Qinshan-I Reactor Shielding Simulation and Sensitivity Analysis Based on JMCT Monte Carlo Code

Qinshan-I reactor has been operated for over thirty years. A great amount of data is obtained from the design, building, operation, life-extension and decommission and can provide the valued reference for the design, building, operation and maintenance of the nuclear power plants with new generation reactors, such as HPR1000. In this paper, the test verification for JMCT Monte Carlo particle transport code is carried out based on the test data of Qinshan-I base mental section, weld section and main pipe. The simulated results show that JMCT code is with high precision in radiation shielding simulation. The resolution of JMCT is better than the commercial code for about 1~2 order.