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检索条件"机构=Science and Technology On Reactor System Design Technology Laboratory"
1292 条 记 录,以下是1191-1200 订阅
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Prediction of the critical heat flux in subcooled flow boiling in round tube using an improved mechanistic model
Prediction of the critical heat flux in subcooled flow boili...
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18th International Conference on Nuclear Engineering, ICONE18
作者: Na, Yu Yu, Zhang National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute of China Chengdu Sichuan 610041 China
Among the existing CHF models, the bubble crowding model and the liquid sublayer dryout model have been well accepted for subcooled flow boiling. But both of the two models couldn't give explanation about some det... 详细信息
来源: 评论
Radar equation of high-speed weak target
Radar equation of high-speed weak target
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International Conference on Advanced Mechatronic systems (ICAMechS)
作者: Cun-suo Pang Nan Zhang Xiang-yang Lu National Key Laboratory for Electronic Measurement Technology Key Laboratory of Instrumentation Science and Dynamic Measurement of Ministry of Education North University of China Taiyuan China Second System Design Department of the Second Research Academy of CASIC Beijing China Electrical Engineering Department Electrical Engineering Department Zhengzhou China
Without considering the echo signal power changes caused by target distance changes during the accumulated time the traditional radar equation is hardly applied. We take account of the effects of velocity, signal-to-n... 详细信息
来源: 评论
Research on the influence of ocean condition on the oscillation in parallel double-channel
Research on the influence of ocean condition on the oscillat...
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18th International Conference on Nuclear Engineering, ICONE18
作者: Zhou, Linglan Hong, Zhang Department of Physic Engineering Tsinghua University China National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute Of China China
In this paper, the flow oscillation in the parallel multichannel system has been studied under ocean condition with RELAP5/MC. A double-channel boiling system model is built using the code RELAP5/MC and it is proved t... 详细信息
来源: 评论
Study on fracture toughness prediction for A508-III steel based on Master Curve approach
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Hedongli Gongcheng/Nuclear Power Engineering 2011年 第SUPPL. 1期32卷 31-34页
作者: Fang, Ying Li, Hui Hui, Hu He, Yin-Biao Li, Pei-Ning Key Laboratory of Safety Science of Pressurized System East China University of Science and Technology Shanghai 200237 China Shanghai Nuclear Engineering Research and Design Institute Shanghai 200233 China
In this study, tensile test and Charpy impact test of domestic A508-III steel are carried out in the ductile-brittle transition range, in which obtained the mechanical properties and temperature dependence of Charpy i... 详细信息
来源: 评论
Formal definition method of denotational semantics and functions for PLC program language
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Zhongnan Daxue Xuebao (Ziran Kexue Ban)/Journal of Central South University (science and technology) 2011年 第SUPPL. 1期42卷 1107-1113页
作者: Xiao, Li-Tian Gu, Ming Sun, Jia-Guang National Laboratory for Information Science and Technology School of Software Tsinghua University Beijing 100084 China Key Laboratory for Information System Security of Ministry of Education Department of Computer Science and Technology Tsinghua University Beijing 100084 China Beijing Special Engineering Design and Research Institute Beijing 100028 China
In order to verify the correctness of PLC programs by formal methods, the definition of denotational semantics on PLC program language was studied to achieve PLC programs modeling and model checking. Based on the exte... 详细信息
来源: 评论
Computational method for crack-opening-area of nuclear pressure pipe with circumferential through-wall crack
Computational method for crack-opening-area of nuclear press...
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18th International Conference on Nuclear Engineering, ICONE18
作者: Jun, Liu Bo, Yan Naibin, Jiang Department of Engineering Mechanics Chongqing University Chongqing 400044 China National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute of China Chengdu Sichuan China
The determination of crack-opening-area (COA) is very important in the application of LBB technique. A numerical method based on coupled finite element-meshless Galerkin method (FEM/EFG) is proposed to calculate the c... 详细信息
来源: 评论
Nodal SP3 method for solving neutron transport equation
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Hedongli Gongcheng/Nuclear Power Engineering 2010年 第SUPPL. 2期31卷 73-78+91页
作者: Li, Yun-Zhao Wu, Hong-Chun Cao, Liang-Zhi Yao, Dong School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an 710049 China Science and Technology on Reactor System Design Technology Laboratory Chengdu 610041 China
This paper establishes a nodal method to solve the two coupled equations transformed from the transport equation by SP3 method. In the nodal method, diffusion equation is discretized into average fluxes in the nodes a... 详细信息
来源: 评论
Subgroup method for resonance self-shielding calculation and research on resonance interference effect
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Hedongli Gongcheng/Nuclear Power Engineering 2010年 第SUPPL. 2期31卷 5-8+20页
作者: Huang, Shi-En Wang, Kan Yao, Dong Department of Engineering Physics Tsinghua University Beijing 100084 China Science and Technology on Reactor System Design Technology Laboratory Chengdu 610041 China
We combined the subgroup method and the method of characteristics for neutron resonance self-shielding calculation, and programmed a resonance calculation code SGMOC. This code is based on the WIMSD format multi-group... 详细信息
来源: 评论
Generalized coarse-mesh finite difference acceleration for the method of characteristics
Generalized coarse-mesh finite difference acceleration for t...
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International Conference on the Physics of reactors 2010, PHYSOR 2010
作者: Chai, Xiaoming Yao, Dong Wang, Kan National Key Laboratory of Science and Technology on Reactor System Design Technology in China P. O. Box 622-509 Chengdu 610041 China Department of Engineering Physics Tsinghua University Beijing 100084 China
Based on generalized coarse mesh rebalance (GCMR) method, this paper proposes a new acceleration method for the method of characteristics (MOC) in unstructured meshes: the generalized coarse-mesh finite difference (GC... 详细信息
来源: 评论
Research on control and operation support integrated system for nuclear power plants
Research on control and operation support integrated system ...
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2010 International Conference on Computer, Mechatronics, Control and Electronic Engineering, CMCE 2010
作者: Zhi, Chen Yao, Zhang Chen, Deng-Ke Ren, Yu National Key Laboratory of Design Technology of Nuclear Reactor System Nuclear Power Institute of China Chengdu China Department of Nuclear Power Science and Engineering Naval University of Engineering Wuhan China
At present, the information and control system (I&C) and operation support system (OSS) of the nuclear power plants (NPPs) are designed separately;their structures and functions are independent. So, the compatibil... 详细信息
来源: 评论