Response of Neutron Dosimeters to Different Neutron Fields

摘要

Correction factors have been calculated for the reading of two different fission-fragment dosimeters (with exp 237 Np and exp 232 Th/U radiators, respectively) in neutron fields of various unshielded and shielded sources. Shielding materials considered were water, polyethylene, concrete, and iron; thicknesses varied up to 180 cm. For three primary neutron spectra shielding factor-versus-thickness plots have been given as an aid to roughly assessing the exposure situation at neutron working places.