Impact of ENDF/B-VII.1 and ENDF/B-VIII.0 Nuclear Data Libraries on NIRR-1 LEU Core Depletion using OpenMC

Authors

Keywords:

NIRR-1, MNSR, Core depletion, Nuclear data libraries, ENDF/B-VIII.0, OpenMC

Abstract

The Nigeria Research Reactor-1 (NIRR-1), a 30 kW Miniature Neutron Source Reactor (MNSR), operates at low power with a highly thermalized neutron spectrum, leading to extremely low fuel burnup over extended lifetimes. Accurate depletion modeling is critical for predicting isotopic evolution, reactivity loss, core lifetime extension via beryllium shims, and safeguards compliance after the 2018 conversion from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel (~13% ²³⁵U in UO₂). This study examines the sensitivity of NIRR-1 LEU core depletion predictions to ENDF/B-VII.1 (2011) and ENDF/B-VIII.0 (2018) nuclear data libraries using the open-source Monte Carlo code OpenMC. Parallel simulations over 10 effective full power days (EFPD) at nominal power kept all inputs identical except the nuclear data library. Results reveal strong convergence in this low-burnup thermal regime. U-235 depletion shows small oscillating differences (average absolute ~0.17%, max |0.32|%), U-238 consumption is negligible (<0.1% net variation), and Pu-239 buildup exhibits a modest systematic positive bias in ENDF/B-VIII.0 (~+0.22% average, up to +0.44% early). Burnup accumulation remains linear with relative differences <0.5% (average ~+0.27% higher in ENDF/B-VIII.0). These subtle effects, stemming from CIELO-project refinements (improved U-235 fission, U-238 resonances, Pu-239 fission/nu-bar), are far smaller than discrepancies in high-burnup light-water reactor benchmarks. Nuclear data library choice has negligible short-term impact on NIRR-1 operations, supporting ENDF/B-VIII.0 adoption for enhanced long-term accuracy without altering core management or safety margins. Extrapolation indicates potential 1–3% cumulative variances over the ~50–60-year LEU lifetime, warranting extended simulations and experimental validation (flux measurements, post-irradiation examination). The work highlights open-source Monte Carlo tools for high-fidelity analysis in resource-limited settings and advances lifetime predictions, non-proliferation safeguards, and capacity building for African research reactors.

Dimensions

Abdulaziz, M., Simon, J., Ibrahim, Y. V., & Asuku, A. (2021). Comparative analysis of core life-time for the NIRR-1 HEU and LEU cores. Progress in Nuclear Energy, 139, 103830. https://doi.org/10.1016/j.pnucene.2021.103830

Asuku, A. (2023). Application of SCALE code for reactor physics analysis of the as-built Nigeria miniature neutron source reactor operating with low enriched uranium fuel. Nuclear Engineering and Design, 405, 112215. https://doi.org/10.1016/j.nucengdes.2023.112215

Brown, D. A., Chadwick, M. B., Capote, R., Kahler, A. C., Trkov, A., Herman, M. W., Sonzogni, A. A., Danon, Y., Carlson, A. D., Dunn, M., Smith, D. L., Hale, G. M., Arbanas, G., Arcilla, R., Bates, C. R., Beck, B., Becker, B., Brown, F., Casperson, R. J., Conlin, J., ... Zhu, Y. (2018). ENDF/B-VIII.0: The 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data. Nuclear Data Sheets, 148, 1–142. https://doi.org/10.1016/j.nds.2018.02.001

Chadwick, M. B., Herman, M., Obložinský, P., Dunn, M. E., Danon, Y., Kahler, A. C., Smith, D. L., Pritychenko, B., Arbanas, G., Arcilla, R., Brewer, R., Brown, D. A., Capote, R., Carlson, A. D., Cho, Y. S., Derrien, H., Guber, K., Hale, G. M., Hoblit, S., Holloway, S., ... Young, P. G. (2011). ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross sections, covariances, fission product yields and decay data. Nuclear Data Sheets, 112(12), 2887–2996. https://doi.org/10.1016/j.nds.2011.11.002

Jonah, S. A., Jibiri, N. N., Funtua, I. I., & Mallam, S. P. (2005a). The Nigerian Research Reactor-1 (NIRR-1): Design, characteristics and applications. Journal of Radioanalytical and Nuclear Chemistry, 266(1), 83–88.

Jonah, S.A.; Balogun, G.I; Umar, I.M.; Mayaki, M.C. (2005). Neutron Spectrum parameters in irradiation channels of the Nigeria Research Reactor – 1 (NIRR – 1) for k0 – NAA standardization. J. Radioanal. Nucl.Chem..266 (1). 83 – 88.

Kim, K. S., & Wieselquist, W. A. (2021). Reactivity underestimation of ENDF/B-VIII.0 compared with ENDF/B-VII.1 for the pressurized water reactor depletion analysis. Transactions of the American Nuclear Society, 124, 520–523. (Also available via OSTI: https://www.osti.gov/servlets/purl/1808386)

Park, H. J., Choi, S., & Shim, H. J. (2019). Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD. Annals of Nuclear Energy, 131, 443–459. https://doi.org/10.1016/j.anucene.2019.04.012

Paul K. Romano, Andrew R. Siegel, Benoit Forget, & Kord Smith (2015). OpenMC: A state-of-the-art Monte Carlo code for research and development. Annals of Nuclear Energy, 82, 90–97.

Romano, P. K., & Forget, B. (2013). The OpenMC Monte Carlo particle transport code. Annals of Nuclear Energy, 51, 274–281. https://doi.org/10.1016/j.anucene.2012.06.040

Romano, P. K., Horelik, N. E., Herman, B. R., Nelson, A. G., & Forget, B. (2015). OpenMC: A state-of-the-art Monte Carlo code for research and development. Annals of Nuclear Energy, 82, 90–97. https://doi.org/10.1016/j.anucene.2014.07.054

Snoj, L., Zerovnik, G., & Ravnik, M. (2012). Computational analysis of the Nigerian Research Reactor-1 (NIRR-1) core with Monte Carlo methods. Annals of Nuclear Energy, 46, 71–79.

Yahaya, B., Ahmed, Y. A., Balogun, G. I., & Agbo, S. A. (2017). Estimating NIRR-1 burn-up and core life time expectancy using the codes WIMS and CITATION. Results in Physics, 7, 196–202. https://doi.org/10.1016/j.rinp.2016.12.013

Published

2026-06-06

How to Cite

Opashola, G. A., Joseph, E., & Asuku, A. (2026). Impact of ENDF/B-VII.1 and ENDF/B-VIII.0 Nuclear Data Libraries on NIRR-1 LEU Core Depletion using OpenMC. Nigerian Journal of Physics, 35(3), 37-45. https://doi.org/10.62292/njp.v35i3.2026.613

How to Cite

Opashola, G. A., Joseph, E., & Asuku, A. (2026). Impact of ENDF/B-VII.1 and ENDF/B-VIII.0 Nuclear Data Libraries on NIRR-1 LEU Core Depletion using OpenMC. Nigerian Journal of Physics, 35(3), 37-45. https://doi.org/10.62292/njp.v35i3.2026.613