Neutron dosimetry based on nuclear track etched detectors

In this work, the response of a neutron dosimeter based on plastic track detectors has been studied. The detector geometry used consists on a C R-39 detector 500 m thick plus either a Makrofol converter 300 μ m thick or air used as converter, for the study of the response to fast or thermal neutrons respectively. The possibility of using Makrofol as a high energy neutron dosemeter has also been studied. In order to validate the results obtained from Monte Carlo simulations, a set of irradiations to monoenergetic neutron beams has been performed at the Ptb and to realistic fields at Cadarache neutron irradiation facilities. An excellent agreement has been found between the simulated and the experimental values. The lower detection limit value found for C R-39 and fast neutrons was 60 μ Sv. (Author)