Individual neutron dosimetry by means of fission track detectors and albedo in the nuclear power plants

A system based on fission fragment tracks has been developed for individual neutron dosimetry. The dosemeter detects both fast neutrons by means of the 232Th(n,f) reaction, and thermal and albedo neutrons by means of the 235U(n,f) reaction. The fission tracks produced in a plastic foil are chemically etched and counted by spark discharges. On the other hand two albedo dosimetric systems have been made operational. They are based on the detection, by thermoluminescence, of neutrons thermalized and backscattered by the wearer's body. The sensitivity of these individual dosemeters has been investigated in 36 different neutron fields: monoenergetic beams, reference fields near isotopic sources, radiation fields encountered in a variety of situations inside nuclear power plants. The results obtained have been compared to those computed by convolution of the neutron spectra with the energy response functions of the dosemeters. The whole set of data constitutes a consistent basis, prerequisite to the use of the systems for neutron individual dosimetry. In practical situations, it is essential to know the shape of the neutron spectrum, approximately at least, in order to perform an accurate dose evaluation. For that purpose, the neutron fields encountered inside nuclear power plants have been grouped into four categories, for which algorithms for dose evaluation have been developed. Concerning the neutron equivalent dose, the residual error associated to this approach does not exceed a factor of 2, which represents a significant improvement in the field of individual neutron dosimetry. (author) figs., tabs., 91 refs