Pasif Nötron Doz Ölçüm Sistemlerinin Monte Carlo Yöntemi ile Benzeşimi

Abstract

The aim of this work is to make Monte Carlo simulations of two different CR-39 passive neutron dosimeter systems used to measure of personal dose equivalents of thermal and fast neutrons. Determination of fluence response and equivalent dose response of these dosimeter systems by using Monte Carlo method were aimed. Neutron interactions within CR-39 dosimeter systems were simulated with the Monte Carlo code developed. Interactions of secondary charged particles with dosimeter materials were simulated by the aid of SRIM software. Chemical etching of tracks formed as a result of charged particle interactions within dosimeter materials were performed by using models present in literature. The equivalent dose response of thermal neutron dosimeter was determined for neutrons have Maxwellian energy distribution. Equivalent dose response of fast neutron dosimeter was determined for 241Am-Be neutron source. The equivalent dose of fast neutrons was found by using track length distributions within CR-39 material. Moreover, the fluence response of fast neutron dosimeter was investigated as a function of chemical etching time.