Open Access
Issue
EPJ Web Conf.
Volume 302, 2024
Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA + MC 2024)
Article Number 13005
Number of page(s) 11
Section Monte Carlo Methods for Reactor Physics
DOI https://doi.org/10.1051/epjconf/202430213005
Published online 15 October 2024
  1. Romano P. K., Horelik N. E., Herman B. R., et al. OpenMC: A state-of-the-art Monte Carlo code for research and development[J]. Annals of Nuclear Energy, 2015, 82:9097. [Google Scholar]
  2. Leppänen J. Serpent-a continuous-energy Monte Carlo reactor physics burnup calculation code[J]. VTT Technical Research Centre of Finland, 2013, 4:455. [Google Scholar]
  3. Forster R. A., Godfrey T. N. K. MCNP-a general Monte Carlo code for neutron and photon transport[C]//Monte-Carlo Methods and Applications in Neutronics, Photonics and Statistical Physics: Proceedings of the Joint Los Alamos National LaboratoryCommissariat à l’Energie Atomique Meeting Held at Cadarache Castle, Provence, France April 22-26, 1985. Berlin, Heidelberg: Springer Berlin Heidelberg, 2006: 33-55. [Google Scholar]
  4. Stacey W. M. Nuclear reactor physics[M]. John Wiley & Sons, 2018. [Google Scholar]
  5. Marleau, G., Hébert, A., Roy, R., 2012. A User Guide for DRAGON Version 4. Rapport Technique IGE-294. Ecole Polytechnique de Montréal. [Google Scholar]
  6. Halsall, M., Tauman, C., 1997. WIMS-D: a neutronics code for standard lattice physics analysis. Distributed by the NEA Databank, NEA 1507. [Google Scholar]
  7. Collins B., Stimpson S., Kelley B. W., et al. Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT[J]. Journal of Computational Physics, 2016, 326:612–628. [CrossRef] [Google Scholar]
  8. Ryu M., Jung Y. S., Cho H. H., et al. Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code[J]. Journal of Nuclear Science and Technology, 2015, 52(7-8): 961–969. [CrossRef] [Google Scholar]
  9. Chen, J., Liu, Z., Zhao, C., He, Q., Zu, T., Cao, L., Wu, H., 2018. A new high-fidelity neutronics code NECP-X. Ann. Nucl. Energy 116, 417–428. [Google Scholar]
  10. Kitada, T., Takeda, T., 2001. Effective convergence of fission source distribution in monte carlo simulation. J. Nucl. Sci. Technol. 38(5), 324–329. [CrossRef] [Google Scholar]
  11. Carney S. E., Brown F. B., Kiedrowski B. C., et al. Fission matrix capability for MCNP Monte Carlo[R]. Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2012. [CrossRef] [Google Scholar]
  12. Walters W. J., Roskoff N. J., Haghighat A. The rapid fission matrix approach to reactor core criticality calculations[J]. Nuclear Science and Engineering, 2018, 192(1):21–39. [CrossRef] [Google Scholar]
  13. He D., Walters W. J. A local fission matrix correction method for heterogeneous whole core transport with RAPID[J]. Annals of Nuclear Energy, 2019, 134:263–272. [CrossRef] [Google Scholar]
  14. Iwasaki, J., Tsuruta, H., Ichikawa, H., 1985. Neutronics Calculation of Upgraded JRR- 3. JAERI-M-85-062. [Google Scholar]
  15. Hosoya, T., Kato, T., Murayama, Y. “Investigation of JRR-3 Control Rod Worth Changed with Burn-up of Follower Fuel Elements”. In: International Research Reactors: Safe Management and Effective Utilization, Australia, 2007. [Google Scholar]
  16. Liu, S., Wang, G., Wu, G., Wang, K., 2015. Neutronics comparative analysis of platetype research reactor using deterministic and stochastic methods. Ann. Nucl. Energy 79, 133–142. [CrossRef] [Google Scholar]
  17. Zhao C., Peng X., Zhao W., et al. Verification of the direct transport code SHARK with the JRR-3M macro benchmark[J]. Annals of Nuclear Energy, 2022, 177:109294. [Google Scholar]

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