咨询与建议

限定检索结果

文献类型

  • 624 篇 会议
  • 506 篇 期刊文献

馆藏范围

  • 1,130 篇 电子文献
  • 0 种 纸本馆藏

日期分布

学科分类号

  • 906 篇 工学
    • 338 篇 动力工程及工程热...
    • 255 篇 核科学与技术
    • 240 篇 计算机科学与技术...
    • 220 篇 力学(可授工学、理...
    • 215 篇 软件工程
    • 206 篇 化学工程与技术
    • 185 篇 机械工程
    • 157 篇 材料科学与工程(可...
    • 140 篇 安全科学与工程
    • 113 篇 冶金工程
    • 109 篇 控制科学与工程
    • 97 篇 电气工程
    • 63 篇 电子科学与技术(可...
    • 59 篇 仪器科学与技术
    • 53 篇 交通运输工程
    • 51 篇 土木工程
    • 37 篇 信息与通信工程
    • 35 篇 航空宇航科学与技...
    • 35 篇 生物工程
    • 22 篇 建筑学
  • 630 篇 理学
    • 342 篇 物理学
    • 218 篇 数学
    • 217 篇 化学
    • 67 篇 统计学(可授理学、...
    • 49 篇 生物学
    • 22 篇 系统科学
  • 105 篇 管理学
    • 94 篇 管理科学与工程(可...
  • 20 篇 医学
  • 9 篇 法学
  • 9 篇 农学
  • 8 篇 经济学
  • 7 篇 教育学
  • 1 篇 文学
  • 1 篇 军事学
  • 1 篇 艺术学

主题

  • 37 篇 nuclear power pl...
  • 15 篇 finite element m...
  • 10 篇 pressurized wate...
  • 9 篇 two phase flow
  • 9 篇 heat flux
  • 9 篇 silicon carbide
  • 9 篇 heat transfer
  • 9 篇 training
  • 8 篇 sensitivity anal...
  • 8 篇 computational mo...
  • 7 篇 computational fl...
  • 7 篇 automation
  • 7 篇 optimization
  • 7 篇 analytical model...
  • 7 篇 loss of coolant ...
  • 6 篇 corrosion resist...
  • 6 篇 simulation
  • 6 篇 force
  • 6 篇 mechanical prope...
  • 6 篇 nuclear fuels

机构

  • 418 篇 science and tech...
  • 56 篇 science and tech...
  • 39 篇 department of en...
  • 30 篇 nuclear power in...
  • 29 篇 school of system...
  • 28 篇 tianjin key labo...
  • 26 篇 nuclear power in...
  • 25 篇 cas key laborato...
  • 17 篇 national demonst...
  • 13 篇 henan key labora...
  • 11 篇 key laboratory o...
  • 11 篇 fundamental scie...
  • 11 篇 shenzhen key lab...
  • 10 篇 school of mechat...
  • 10 篇 school of nuclea...
  • 9 篇 national key lab...
  • 9 篇 national key lab...
  • 9 篇 key laboratory o...
  • 8 篇 state key labora...
  • 8 篇 college of nucle...

作者

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

语言

  • 930 篇 英文
  • 145 篇 其他
  • 54 篇 中文
  • 2 篇 法文
  • 1 篇 德文
检索条件"机构=Key Laboratory of Science and Technology on Reactor System Design Technology"
1130 条 记 录,以下是161-170 订阅
Prediction of Electromagnetic Shielding Effectiveness of DCS Cabinet Based on Neural Network  7th
Prediction of Electromagnetic Shielding Effectiveness of DCS...
收藏 引用
7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Zhang, Xu Yang, You-wei Yang, Jing-hua Li, Jun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China PowerChina Sichuan Electric Power Engineering Co. Ltd Chengdu610041 China
The shielding effectiveness (SE) of structural components is one of the important indicators of electromagnetic compatibility (EMC) performance, and it is related to the size, material, frequency and test points posit... 详细信息
来源: 评论
Gas Leakage-based Fault Prediction for a Boron-coated Proportional counter  15
Gas Leakage-based Fault Prediction for a Boron-coated Propor...
收藏 引用
15th IEEE Global Reliability and Prognostics and Health Management Conference, PHM-Beijing 2024
作者: Wang, Miao Wei, Wenbin Wan, Bo Huang, Qichang Sun, Shangqing Lu, Weiwei Wu, Chenlu Hong, Shixin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China CNNP Guodian Zhangzhou Energy Co. Ltd. China Nuclear Power Engineering Co. Ltd. Zhangzhou China
Large reaction cross-sections, low operating voltage, extended lifespan, good stability, and suitability for high-temperature and intense gamma radiation settings are among the features of boron-coated proportional co... 详细信息
来源: 评论
Study on the resource utilization of high fluorine-containing organic waste through fluidized incineration
收藏 引用
Waste Disposal and Sustainable Energy 2022年 第2期4卷 117-129页
作者: Wenhan Li Zengyi Ma Jianhua Yan Qianming Huang Xingjian Wen Zian Zhai Bochen Huang Shuang Wang Yongqiang Chen Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu610213China State Key Laboratory of Clean Energy Utilization Institute for Thermal Power EngineeringZhejiang UniversityHangzhou310027China Zhejiang Xianchuang Energy&Technology Co.Ltd Jinhua321000China
In this study,the method of fluidized incineration and water washing to recover hydrogen fluoride(HF)was proposed to dispose of high fluorine-containing organic *** resource utilization of the waste was investigated i... 详细信息
来源: 评论
Research of SSAE-GPC in Coordinated Control system of Nuclear Power Plant  5th
Research of SSAE-GPC in Coordinated Control System of Nuclea...
收藏 引用
5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020
作者: Deng, Zhi-Guang Wu, Qian Zhu, Bi-Wei Lv, Xin Zhu, Jia-Liang Xu, Si-Jie Wang, Xue-Mei National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu610213 China
For the problem of poor control effect of conventional PID controllers in complex systems, this paper fully combines the advantages of deep learning in feature extraction, regression prediction, and predictive control... 详细信息
来源: 评论
A Monte Carlo Code Developed for Radiation Shielding Calculations Based on RMC  23rd
A Monte Carlo Code Developed for Radiation Shielding Calcula...
收藏 引用
23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Ying, Dongchuan Lyu, Huanwen Tang, Songqian Shang, Xiaotong Xiao, Feng National Key Laboratory of Reactor System Design Technology Nuclear Power Institute of China Chengdu610041 China Department of Engineering Physics Tsinghua University Beijing100084 China
In this paper, a new developed Monte Carlo method code, intended to be used in shielding calculations, will be introduced. This code was developed on the basis of RMC and under the collaboration of the Nuclear Power I... 详细信息
来源: 评论
Thermodynamic Analysis and Optimization of Nuclear Closed Air Brayton Cycle  1
收藏 引用
23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Fang, Huawei Yi, Jingwei Zhang, Xiaoyu Liang, Tiebo Qian, Yiran Tang, Xin Chen, Weixiong Key Laboratory of Nuclear Reactor System Design Technology Nuclear Power Institute of China Sichuan Chengdu China State Key Laboratory of Multiphase Flow in Power Engineering Xi’an Jiaotong University Shaanxi Xi’an China
In order to improve the flexibility and adaptability of micro nuclear power systems, air is considered as an optional working fluid of nuclear Brayton cycle. It has ability to avoid shortage of working fluid under ext... 详细信息
来源: 评论
Thermal Management and Dynamic Performance of a Cooler design for the Supercritical CO2 Turbine Shaft Cooling
收藏 引用
FRONTIERS IN ENERGY RESEARCH 2022年 10卷
作者: Li, Jun Gurgenci, Hal Guan, Zhiqiang Li, Jishun Xue, Yujun Li, Lun School of Mechatronics Engineering Henan University of Science and Technology Henan Key Laboratory for Machinery Design and Transmission System Henan University of Science and Technology Luoyang China School of Mechanical and Mining Engineering University of Queensland Brisbane QLD Australia
This paper presents the results of a numerical study on a supercritical CO2 (SCO2) turboshaft cooling device by considering heat transfer and hydrodynamics. A micro-cooling device with a radius clearance of 50 micron ... 详细信息
来源: 评论
Assessment of Coupled Effect of Steam Pipes on Seismic Analysis of reactor Coolant system  7
Assessment of Coupled Effect of Steam Pipes on Seismic Analy...
收藏 引用
7th International Conference on Environmental science and Civil Engineering, ESCE 2021
作者: Li, Lijuan Liu, Zhenyu Li, Hui Ye, Xianhui Ai, Honglei National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu Sichuan China
reactor coolant system is connected with auxiliary pipes, surge pipes and steam pipes. In order to facilitate the dynamic analysis of reactor coolant system, it is necessary to decouple the pipes connected with the re... 详细信息
来源: 评论
Research of Advanced Control Algorithm in Primary Loop Control system  5th
Research of Advanced Control Algorithm in Primary Loop Contr...
收藏 引用
5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020
作者: Deng, Zhi-Guang Zhu, Bi-Wei Wu, Qian He, Peng Xiang, Mei-Qiong Xu, Tao Qing, Yue National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu610213 China
The primary loop system of nuclear power plant is a large-scale control system with serious coupling between loops and complex objects. In order to solve the problem of integrated control of primary loop core power, s... 详细信息
来源: 评论
Multi-physics Coupling Analyses of Nuclear Thermal Propulsion reactor  23rd
Multi-physics Coupling Analyses of Nuclear Thermal Propulsio...
收藏 引用
23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Han, Wenbin Guan, Zechuan Huang, Shanfang Deng, Jian Department of Engineering Physics Tsinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China China Institute of Atomic Energy Beijing China
Nuclear thermal propulsion (NTP) reactors have high-temperature solid-state characteristics and significant thermal expansion, which therefore require multi-physics coupling analyses. In this paper, the framework of N... 详细信息
来源: 评论