Abstract: The detailed neutron shielding design is one of the main radiation protection design features of the third generation reactor, which will directly affect equipment life located in radiation field and the radiation safety of the workers entering the plant during the power operation. So far, there is no effective neutron calculation method that can meet the engineering design requirements in China due to excessively time-consuming and poor accuracy caused by large scale and complex structure. The MC-MC coupling calculation method is proposed to make the large-scale complex neutron shielding calculation accurately, quickly and effectively. The difference between the results obtained by this method and those obtained by CEPR design shows that this method is reliable in engineering design. This method has been used in a 3rd generation PWR in China.

Key words: neutron shielding, Monte Carlo, MC-MC coupled method, reactor plant