Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model
Publish Year: 1396
نوع سند: مقاله ژورنالی
زبان: English
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شناسه ملی سند علمی:
JR_JACM-3-3_005
تاریخ نمایه سازی: 1 اردیبهشت 1397
Abstract:
Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very fast model for predicting thermal hydraulics behavior of pressurized water reactor core has been developed. For verifying the results of this model, we used RELAP5 code as US nuclear regulatory approved thermal hydraulics code. The results of developed single heated channel model have been checked with RELAP5 results for WWER-1000. This comparison shows the capability of single heated channel model for predicting thermal hydraulics behavior of reactor core.
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Authors
Reza Akbari
Amirkabir University of Technology (Tehran Polytechnic), Department of Energy Engineering and Physics, Tehran, Iran
Dariush Rezaei
Amirkabir University of Technology (Tehran Polytechnic), Department of Energy Engineering and Physics, Tehran, Iran
Ahmad Gharib
Amirkabir University of Technology (Tehran Polytechnic), Department of Energy Engineering and Physics, Tehran, Iran