Abstract
In this paper, a new module for generating the fuel depletion cross section of the PARCS code based on DRAGON lattice code using FORTRAN programming language is produced. The program has been compiled as a module named DPGEN (Dragon Pmaxs library GENerator) which execute the DRAGON code for any desired fuel assembly and using its results to generate PMAXS (Purdue Macroscopic XS) formatted library for the reactor core simulator PARCS code. To prove the DPGEN module and the PMAXS libraries generated by it, two sets of benchmarks are carried out. First, the Bushehr Nuclear Power Plant (BNPP) core reactor was selected and core fuel depletion analyses were performed with PARCS by using the generated PMAXS files from DPGEN. In the second step change of main neutronics parameter during reactor unloading process has been checked. It was found that the DPGEN program produces PMAXS files with high precision and the results of core simulation by PARCS using these libraries has acceptable accuracy.
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