The simulation and analysis on the radiation fence of D-D neutron generator by Monte Carlo Method

This paper simulates and analyses the irradiation fence around D-D neutron generator by a method, which combines Monte Carlo and practical measurement. Setting up the model of MCNP(the analog Monte Carlo method for Neutron and Proton´s transport) and analyzing the results are introduced. The energy of neutron from neutron generator is 2.5 MeV. Water has been used as the material of neutron fence. We use the MCNP procedure to simulate them and find the relation between the thickness of the fence material and the quantity of neutron injection. We take the result as a basis for designing the rapied analyzer of cement raw meal using D-D neutron generator. The results approve that Monte Carlo can be used in radiation protection analysis and optimum design of radiation source shield.