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Thermal-hydraulic Stability Analysis of Nuclear Heating Reactors
作者姓名:李金才  高祖瑛  张作义
作者单位:Institute of Nuclear Energy Technology,Tsinghua University
摘    要:Thermal-hydraulicStabilityAnalysisofNuclearHeatingReactorsLiJincai(李金才);GaoZuying(高祖瑛);ZhangZuoyi(张作义)(InstituteofNuclearEner...


Thermal-hydraulic Stability Analysis of Nuclear Heating Reactors
Li Jincai, Gao Zuying, Zhang Zuoyi.Thermal-hydraulic Stability Analysis of Nuclear Heating Reactors[J].Tsinghua Science and Technology,1996(1).
Authors:Li Jincai  Gao Zuying  Zhang Zuoyi
Abstract:The two-phase flow instability that can occur in a natural circulation system is of importance in the design of nuclear heating reactors. The time domain code RETRAN-02 and the frequency domain code NUFREQ were applied to estimate the instability boundary and the effects of such parameters as pressure, inlet resistance and riser height in NHR-5 and an experimental loop. The results of the calculations and the experiments are in good agreement. Nonlinear density wave oscillations were analyzed using the RETRAN-02 code. The theory of nonequilibrium thermodynamics was used to find an explicit criterion to estimate the threshold of the stability. Experimental simulation of the nuclear feedback density wave instability was also carried out in a test loop using. computer controlled electric power.
Keywords:nuclear heating reactor (NHR)  thermal-hydraulics  safety  flow instability
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