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- W2175610068 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" @default.
- W2175610068 created "2016-06-24" @default.
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- W2175610068 date "1991-08-01" @default.
- W2175610068 modified "2023-09-25" @default.
- W2175610068 title "Calibration of Neutron Personnel Dosemeters in Terms of the ICRU Operational Quantities" @default.
- W2175610068 doi "https://doi.org/10.1093/oxfordjournals.rpd.a081046" @default.
- W2175610068 hasPublicationYear "1991" @default.
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