Cross-Verification and validation of steady-state OPAL research reactor neutronic models using OpenMC and MCNP5 Codes: A foundation for advanced coupled simulations

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-03-07 DOI:10.1016/j.anucene.2025.111324

Djahid Lababsa , Hakim Mazrou , Djalal Hamed , Abdelkader Aouaichia , Hamza Hasnaoui

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Abstract

This study develops, verifies, and validates high-fidelity steady-state neutronic models of the OPAL research reactor using OpenMC and MCNP5. The models were developed based on a consistent methodology, utilizing identical input data, geometric modeling, and cross-section libraries, minimizing discrepancies from external factors, ensuring a solid foundation for subsequent code-to-code comparisons.

Verification and validation were conducted through comparisons with results from SERPENT and MCNP6, as well as experimental data. Our results showed strong agreement with the experimental data, including control rod worth calculations within 3% and axial peak factor differences averaging 2% for MCNP5 and 3% for OpenMC. Differences in isothermal temperature and void coefficients were approximately 1 pcm/°C and 7 pcm/%, respectively. Deviations from SERPENT and MCNP6 for few key parameters were within acceptable limits, consistent with reference studies, and attributed to variations in modeling, code differences, and Monte Carlo statistical uncertainties.

Finally, a comprehensive code-to-code comparison of key neutronic parameters, such as reactivity, flux distributions, kinetic parameters, and power distribution, showed excellent agreement between OpenMC and MCNP5, with relative differences under 1% for most parameters.

Overall, this study confirms the reliability of the developed models for simulating the OPAL reactor and establishes OpenMC as a viable alternative to MCNP for reactor physics simulations, laying the foundation for future coupling with thermal–hydraulic models.

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.