Neutron shielding performance of polyethylene-7% B and Al-30 wt% B4C composites fabricated via hot-press sintering en en The current research investigates the neutron shielding features of polyethylene-7% B and Al-30 wt% B4C composites fabricated via hot-press sintering. The practical analysis was conducted via Neutron radiography and Monte Carlo N-Particle (MCNP) simulation. The results illustrated that Al-30 wt% B4C with 5 mm thickness has equivalent neutron absorption properties with 14 mm thickness of PE-7% B. Composites with higher density and homogenous distribution of B4C have better neutron shield properties. Al-30 wt% B4C composite fabricated at 650 °C has a higher neutron absorption property. Experimental and simulation findings confirmed each other at lower thicknesses and Al-30 wt% B4C has better neutron shielding than PE-7% B. At thicknesses over 1 cm, the cross-sectional area of polyethylene-7% B and Al-30 wt% B4C composites are near each other. By increasing the thicknesses of composites, the relative total dose reduction and the shield properties of composites are enhanced. 241 247 Masomeh Ghayebloo Department of Materials Science and Engineering University of Bonab, P.O. Box 5551761167, Bonab Iran Zeinab Naghsh Nejad Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran Iran Nafiseh Araghian Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran Iran Hamzeh Foratirad Nuclear Fuel Cycle Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran Iran hforatirad@aeoi.org.ir Amir Movafeghi Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran Iran Hot-press Monte Carlo Neutron radiography Neutron shielding Vol 4 No 4 Paper 2.pdf [1] G. Jobson, H. Spilker, D. 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