CR 39 detector efficiency estimation a neutron emitted by an isotopic source to application in neutron dosimetry

Solid-state nuclear trace detectors, such as the Cr-39 (PADC), are used in neutron dosimetry. By placing a converter like SN1 sheet (natural boron + polyester) on the surface of the trace detector, it can record alpha particles that come from the nuclear reaction (n, α). For this, a program based on Monte Carlo simulations was developed to estimate the efficiency of the detector to neutrons emitted from a 241Am-Be isotopic source. The program uses the code MCNP6.1.0 to calculate the rate of reactions (reactions.cm-3.s-1) produced in the sheet of natural boron. The results of MCNP6.1.0 were manipulated by means of a sub-routine written in Python, generating a volumetric arrangement of 5 x 5 x 10 in natural boron. The subroutine determines which alpha particles from natural boron are capable of producing visible traces on the detector.