Abstract
The Monte Carlo computer code MCNP was used to calculate the directional dose equivalent, H'(10), for 0.001 MeV, 0.1 MeV, 1.0 MeV neutrons, and for both unmoderated and D 2 O-moderated 252 Cf neutrons. The dose equivalent in a polymethylmethacrylate (PMMA) dosemeter mounted on a PMMA phantom was also calculated for the unmoderated 252 Cf and D 2 O-moderated 252 Cf sources used for personnel dosemeter calibration at the Pacific Northwest Laboratory. This dosemeter dose equivalent when compared with the directional dose equivalent was found to be much more dependent on the dosemeter composition than on the phantom composition
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