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291-300 订阅
排序:
The investigateion of damage and fracture behavior of particle reinforced composites at mesoscale under complex impact loads  14
The investigateion of damage and fracture behavior of partic...
收藏 引用
14th International Conference on Fracture, ICF 2017
作者: Bai, Xiaoming Guo, Licheng Shi, Kaikai Zheng, Liangang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Astronautic Science and Mechanics Harbin Institute of Technology Harbin150001 China
A mesoscale numerical model for the damage and fracture behavior of particle reinforced composites is proposed in present work. In this model, the digital image technique is used to reconstruct the real microstructure... 详细信息
来源: 评论
Research on trans critical characteristic on sliding pressure booting process of SCWR
Research on trans critical characteristic on sliding pressur...
收藏 引用
2013 21st International Conference on Nuclear Engineering, ICONE 2013
作者: Liu, Liang Zhou, Tao Song, Mingqiang Chen, Juan Luo, Feng Xia, Bangyang North China Electric Power University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The homogeneous flow model of trans critical transient calculation is achieved by the trans critical program of SCWR which is made by FORTRAN. The SCWR sliding pressure starting scheme is simulated by this program. So... 详细信息
来源: 评论
Calculation strategy for the determination of plasticity correction factors  13th
Calculation strategy for the determination of plasticity cor...
收藏 引用
13th Asia-Pacific Symposium on Engineering Plasticity and its Applications, AEPA 2016
作者: Du, Juan Shao, Xue Jiao Kan, Qian Hua Zhang, Ying Fu, Xiao Long Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Southwest Jiaotong University Chengdu610031 China
This paper presents an investigation about the plasticity correction factor, Ke, proposed in the RCC-M code, for the correction of elastic stress range exceeds twice the yield stress which results from both mechanical... 详细信息
来源: 评论
Fuel assembly design for supercritical water-cooled reactor
Fuel assembly design for supercritical water-cooled reactor
收藏 引用
作者: Linna, Feng Fawen, Zhu Science and Technology on Reactor System Design Technology Laboratory Third Section of Huafu Road Huayang Town Shuangliu County Chengdu Sichuan Province610213 China
The supercritical water-cooled reactor (SWCR) has been selected as one of the most promising reactors for Generation IV nuclear reactors due to its higher thermal efficiency and more simplified structure compared to t... 详细信息
来源: 评论
Research on integrated managing system design of NPP
Research on integrated managing system design of NPP
收藏 引用
2014 International Conference on Manufacturing technology and Electronics Applications, ICMTEA 2014
作者: Li, Feng-Yu Yan, Yu-Kun Zhang, Long-Fei Chen, Zhi Liao, Long-Tao Xiao, Kai Naval University of Engineering 125 mailbox Wuhan China Science and technology on reactor system design technology laboratory Nuclear Power Institute of China Chengdu China
In order to improve safety, economy and reliability of NPP(nuclear power plant) and to make the best of human, material and information resources in the NPP, a specific function model developing method for integrated ... 详细信息
来源: 评论
Numerical study on single Droplet's rise in steam separator by using VOF method
Numerical study on single Droplet's rise in steam separator ...
收藏 引用
2014 ANS Winter Meeting and Nuclear technology Expo
作者: Zhang, Di Luo, Qi Huang, Wei Wang, Kan Department of Engineering Physics Tsinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
来源: 评论
CFD simulation of single-phase flow in a 5×5 rod bundle with spacer grid  23
CFD simulation of single-phase flow in a 5×5 rod bundle wit...
收藏 引用
23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Li, Quan Jiao, Yongjun Chen, Jie Yu, Junchong Department of Engineering Physics Tinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Spacer grid is an important component in PWR fuel assemblies for its significant influence on thermal-hydraulic characteristics of the reactor core. In this study, single-phase CFD technology is used to study the flow... 详细信息
来源: 评论
Safety design and evaluation of loss of forced flow accident of CRS1000
Safety design and evaluation of loss of forced flow accident...
收藏 引用
2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
作者: Dan, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Changshun Road No.328 ShuangLiu County Chengdu610213 China
CSR1000 (China supercritical water reactor, 1000MWe) was developed by NPIC, as BWR, the pressure vessel's reactor and directly circulate loop was adopted, however, the coolant will encounter double flow pass in th... 详细信息
来源: 评论
Development and Verification of a New Depletion, Activation and Radiation Source Term Calculation Code  23rd
Development and Verification of a New Depletion, Activation ...
收藏 引用
23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Wen, Xingjian Zhai, Zian Tang, Songqian Tian, Chao Liu, Zhouyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China Xi’an Jiaotong University Xi’anShaanxi China
Existing depletion and source term calculation codes lack flexible interfaces, which is difficult to meet the actual engineering design needs. Based on the Chebyshev rational approximation method, a new depletion, act... 详细信息
来源: 评论
2-D/1-D method for neutron transport based on large-scale parallel computation
2-D/1-D method for neutron transport based on large-scale pa...
收藏 引用
2014 ANS Winter Meeting and Nuclear technology Expo
作者: Wu, Wenbin Li, Qing Wang, Kan Department of Engineering Physics Tsinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
来源: 评论