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- W2359644230 abstract "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." @default.
- W2359644230 created "2016-06-24" @default.
- W2359644230 creator A5053312163 @default.
- W2359644230 date "2013-01-01" @default.
- W2359644230 modified "2023-09-28" @default.
- W2359644230 title "Monte Carlo Simulation of High Density B_4C/Al neutron shielding materials" @default.
- W2359644230 hasPublicationYear "2013" @default.
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