With ²³⁵U fission source in thermal neutron reactor as radiation source, MCNP code is employed to simulate energy spectrum and to study shielding protect.It shows that for prompt neutron, emitting by ²³⁵U fission source, with energy more than 3 MeV, heavy metals materials have better shielding effect.However, light hydrogen materials performance better for neutrons with energy below 1MeV.For compounds-W/LiH, W/B₄C and TiH₂/W, shielding effect is best as weight ratios are W:LiH=19:1, W:B₄C=9:1, W:TiH₂=3:1.GA combined with MCNP code is employed to search optimized design of compounds, W/TiH₂/B₄C, TiH₂/Cu/Gd and TiH₂/B₄C/Gd, respectively.Weight fractions are calculated as shielding effect performance is best.Exponential decay relations between dose equivalent rate (10^-11Sv·h^-1) in tissues caused by neutron and gamma rays penetrating materials and thickness of materials can be expressed as 1.071exp (-0.187 8x), 1.077exp (-0.166 2x) and 1.608exp (-0.171 9x), respectively, where x is thickness of material in cm.