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.