Preliminary Study of Few-channel Unfolding for Neutron Personal Dosimeter

Few-channel unfolding method was used for estimating the neutron personal dose equivalent in this paper because there is large deviation of estimating the occupational exposure in the workplace. Neutron energy response of 31 monoenergetic points was calculated by MCNP for the designed TLD. The response matrixes were obtained by using Lagrange linear interpolation and the dose estimation was analyzed by using the few-channel unfolding softwares of MXD-FC31 and GRV-FC31. The results show that the few-channel unfolding method is practicable for the reasonable evaluation of neutron personal dose equivalent.