Monte Carlo Simulation of High Density B_4C/Al neutron shielding materials

Background: B4C/Al composite is an ideal neutron shielding material with good mechanical property,which is successfully made as spent fuel container.Purpose: To study its shielding property under different conditions,so as to make use of it properly.Method: Monte-Carlo method is applied to calculate the shielding property of B4C/Al composite.Results: The content of B4C and transmission coefficient is a linear relationship,with a small drop.Transmission coefficient show up and down with the increasing neutron energy,When the neutron energy is 0.5,0.8 or 1.2 MeV,there is a low transmission coefficient.Material thickness and transmission coefficient is a exponential relationship,with a great drop.It can reach ideal shielding effect when it's thickness is more than 13 cm.Conclusions: the content of carbide boron can not change neutron shielding effect significantly.B4C/Al composite is suitable for shielding neutron of 0.5,0.8,1.2 MeV.To reduced neutron radiation effect,adding thickness of material is the best way.