Abstract
The Monte Carlo method is essential in field of nuclear engineering and has been widely applied in reactor particle simulation owing to the rapid development of computer technology. Academic institutes and organizations of different countries have developed their own Monte Carlo code. The JMCT code is a Monte Carlo particle transport code developed by the China Academy of Engineering Physics. Before the JMCT Monte Carlo code is applied to the design of new nuclear power plant, the verification and validation (V&V) of the code on the operating reactors is necessary. In this work, the V&V of the JMCT code on criticality calculation and fixed-source calculation was performed on the operating CPR1000 reactors. First, the full core pin-by-pin model of CPR1000 was established and the criticality calculation was performed. Then, the 1/4 core model with irradiation surveillance capsules (ISC) of CPR1000 was established and the fixed-source calculation was performed. The calculation results of JMCT were compared to the reference code and the measured values in the ISC.
