Open Access
Issue
EPJ Nuclear Sci. Technol.
Volume 12, 2026
Article Number 14
Number of page(s) 24
DOI https://doi.org/10.1051/epjn/2026006
Published online 08 June 2026
  1. P. Mosca, L. Bourhrara, A. Calloo, A. Gammicchia, F. Goubioud, L. Mao, F. Madiot, F. Malouch, E. Masiello, F. Moreau, S. Santandrea, D. Sciannandrone, I. Zmijarevic, E.Y. Garcia-Cervantes, G. Valocchi, J.F. Vidal, F. Damian, P. Laurent, A. Willien, A. Brighenti, L. Graziano, B. Vezzoni, APOLLO3®: Overview of the new code capabilities for reactor physics analysis, Nucl. Sci. Eng. 199, S17 (2025), https://doi.org/10.1080/00295639.2024.2334992 [Google Scholar]
  2. S. Choi, H. Lee, S.G. Hong, D. Lee, Resonance self-shielding methodology of new neutron transport code STREAM, J. Nucl. Sci. Technol. 52, 1133 (2015), https://doi.org/10.1080/00223131.2014.993738 [Google Scholar]
  3. H. Koike, K. Yamaji, K. Kirimura, D. Sato, H. Matsumoto, A. Yamamoto, Advanced resonance self-shielding method for gray resonance treatment in lattice physics code GALAXY, J. Nucl. Sci. Technol. 49, 725 (2012), https://doi.org/10.1080/00223131.2012.693885 [Google Scholar]
  4. J. Rhodes, D. Lee, K. Smith, CASMO-5 development and applications, PHYSOR-2006 (2006) [Google Scholar]
  5. G. Marleau, R. Roy, A. Hébert, DRAGON: A Collision Probability Transport Code for Cell and Supercell Calculations (École Polytechnique de Montréal, 1994) [Google Scholar]
  6. 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 (2015), https://doi.org/10.1016/j.anucene.2014.07.048 [CrossRef] [Google Scholar]
  7. W. Jakob, J. Rhinelander, D. Moldovan, pybind11 – Seamless operability between C++11 and Python (2017), https://github.com/pybind/pybind11 [Google Scholar]
  8. D. Mancusi, E. Brun, B. Dechenaux, K. Frölicher, T. Gonçalves, A. Jinaphanh, M.A. Kowalski, C. Larmier, F. Malvagi, G. Millasseau, W. Monange, O. Petit, A. Zoia, Overview of TRIPOLI-5, a Monte Carlo code for HPC, EPJ Nucl. Sci. Technol. 10, 26 (2024), https://doi.org/10.1051/epjn/2024028 [Google Scholar]
  9. P. Romano, J. Tramm, P. Shriwise, Language and design evolution of the OpenMC Monte Carlo particle transport code, EPJ Nucl. Sci. Technol. 10, 15 (2024), https://doi.org/10.1051/epjn/2024016 [Google Scholar]
  10. C.R. Harris, K.J. Millman, S.J.v.d. Walt, R. Gommers, P. Virtanen, D. Cournapeau, E. Wieser, J. Taylor, S. Berg, N.J. Smith, R. Kern, M. Picus, S. Hoyer, M.H.v. Kerkwijk, M. Brett, A. Haldane, J.F.d. Río, M. Wiebe, P. Peterson, P. Gérard-Marchant, K. Sheppard, T. Reddy, W. Weckesser, H. Abbasi, C. Gohlke, T.E. Oliphant, Array programming with NumPy, Nature 585, 357 (2020), https://doi.org/10.1038/s41586-020-2649-2 [NASA ADS] [CrossRef] [Google Scholar]
  11. xtensor, https://github.com/xtensor-stack/xtensor [Google Scholar]
  12. xtensor-python, https://github.com/xtensor-stack/xtensor-python [Google Scholar]
  13. G. Guennebaud, B. Jacob, et al., Eigen v3 (2010), http://eigen.tuxfamily.org [Google Scholar]
  14. The HDF Group, Hierarchical Data Format, version 5, https://github.com/HDFGroup/hdf5 [Google Scholar]
  15. H. Belanger, P. Sinh, J. Gaiardelli, Scarabée (2025), https://github.com/scarabee-dev/scarabee [Google Scholar]
  16. B. Fu, L.-R. Zhang, D. She, C.-L. Wei, A. Hébert, XPZLIB: An HDF5-format multi-group cross-section library, Nucl. Sci. Tech. 35, 191 (2024), https://doi.org/10.1007/s41365-024-01536-9 [Google Scholar]
  17. R. Macfarlane, D.W. Muir, R.M. Boicourt, A.C. Kahler, III, J.L. Conlin, The NJOY Nuclear Data Processing System, Version 2016 (Los Alamos National Laboratory, 2017), https://doi.org/10.2172/1338791 [Google Scholar]
  18. D. Brown, M. Chadwick, R. Capote, A. Kahler, A. Trkov, M. Herman, A. Sonzogni, Y. Danon, A. Carlson, M. Dunn, D. Smith, G. Hale, G. Arbanas, R. Arcilla, C. Bates, B. Beck, B. Becker, F. Brown, R. Casperson, J. Conlin, D. Cullen, M.-A. Descalle, R. Firestone, T. Gaines, K. Guber, A. Hawari, J. Holmes, T. Johnson, T. Kawano, B. Kiedrowski, A. Koning, S. Kopecky, L. Leal, J. Lestone, C. Lubitz, J.M. Damián, C. Mattoon, E. McCutchan, S. Mughabghab, P. Navratil, D. Neudecker, G. Nobre, G. Noguere, M. Paris, M. Pigni, A. Plompen, B. Pritychenko, V. Pronyaev, D. Roubtsov, D. Rochman, P. Romano, P. Schillebeeckx, S. Simakov, M. Sin, I. Sirakov, B. Sleaford, V. Sobes, E. Soukhovitskii, I. Stetcu, P. Talou, I. Thompson, S.v.d. Marck, L. Welser-Sherrill, D. Wiarda, M. White, J. Wormald, R. Wright, M. Zerkle, G. Žerovnik, Y. Zhu, 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, Nucl. Data Sheets 148, 1 (2018), https://doi.org/10.1016/j.nds.2018.02.001 [CrossRef] [Google Scholar]
  19. W. Haeck, N. Gibson, P. Talou, ENDFtk: A robust tool for reading and writing ENDF-formatted nuclear data, Comp. Phys. Commun. 303, 109245 (2024), https://doi.org/10.1016/j.cpc.2024.109245 [Google Scholar]
  20. H. Belanger, Papillon Nuclear Data Library – A free and open-source C++/Python library for interacting with ACE files for continuous-energy neutron data, EPJ Nuclear Sci. Technol. 9, 23 (2023), https://doi.org/10.1051/epjn/2023006 [Google Scholar]
  21. K. Tada, Y. Nagaya, S. Kunieda, K. Suyama, T. Fukahori, Development and verification of a new nuclear data processing system FRENDY, J. Nucl. Sci. Technol. 54, 806 (2017), https://doi.org/10.1080/00223131.2017.1309306 [CrossRef] [Google Scholar]
  22. A. Yamamoto, K. Tada, G. Chiba, T. Endo, Multi-group neutron cross section generation capability for FRENDY nuclear data processing code, J. Nucl. Sci. Technol. 58, 1165 (2021), https://doi.org/10.1080/00223131.2021.1921631 [Google Scholar]
  23. A. Yamamoto, T. Endo, G. Chiba, K. Tada, Implementation of resonance up-scattering treatment in FRENDY nuclear data processing System, Nucl. Sci. Eng. 196, 1267 (2022), https://doi.org/10.1080/00295639.2022.2087833 [Google Scholar]
  24. A. Hébert, Applied Reactor Physics (Presses Internationales Polytechnique, 2020), https://books.google.com/books/about/Applied_Reactor_Physics.html?hl= &id=tLcszgEACAAJ [Google Scholar]
  25. R.J.J. Stamm’ler, M.J. Abbate, Methods of Steady-State Reactor Physics in Nuclear Design (Academic Press Inc., 1983) [Google Scholar]
  26. S. Choi, K. Smith, H.C. Lee, D. Lee, Impact of inflow transport approximation on light water reactor analysis, J. Comput. Phys. 299, 352 (2015), https://doi.org/10.1016/j.jcp.2015.07.005 [Google Scholar]
  27. K.S. Smith, Nodal diffusion methods and lattice physics data in LWR analyses: Understanding numerous subtle details, Prog. Nucl. Energy 101, 360 (2017), https://doi.org/10.1016/j.pnucene.2017.06.013 [CrossRef] [Google Scholar]
  28. B. Herman, Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration, Ph.D. thesis, Massachusetts Institute of Technology, 2014, https://dspace.mit.edu/handle/1721.1/95525 [Google Scholar]
  29. D. Knott, A. Yamamoto, Lattice Physics Computations, Handbook of Nuclear Engineering (Springer, 2010) [Google Scholar]
  30. N. Gibson, Novel Resonance Self-Shielding Methods for Nuclear Reactor Analysis, Ph.D. thesis, Massachusetts Institute of Technology, 2016 [Google Scholar]
  31. Y. Xu, Z. Gao, T. Downar, The Calculation of Resonance Parameters for the DeCART MOC Code, M &C + SNA 2007 (Monterey, California, 2007) [Google Scholar]
  32. R. Sanchez, On the Intermediary Resonance method and beyond, Ann. Nucl. Energy 213, 111085 (2025), https://doi.org/10.1016/j.anucene.2024.111085 [Google Scholar]
  33. R.M. Ferrer, J.M. Hykes, Spatially dependent resonance self-shielding in CASMO5, Nucl. Sci. Eng. 197, 333 (2023), https://doi.org/10.1080/00295639.2022.2053491 [Google Scholar]
  34. N. Sugimura, A. Yamamoto, Evaluation of Dancoff factors in complicated geometry using the method of characteristics, J. Nucl. Sci. Technol. 43, 1182 (2006), https://doi.org/10.1080/18811248.2006.9711210 [Google Scholar]
  35. C. Stoker, Z. Weiss, Spatially dependent resonance cross sections in a fuel rod, Ann. Nucl. Energy 23, 765 (1996), https://doi.org/10.1016/0306-4549(95)00074-7 [Google Scholar]
  36. E.E. Lewis, W.F. Miller, Computational Method of Neutron Transport (John Wiley & Sons, 1984) [Google Scholar]
  37. S. Machach, Étude des techniques d’équivalence nodale appliquées aux modèles de réflecteurs dans les réacteurs à eau pressurisée, Master’s thesis, Polytechnique Montréal, 2022 [Google Scholar]
  38. S. Machach, A. Hébert, A. Dall’Osso, Improvements to the Baff-Refl equivalence technique applied to reflector models in PWRs, Nucl. Sci. Eng. 199, S1 (2025), https://doi.org/10.1080/00295639.2024.2328451 [Google Scholar]
  39. G. Gunow, B. Forget, K. Smith, Stabilization of multi-group neutron transport with transport-corrected cross-sections, Ann. Nucl. Energy 126, 211 (2019), https://doi.org/10.1016/j.anucene.2018.10.036 [Google Scholar]
  40. W. Boyd, S. Shaner, L. Li, B. Forget, K. Smith, The OpenMOC method of characteristics neutral particle transport code, Ann. Nucl. Energy 68, 43 (2014), https://doi.org/10.1016/j.anucene.2013.12.012 [Google Scholar]
  41. F. Zhou, Y. Yang, X. Wu, P. Fang, Q. Liang, H. Lai, Y. Guo, Y. Zhu, L. Yang, Research on spherical harmonics method based on the MOC neutron transport code OpenMOC, Ann. Nucl. Energy 208, 110759 (2024), https://doi.org/10.1016/j.anucene.2024.110759 [Google Scholar]
  42. K.S. Smith, J.D. Rhodes, Full-core, 2-D, LWR Core Calculations with CASMO-4E, PHYSOR 2002, Seoul, Korea (2002) [Google Scholar]
  43. L. Li, A Low Order Acceleration Scheme for Solving the Neutron Transport Equation Lulu Li, Master’s thesis, Massachusetts Institute of Technology, 2013 [Google Scholar]
  44. E.W. Larsen, Infinite-medium solutions of the transport equation, SN discretization schemes, and the diffusion approximation, Transport Theor. Stat. Phys. 32, 623 (2003) [Google Scholar]
  45. A. Zhu, M. Jarrett, Y. Xu, B. Kochunas, E. Larsen, T. Downar, An optimally diffusive Coarse Mesh Finite Difference method to accelerate neutron transport calculations, Ann. Nucl. Energy 95, 116 (2016) [Google Scholar]
  46. R. Sanchez, G. Dante, I. Zmijarevic, Diffusion piecewise homogenization via flux discontinuity ratios, Nucl. Eng. Technol. 45, 707 (2013), https://doi.org/10.5516/net.02.2013.518 [Google Scholar]
  47. R. Lawrence, Progress in nodal methods for the solution of the neutron diffusion and transport equations, Prog. Nucl. Energy 17, 271 (1986), https://doi.org/10.1016/0149-1970(86)90034-x [Google Scholar]
  48. M.L. Zerkle, Development of a Polynomial Nodal Method with Flux and Current Discontinuity Factors, Ph.D. thesis, Massachusetts Institute of Technology, 1992 [Google Scholar]
  49. K. Koebke, L. Hetzelt, On the reconstruction of local homogeneous neutron flux and current distributions of light water reactors from nodal schemes, Nucl. Sci. Eng. 91, 123 (1985), https://doi.org/10.13182/nse85-a27435 [Google Scholar]
  50. K.R. Rempe, K.S. Smith, A.F. Henry, SIMULATE-3 pin power reconstruction: Methodology and benchmarking, Nucl. Sci. Eng. 103, 334 (1989), https://doi.org/10.13182/nse89-a23686 [Google Scholar]
  51. P.M. Bokov, D. Botes, R.H. Prinsloo, D.I. Tomašević, A multigroup homogeneous flux reconstruction method based on the ANOVA-HDMR decomposition, Nucl. Sci. Eng. 197, 308 (2023), https://doi.org/10.1080/00295639.2022.2108654 [Google Scholar]
  52. K. Smith, Assembly homogenization techniques for light water reactor analysis, Prog. Nucl. Energy 17, 303 (1986), https://doi.org/10.1016/0149-1970(86)90035-1 [Google Scholar]
  53. L. Liponi, Calculation and Verification of Assembly Discontinuity Factors for the Dragon/Parcs Code Sequence, Master’s thesis, École Polytechnique de Montréal, 2017 [Google Scholar]
  54. C. Josey, Development and Analysis of High Order Neutron Transport–Depletion Coupling Algorithms, Ph.D. thesis, Massachusetts Institute of Technology, 2017 [Google Scholar]
  55. A. Isotalo, G. Davidson, T. Pandya, W. Wieselquist, S. Johnson, Flux renormalization in constant power burnup calculations, Ann. Nucl. Energy 96, 148 (2016), https://doi.org/10.1016/j.anucene.2016.05.031 [Google Scholar]
  56. M. Pusa, Rational approximations to the matrix exponential in burnup calculations, Nucl. Sci. Eng. 169, 155 (2011), https://doi.org/10.13182/nse10-81 [Google Scholar]
  57. P. Maria, Higher-order chebyshev rational approximation method and application to burnup equations, Nucl. Sci. Eng. 182, 297 (2016), https://doi.org/10.13182/nse15-26 [CrossRef] [Google Scholar]
  58. P.K. Romano, C.J. Josey, A.E. Johnson, J. Liang, Depletion capabilities in the OpenMC Monte Carlo particle transport code, Ann. Nucl. Energy 152, 107989 (2021), https://doi.org/10.1016/j.anucene.2020.107989 [CrossRef] [Google Scholar]
  59. N. Horelik, B. Herman, M. Ellis, S. Kumar, J. Liang, B. Forget, K. Smith, Benchmark for Evaluation And Validation of Reactor Simulations (Massachusetts Institute of Technology, 2020) [Google Scholar]
  60. E.E. Lewis, M.A. Smith, N. Tsoulfanidis, G. Palmiotti, T.A. Taiwo, R.N. Blomquist, Benchmark specification for Deterministic 2-D/3-D MOX fuel assembly transport calculations without spatial homogenisation (C5G7 MOX), NEA/NSC (2001) [Google Scholar]
  61. A. Yamamoto, M. Tabuchi, N. Sugimura, T. Ushio, M. Mori, Derivation of optimum polar angle quadrature set for the method of characteristics based on approximation error for the Bickley function, J. Nucl. Sci. Technol. 44, 129 (2007), https://doi.org/10.1080/18811248.2007.9711266 [Google Scholar]
  62. A. Yamamoto, T. Endo, Treatment of corner crossing ray-traces in CMFD acceleration of MOC, J. Nucl. Sci. Technol. 63, 120 (2025), https://doi.org/10.1080/00223131.2025.2490832 [Google Scholar]
  63. G. Sengler, F. Forêt, G. Schlosser, R. Lisdat, S. Stelletta, EPR core design, Nucl. Eng. Des. 187, 79 (1999), https://doi.org/10.1016/s0029-5493(98)00259-3 [CrossRef] [Google Scholar]
  64. K.S. Kim, Specification for the VERA Depletion Benchmark Suite, ORNL/TM–2016/53 (Oak Ridge National Laboratory, 2016) [Google Scholar]
  65. K. Smith, Practical and efficient iterative method for LWR fuel assembly homogenization, Trans. Am. Nucl. Soc. 71, 238 (1994) [Google Scholar]
  66. T. Bahadir, S.-Ö. Lindahl, S. P. Palmtag, SIMULATE-4 Multigroup Nodal Code with Microscopic Depletion Model, M &C 2005 (Avignon, France, 2005) [Google Scholar]
  67. A. Dall’Osso, Assembly rehomogenization methods for reactor analysis, J. Nucl. Eng. 6, 14 (2025), https://doi.org/10.3390/jne6020014 [Google Scholar]
  68. H. Belanger, P. Singh, Scarabée: A Free and Open-Source Lattice Physics Code, M &C 2025, Denver, Colorado (2025) [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.