ICONE23-1297 Program Design for CSR1000 Passive Residual Heat Removal System

Abstract

China supercritical water cooled reactor CSR1000 is one of the fourth generation advanced reactors and is the first one which introduces passive safety system into the fourth generation reactor. Establish an analysis module based on Fortran language for the isolation condenser system (ICS) of CSR1000. This module mainly includes solving the flow control equation. Based on this module, sensitivity analysis for the ICS of CSR1000 is done, which mainly analysis the influence of outlet pressure and temperature, the decay power and the height difference of hot and cold end. Results show that, with the increase of the core exit temperature and the height difference between hot and cold end, the natural circulation flow rate is gradually increased, while with the increase of the outlet pressure and the decrease of heating power, the natural circulation flow rate gradually decreases. Between the core outlet pressure and temperature, the temperature has a greater influence on the natural circulation flow rate.