Method for calculating delayed gamma-ray response in the ACRR Central Cavity using MCNP

This document presents the process for a new method developed characterization of delayed gamma-ray radiation fields in pulse reactors like Annular Core Research Reactor (ACRR). The environments used to test this ACRR Central Cavity were various standard irradiation configurations that amounts moderators and shielding. All environment same fission product source energy spectrum. required use sites recorded Monte Carlo N-Particle (MCNP) KCODE tape. A FORTRAN script was written translate extract coordinates sites. then input into an MCNP mode file. Using MATLAB script, parametric analysis performed determined 10K are appropriate number converge correct answer. gave excellent results as compared previous methods. can be applied other research well.