Test of flow balance in fuel assemblies of the reactor for Qinshan nuclear power plant
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Test of flow balance in fuel assemblies of the reactor for Qinshan nuclear power plant
Nuclear TechniquesVol. 09, Issue 12, (1986)
作者机构:
中国科学院上海原子核研究所
作者简介:
基金信息:
DOI:
CLC:
Received:15 November 1985,
Published:1986-12
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Tongsheng Yao, Chunhua Guo, Yufeng Zhou, et al. Test of flow balance in fuel assemblies of the reactor for Qinshan nuclear power plant[J]. Nuclear techniques, 1986, 09(12): 15-19,55.
DOI:
Tongsheng Yao, Chunhua Guo, Yufeng Zhou, et al. Test of flow balance in fuel assemblies of the reactor for Qinshan nuclear power plant[J]. Nuclear techniques, 1986, 09(12): 15-19,55.DOI:
Test of flow balance in fuel assemblies of the reactor for Qinshan nuclear power plant
This paper described the test of flow balance in fuel assemblies of the pressurized water reactor power plant (300MW) which is the first plant designed and to be built by our country. The resistance matching between parts of the four different structure of fuel assemblies was reasonably settled. The difference of the coolant between them was adjusted to less than 1%. The design of the plug was improved after the test. The dimension of orifice for upper grid plate of the reactor core and resistance coefficients of the outlet for various assemblies have been determined. The test results provide the reliable experimental basis for the thermal-hydraulic and structure design of the Qinshan nuclear power plant.
Experimental and theoretical study on the natural circulation characteristics of humid air in the fuel assembly of a full-scale pressurized water reactor
Geometric configuration of fuel assembly for small lightweight lead-bismuth reactor
Design and analysis of the spent fuel transfer basket for the reprocessing plant
Theoretical research on location of fuel assemblies failure using the activity ratio of134Cs and 137Cs
Design of fuel assembly for molten-salt-cooled reactors
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Related Institution
School of Nuclear Science and Engineering, Shanghai Jiao Tong University
Department of Mechanical Engineering, City University of Hong Kong
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Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, University of South China
Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences