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Volume 42 Issue 6
Dec.  2021
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Teng Chen, Xie Heng, Jia Haijun. Assessment of RELAP5 Code for Predicting Unstable Boundary of Type-I Density Wave with Experiment[J]. Nuclear Power Engineering, 2021, 42(6): 65-71. doi: 10.13832/j.jnpe.2021.06.0065
Citation: Teng Chen, Xie Heng, Jia Haijun. Assessment of RELAP5 Code for Predicting Unstable Boundary of Type-I Density Wave with Experiment[J]. Nuclear Power Engineering, 2021, 42(6): 65-71. doi: 10.13832/j.jnpe.2021.06.0065

Assessment of RELAP5 Code for Predicting Unstable Boundary of Type-I Density Wave with Experiment

doi: 10.13832/j.jnpe.2021.06.0065
  • Received Date: 2020-09-15
  • Rev Recd Date: 2021-06-16
  • Publish Date: 2021-12-09
  • In order to estimate the unstable (Type-I DWO) boundary of Type-I density wave of low temperature nuclear heating reactor and determine the parameter interval of its slight-boiling mode, the RELAP5 numerical model of NHR200 similarity experimental loop HRTL200 of low temperature nuclear heating reactor is established in this paper. By comparing the simulation results with the experimental results, the general characteristics of RELAP5/MOD3.2 program for simulating Type-I DWO and the ability to predict the unstable boundary are evaluated, and the effects of inlet and outlet resistance coefficients and interphase friction on the simulation results are analyzed. The results show that the general characteristics of Type-I DWO simulated by RELAP5 program are in good agreement with the experiment; When the operating pressure is not higher than 25 bar (1 bar=105Pa), the deviation between the degree of subcooling boundary value of the unstable boundary calculated by the program and the experimental value is within 3 K; when the operating pressure is greater than 30 bar, the accurate interphase friction relationship can improve the prediction results. Therefore, RELAP5 program can be used to simulate and predict Type-I DWO after selecting the interphase friction relationship matching the circuit.

     

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