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《Nuclear Power Engineering》 2003-S1
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Reactor Hydraulic Simulation Test Study of Qinshan Phase II NPP Project

YANG Lai-sheng,ZONG Gui-fang ,HU Jun (Nuclear Power Institute of China,Chengdu, 610041, China)  
Theoretical calculation, single test and reactor integral simulation test are adopted in this experimental study. The integral model scale is 1:4. The model of the fuel assembly is designed to be the 2? rod bundle in the light of the open lattice core simulation criterion, the lateral and axial flow characteristics is designed to be the same as the prototype respectively, the turbine meter especially made to measure the flow rate and the electrode used to measure the concentration are installed in the inlet of the model assembly. The test installation consists of two hydraulic test loops arranged in symmetry, the rated flow is 21170m3/h. The test results such as the flow rate distribution, resistance coefficients, bypass flow and the mixing factor at the inlet of the core, verify and optimize the design of the reactor, and provide indispensable hydraulic characteristics parameters for the reactor engineering structure, thermo-hydraulics design and safety analysis.
【CateGory Index】: TL375.5
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