AWCC Simulations Based on Monte Carlo Code RMC

Abstract Neutron multiplicity measurement technology utilizes the correlation of neutron emission times during fission in nuclear materials. By employing mathematical tools to interpret processes such as neutron generation, multiplication, and detection in nuclear materials, a point model equation can be derived through this process. Simultaneously, nuclear material mass can be inverted based on neutron multiplicity counting. Due to the different spontaneous fission neutron yields of uranium and plutonium, neutron multiplicity analysis methods are divided into active and passive methods. This article is based on the independently developed Monte Carlo program RMC, which models and analyzes the AWCC device, and studies the neutron multiplicity counting in both active and passive methods. At the same time, the parameters of the point model equations are calculated, and the influence of different gate widths on the results is analyzed, demonstrating the capability of RMC in solving this problem. This expands the application of RMC in this field and provides reference for the design of subsequent experimental instruments.