Abstract
The shielding for 14 MeV neutrons from a D-T generator at SLAC needs to be optimised in terms of shield thickness and cost. Shielding calculations were made using the MCNP4B Monte Carlo code and the ENDF/B-VI cross section set. The following materials were studied: iron, borated polyethylene, three types of normal and heavy concrete, and combinations of iron and borated polyethylene. The effects of shielding geometry (sphere, cube, and the proposed geometry) were also examined. The results of the transmission factor for ambient dose equivalent, as well as the attenuation lengths and the average energies, for neutrons and gammas outside the shielding are presented.
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