Year: 2024
Type: article
Abstract: Ensuring the reliable use of particle transport computer codes necessitates verification against benchmark experiments. This study aims to verify the Monte Carlo code OpenMC using the criticality benchmark model IEUCOMP- THERM-003 from the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook. The analysis focuses on the TRIGA Mark II reactor cores 132 and 133, employing nuclear cross-section libraries ENDF/B-VIII.0, ENDF/B-VII.1, ENDF/B-VII.0, and ENDF/BVI. 2. Results show that OpenMC provides KEFF values in close agreement with benchmark values, demonstrating its robustness in neutronic simulations. Comparison with MVP code results obtained previously, particularly with JENDL-3.3, shows similar accuracy. J. Bangladesh Acad. Sci. 48(2); 231-236: December 2024
Authors: Saad Islam, Mohammad Abdul Motalab
Institutions: University of Dhaka, Bangladesh Atomic Energy Commission
Language: English
Subfield: Aerospace Engineering
Field: Engineering
Domain: Physical Sciences
Open Access status: diamond
OpenAlex ID: W4405946554