Design and Performance Study of Carbon-Containing Neutron Shielding Materials

In this paper, Monte Carlo method is used to simulate the shielding effect of various shielding materials on high energy neutron by using MCNP5. In the experiment, it is found that the density of composite material is very difficult to improve, the shielding effect of material is far inferior to that of layered design, so the design of this paper is layered. The optimum thickness of different materials is obtained by counting the energy and selecting different shielding materials for different energies.The main research contents are as follows: Firstly, the shielding effect of iron, aluminum, graphite and polyethylene on neutron with different energy is studied, and the results show that the shielding effect of heavy nuclei is better for high energy neutron. Compared to aluminum and iron, found that the use of iron is better, and when the thickness of 24 cm, 14 MeV Neutron shielding after the remaining less than five out of 10,000. Therefore, the first layer of material selection of iron, thickness of 24 cm.It is found that the shielding effect of light nuclei is good for medium neutron. For the neutron around 2 MeV, the shielding effect of polyethylene is better than that of iron. When only 24 cm iron, the maximum count is 0.5 MeV, after shielding neutron count is 0.06; When adding 8 cm polyethylene, the maximum count in 0.5 MeV, after shielding counting only 0.001, but still exist in the lower energy segment peak, thermal neutron count of 0.02, so the neeWhen the boron carbide thickness is 3 cm, the 0.5 MeV neutron count and the thermal neutron count are already very low.When the outermost iron is 12 cm, the maximum count of 0.5 MeV neutron count has dropped to 2000 points. In short, the results of the design of 14 MeV high energy neutron are as follows, such as Iron 24 cm, polyethylene 8 cm, boron carbide 3 cm, iron 12 cm, the effect of layered composite shielding is ideal.