Open Access
Issue
EPJ Web Conf.
Volume 302, 2024
Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA + MC 2024)
Article Number 07006
Number of page(s) 8
Section High Performance Computing for Nuclear Data Processing – Benchmarking
DOI https://doi.org/10.1051/epjconf/202430207006
Published online 15 October 2024
  1. G. L. Squires, Introduction to the Theory of Thermal Neutron Scattering, 3rd ed. Cambridge University Press, 2012. [CrossRef] [Google Scholar]
  2. H. Schober, ‘An introduction to the theory of nuclear neutron scattering in condensed matter’, J. Neutron Res., 17(3-4), 109–357, 2014. [Google Scholar]
  3. P. K. Romano, N. E. Horelik, B. R. Herman, A. G. Nelson, B. Forget, K. Smith, ‘OpenMC: A state-of-the-art Monte Carlo code for research and development’, Ann. Nucl. Energy, 82, 90–97, 2015. [CrossRef] [Google Scholar]
  4. H. El Yaakoubi, H. Boukhal, T. El Bardouni, L. Erradi, E. Chakir, K. Benaalilou, M. Lahdour, S. El Ouahdani, et al., ‘Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors’, J. King Saud Univ. - Sci., 31(4), 1271–1275, 2019. [Google Scholar]
  5. H. Guo, X. Huo, K. Feng, H. Gu, ‘Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests’, Nucl. Eng. Technol., 54(10), 3897–3908, 2022. [Google Scholar]
  6. T. Wang, S. Chen, S. Xu, Z. Li, S. Chen, X. Wu, ‘OpenMC interpretation and analysis of two series highly-enriched-uranium thermal-spectrum benchmarks for nuclear data validation’, Ann. Nucl. Energy, 192, 110017, 2023. [CrossRef] [Google Scholar]
  7. D. Heinrichs, B. Lloyd, J. Scorby, ‘Highly Enriched Uranium Metal Moderated by Beryllium Oxide’, NEA/NSC/DOC/(95)03/II. [Google Scholar]
  8. ‘Nuclear Energy Agency (NEA) - International Criticality Safety Benchmark Evaluation Project (iCSBEP) Handbook’. https://www.oecd-nea.org/jcms/pl_20291/international-criticality-safety-benchmark-evaluation-project-icsbep-handbook (accessed Jan. 12, 2023). [Google Scholar]
  9. R. M. Buck, D. E. Cullen, D. P. Heinrichs, E. M. Lent, K. E. Sale, ‘COG - Publicly Available Now to Criticality Safety Practitioners’, Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States), UCRL-CONF-224715, 2006. [Google Scholar]
  10. N. Horelik, B. Herman, B. Forget, K. Smith, ‘Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS)’, in Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering, Sun Valley, Idaho, 2013. [Google Scholar]
  11. D. E. Johnson, R. Mills, ‘Irradiation Behavior of BeO-UO2 Fuel as a Function of FuelParticle Size’, General Atomic Division of United States Atomic Energy Commission, 1963. [Google Scholar]
  12. S.-L. Chen, X.-J. He, C.-X. Yuan, ‘Recent studies on potential accident-tolerant fuelcladding systems in light water reactors’, Nucl. Sci. Tech., 31(3), 32, 2020. [Google Scholar]
  13. S. Chen, C. Yuan, ‘Neutronic study of UO2-BeO fuel with various claddings’, Nucl. Mater. Energy, 22, 100728, 2020. [CrossRef] [Google Scholar]
  14. OpenMC Development Team, ‘S(a,b) name suggestions • Issue #1945 • openmc- dev/openmc — github.com’. [Online]. Available: https://github.com/openmc-dev/openmc/issues/1945. [Accessed: 15-Jul-2024]. [Google Scholar]
  15. OpenMC Development Team, ‘Fixes for various bugs • Pull Request #1949 • openmc- dev/openmc — github.com’. [Online]. Available: https://github.com/openmc-dev/openmc/pull/1949. [Accessed: 15-Jul-2024]. [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.