Contribution to neutron dosimetry topics

A method is described of determining the absorbed dose in variation with linear energy transfer for selected neutron spectra in three designated points on a cylindrical phantom, according to tables by Auxier. The quantities are given defined by ICRP, such as the absorbed dose index, the dose equivalent index. The values are compared of the dose equivalent index for monoenergetic neutrons obtained by calculation and that of the maximum dose equivalent as specified by the standard. The dose equivalent index is calculated for the neutron fission spectrum. (author)