In this shielding laboratory, shielding experiments are carried out to evaluate shielding ability of resin, serpentine concrete, and water with boron with a neutron source 252Cf and also of spent fuel transportable interim cask models with a neutron source 252Cf and a gamma-ray source 60Co. The experimental data includes not only neutrons and primary gamma rays but also secondary gamma rays produced by the capture of thermal neutrons. Accordingly, in order to improve the evaluation contents, the results of the experiment are analyzed by using the continuous energy Monte Carlo code MCNP, in detail.
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Shielding Laboratory (Cask)
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