction of the size and l... 详细信息
来源: 评论
COMPARISON OF NUMERICAL ANALYSIS METHODS OF COOLANT ENVIRONMENTAL FATIGUE BASED ON STRAIN RATE CONTROL  29
COMPARISON OF NUMERICAL ANALYSIS METHODS OF COOLANT ENVIRONM...
收藏 引用
2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Shao, Xuejiao Xie, Hai Zhang, Yixiong Xiong, Furui Wang, Xinjun Shi, Kaikai Yu, Mingda Huang, Xuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In this paper, the transformed strain rate of environmental fatigue correction factor (Fen), which is used to consider the influence of PWR primary coolant environment on material fatigue, is studied. EPRI's guide... 详细信息
来源: 评论