Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON

This research focuses on the comparative analysis of PWR fuel assembly based VERA depletion benchmark problems using community-developed open source Monte Carlo code OpenMC, python burnup system ONIX (a coupling interface for OpenMC), and deterministic DRAGON code. The was performed OpenMC with ENDF/B-VII.1 nuclear data library, SHEM-361 DRAGLIB format library (ENDF/B-VII.1). code-to-code evolution k eff , atom number density, power distribution as a function has been result shows good agreement maximum difference within 200 pcm at EOC. However small discrepancy around 90 observed in calculated by compared to presence integral burnable absorbers (IFBA). above-mentioned codes have validated successfully first time against problems. It can be concluded that initial implementation these Department Nuclear Science Engineering under Military Institute Technology, Dhaka, successful further works are utilize depletion/neutronics calculation existing 3MW TRIGA Mark-II reactor VVER-type is commissioned Bangladesh.