Abstarct: One of the biggest challenges in neutron dosimetry is the dependence of detector responses on the energy of the incident neutron.CR-39 is a solid-state nuclear track detector (SSNTD) with good sensitivity for neutron dosimetry, but its response dependency on neutron energy means that the detector response in a calibrated neutron field cannot be applied to other neutron fields. As the neutron energy spectrum changes, the detector response varies, resulting in uncertainty in the obtained dose equivalent. Therefore, the detector response needs correction. To this end, the response of CR-39 must be measured in various neutron fields, but this is impractical as calibrated neutron sources are not available in the country. The only available calibrated neutron source is the (_‍^241)Am-Be source at the National Nuclear Safety Center. Therefore, to calculate the response of CR-39 in other neutron fields, a modeling approach is required. In this study, the CR-39 detector response in the (_‍^241)Am-Be neutron field was obtained both experimentally and through simulation. After validating the simulation, it was used to calculate the CR-39 response in other neutron fields. Subsequently, correction coefficients for these neutron fields were calculated. These correction coefficients enable the calibration curve obtained for the (_‍^241)Am-Be neutron source to be used in other neutron fields, thereby reducing the uncertainty in the read dose equivalent.