Abstract
Chinese integrated pressurized water reactor (CIPWR) has compact configuration and high inherent safety, which is appropriate for nuclear power plants of small and medium scale. Heat balance model has been adopted widely in thermal power calibration of PWRs because of its advantage of accuracy. In this paper, a package based on FORTRAN language is developed and added into RELAP5 to calculate the heat loss value needed in heat balance analysis. The steady-state operation of CIPWR is modelled correctly by RELAP5. The heat loss of CIPWR is calculated by the package, and the comparison of the main values of parameters needed in the heat loss calculation between RELAP5 and the package has been done. It shows that the package has high calculation accuracy and can be applied in reactor design and monitoring.
Highlights
Reactor Excursion and Leak Analysis Program (RELAP5) is a reactor analysis program developed by Idaho National Engineering Laboratory (INEL), approved by Nuclear Regulatory Commission (NRC) for engineering review of thermal hydraulic calculation of PWRs [1]
Our study aims at evaluating the performance of Chinese integrated pressurized water reactor (CIPWR) in stable and transient operations
RELAP5/ MODE3.4 is used to model the stable condition of CIPWR and calculate the heat loss needed in heat balance analysis with the package we developed
Summary
Reactor Excursion and Leak Analysis Program (RELAP5) is a reactor analysis program developed by Idaho National Engineering Laboratory (INEL), approved by Nuclear Regulatory Commission (NRC) for engineering review of thermal hydraulic calculation of PWRs [1]. RELAP5 has been generally applied to reactor design and safety analysis of PWRs, which is convenient for users and has high calculation efficiency. The heat loss (or increase) from other heat sources (except reactor core) in primary loop is needed in the heat balance calculation, which has to be obtained from operating experience sometimes. There are several different concepts of IPWR proposed by Nuclear Power Institute of China [9, 10] One of these designs of IPWR with coolant pumps is our study object, which is called CIPWR in this paper. RELAP5/ MODE3.4 is used to model the stable condition of CIPWR and calculate the heat loss needed in heat balance analysis with the package we developed. The series of transient accidents of CIPWR will be studied in the future
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