Open Access

This article has an erratum: [https://doi.org/10.1051/epjn/2026014]


Issue
EPJ Nuclear Sci. Technol.
Volume 12, 2026
Article Number 20
Number of page(s) 51
DOI https://doi.org/10.1051/epjn/2026011
Published online 19 June 2026
  1. D. Rochman, A. Algora, F. Àlvarez-Velarde, A. Bardelay, Ø. Bremnes, O. Cabellos, D. Cano-Ott, L. Capponi, C. Carmouze, S. Caruso, A. Cummings, R. Dagan, M. Fallot, L. Fiorito, L. Giot, K. Govers, S. Häkkinen, V. Hannstein, A. Hoefer, T.D. Huynh, R. Ichou, G. Ilas, P. Juutilainen, L. Koszuk, M. Kromar, S. Lahaye, J. Lam, F. Laugier, A. Launay, V. Léger, D. Lecarpentier, J. Leppanen, F. Malouch, J.F. Martin, D. McGinnes, R.W. Mills, F. Minato, Y. Nauchi, P. Ortego, P. Petkov, P. Romojaro, S. Sato, M. Seidl, A. Shama, T. Simeonov, A. Sjöland, V. Solans, F. Sommer, S. Tittelbach, A. Tsilanizara, E. Vlassopoulos, V. Vallet, A. Vasiliev, T. Watanabe, G. Žerovnik, An introduction to spent nuclear fuel decay heat for light water reactors: a review from the NEA WPNCS, EPJ Nucl. Sci. Technol. 10, 9 (2024), https://doi.org/10.1051/epjn/2024010 [Google Scholar]
  2. H. Akkurt, R. Hall, F. Johansson, A. Mehic, J. Kierkegaard, H. Liljenfeldt, Spent fuel decay heat measurements at clab: description of decay heat measurements from 2003–2021 under EPRI-SKB collaboration, Tech. Rep. 000000003002026549, Electric Power Research Institute, EPRI, USA, October 2024, https://www.epri.com/research/programs/061149/results/3002026549 [Google Scholar]
  3. F. Sturek, L. Agrenius, Measurements of decay heat in spent nuclear fuel at the Swedish interim storage facility, Clab, Tech. Rep. R-05-62, Svensk Kärnbränslehantering AB (SKB), Sweden, December 2006, https://www.skb.se/publikation/1472024/R-05-62.pdf [Google Scholar]
  4. P. Jansson, M. Bengtsson, U. Bäckström, F. Àlvarez-Velarde, D. Calic, S. Caruso, R. Dagan, L. Fiorito, L. Giot, K. Govers, A.H. Solis, V. Hannstein, G. Ilas, M. Kromar, J. Leppänen, M. Mosconi, P. Ortego, R. Plukiene, A. Plukis, A. Ranta-aho, D. Rochman, L. Ros, S. Sato, P. Schillebeeckx, A. Shama, T. Simeonov, A. Stankovskiy, H. Trellue, S. Vaccaro, V. Vallet, M. Verwerft, G. Žerovnik, A. Sjöland, Blind benchmark exercise for spent nuclear fuel decay heat, Nucl. Sci. Eng. 196, 1125 (2022), https://doi.org/10.1080/00295639.2022.2053489 [CrossRef] [Google Scholar]
  5. I.C. Gauld, G. Ilas, B.D. Murphy, C.F. Weber, Validation of SCALE 5 decay heat predictions for LWR Spent Nuclear Fuel, Tech. Rep. ORNL/TM-2008/015 and NUREG/CR-6972, Oak Ridge National Laboratory, USA, February 2010, https://www.nrc.gov/docs/ML1009/ML100900229.pdf [Google Scholar]
  6. O.W. Hermann, C.V. Parks, J.P. Renier, Technical support for a proposed decay heat guide using Sas2H/Origen-S data, Tech. Rep. NREG/CR-5625, ORNL-6698, Oak Ridge National Laboratory, September 1994, https://www.osti.gov/servlets/purl/43752 [Google Scholar]
  7. G. Ilas, I.C. Gauld, H. Liljenfeldt, Validation of origen for LWR used fuel decay heat analysis with scale, Nucl. Eng. Des. 273, 58 (2014), https://doi.org/10.1016/j.nucengdes.2014.02.026 [Google Scholar]
  8. D. Rochman, Decay heat computational comparison exercise: definition for a PWR UO2 assembly and pincell; specifications for the exercise of WPNCS SG16, Tech. Rep., Nuclear Energy Agency, NEA/NSC/WPNCS/WD(2024)1/REV1, 2024 [Google Scholar]
  9. D. Rochman, J. Taforeau, T. Simeonov, A. Shama, Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods, Nucl. Eng. Des. 410, 112392 (2023), https://doi.org/10.1016/j.nucengdes.2023.112392 [Google Scholar]
  10. A. Shama, D. Rochman, S. Caruso, A. Pautz, Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5, Ann. Nucl. Energy 165, 108758 (2022), https://doi.org/10.1016/j.anucene.2021.108758 [CrossRef] [Google Scholar]
  11. J. Jang, B. Ebiwonjumi, W. Kim, J. Park, J. Choe, D. Lee, Validation of spent nuclear fuel decay heat calculation by a two-step method, Nucl. Eng. Technol. 53, 44 (2021), https://doi.org/10.1016/j.net.2020.06.028 [Google Scholar]
  12. G. Ilas, I.C. Gauld, SCALE analysis of CLAB decay heat measurements for LWR spent fuel assemblies, Ann. Nucl. Energy 35, 37 (2008), https://doi.org/10.1016/j.anucene.2007.05.017 [CrossRef] [Google Scholar]
  13. 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]
  14. E. Brun, A. Zoia, J.C. Trama, S. Lahaye, Y. Nagaya, Inter-code comparison of TRIPOLA and MVP on the MCNP criticality validation suite, in Proceedings of the ICNC-2015, International Conference on Nuclear Criticality Safety Conference (Charlotte, NC, September 13–17, 2015), p. 351, https://cea.hal.science/cea-02489517/document [Google Scholar]
  15. H.J. Park, H. Kang, H.C. Lee, J.Y. Cho, Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD, Ann. Nucl. Energy 131, 443 (2019), https://doi.org/10.1016/j.anucene.2019.04.012 [Google Scholar]
  16. F. Michel-Sendis, I. Gauld, J.S. Martinez, C. Alejano, M. Bossant, D. Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, M. Gren, K. Govers, M. Gysemans, V. Hannstein, F. Havluj, M. Hennebach, G. Hordosy, G. Ilas, R. Kilger, R. Mills, D. Mountford, P. Ortego, G. Radulescu, M. Rahimi, A. Ranta-Aho, K. Rantamäki, B. Ruprecht, N. Soppera, M. Stuke, K. Suyama, S. Tittelbach, C. Tore, S.V. Winckel, A. Vasiliev, T. Watanabe, T. Yamamoto, T. Yamamoto, SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data, Ann. Nucl. Energy 110, 779 (2017), https://doi.org/10.1016/j.anucene.2017.07.022 [CrossRef] [Google Scholar]
  17. C. Carmouze, R. Ichou, G. Ilas, F. Alvarez-Velarde, M. Chernykh, R. García-Baonza, L. Giot, K. Govers, F. Grimaldi, V. Hannstein, A. Hoefer, P. Juutilainen, J. Lams, P. Martinez-Moreno, D. Mennerdahl, U. Mertyurek, Y. Molla, S. Richards, D. Rochman, P. Romojaro, D.S. Grachtrup, A. Shama, N. Slosse, P. Smith, F. Sommer, M.S. Skrodzka, S. Tittelbach, T.W.G. Žerovnik, Overview of spent nuclear fuel inventory results for the ARIANE GU3 sample, in Proceedings of the ICNC-2023, International Conference on Nuclear Criticality Safety Conference (Sendai, Japan, October 1–6, 2023), https://www.osti.gov/biblio/2333758 [Google Scholar]
  18. J.D. Bess, T. Ivanova, I. Hill, J.-F. Martin, J.B. Briggs, L. Scott, M. DeHart, C. Percher, B.J. Marshall, P. Blaise, Intrinsic value of the international benchmark projects, ICSBEP and IRPhEP, for advanced reactor development, Front. Energy Res. 11 (2023), https://doi.org/10.3389/fenrg.2023.1085788 [Google Scholar]
  19. M. Frankl, A. Vasiliev, D. Rochman, H. Ferroukhi, M. Wittel, S. Pudollek, Refinement of the loading curve determination methodology and modeling for Swiss PWR spent fuel final disposal canisters, in Proceedings of the ICNC-2023, International Conference on Nuclear Criticality Safety Conference (Sendai, Japan, October 1–6, 2023), https://www.researchgate.net/publication/377207109_REFINEMENT_OF_THE_LOADING_CURVE_DETERMINATION_METHODOLOGY_AND_MODELING_FOR_SWISS_PWR_SPENT_FUEL_FINAL_DISPOSAL_CANISTERS [Google Scholar]
  20. M. Frankl, M. Hursin, D. Rochman, A. Vasiliev, H. Ferroukhi, Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal, Appl. Sci. 11, 6499 (2021), https://doi.org/10.3390/app11146499 [CrossRef] [Google Scholar]
  21. D. Rochman, O. Leray, G. Perret, A. Vasiliev, H. Ferroukhi, A. Koning, Re-evaluation of the thermal neutron capture cross section of 147Nd, Ann. Nucl. Energy 94, 612 (2016), https://doi.org/10.1016/j.anucene.2016.03.024 [Google Scholar]
  22. D. Rochman, A. Vasiliev, H. Ferroukhi, M. Hursin, R. Ichou, J. Taforeau, T. Simeonov, Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat, EPJ Nucl. Sci. Technol. 7, 14 (2021), https://doi.org/10.1051/epjn/2021013 [CrossRef] [EDP Sciences] [Google Scholar]
  23. D. Rochman, A. Vasiliev, H. Ferroukhi, M. Hursin, Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat, EPJ Nucl. Sci. Technol. 7, 18 (2021), https://doi.org/10.1051/epjn/2021017 [Google Scholar]
  24. D. Rochman, A. Vasiliev, H. Ferroukhi, M. Seidl, J. Basualdo, Improvement of PIE analysis with a full core simulation: the U1 case, Ann. Nucl. Energy 148, 107706 (2020), https://doi.org/10.1016/j.anucene.2020.107706 [CrossRef] [Google Scholar]
  25. G. Žerovnik, P. Schillebeeckx, K. Govers, A. Borella, D. Calic, L. Fiorito, B. Kos, A. Stankovskiy, G. van der Eynde, M. Verwerf, Observables of interest for the characterization of Spent Nuclear Fuel, Tech. Rep. EUR 29301 EN, Publications Office of the European Union, Luxembourg, 2018, https://publications.jrc.ec.europa.eu/repository/bitstream/JRC112361/report_eur_29301en.pdf [Google Scholar]
  26. P. Schillebeeckx, M. Verwerft, P. Romojaro, G. Žerovnik, N. Messaoudi, G. Alaerts, L. Fiorito, K. Govers, J. Paepen, Y. Parthoens, B. Pedersen, A. Stankovskiy, G. Van den Eynde, R. Wynants, An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation, Front. Energy Res. 11, 1162367 (2023), https://doi.org/10.3389/fenrg.2023.1162367 [CrossRef] [Google Scholar]
  27. P. Jansson, M. Bengtsson, U. Bäckström, K. Svensson, M. Lycksell, A. Sjöland, Data from calorimetric decay heat measurements of five used PWR 17x17 nuclear fuel assemblies, Data Brief 28, 104917 (2020), https://doi.org/10.1016/j.dib.2019.104917 [CrossRef] [Google Scholar]
  28. H. Akkurt, H. Liljenfeldt, G. Ilas, S. Baker, Phenomena Identification and Ranking Table (PIRT) for decay heat, Tech. Rep. 3002018440, Electric Power Research Institute, EPRI, USA, July 2020 [Google Scholar]
  29. DIN Standards Committee Materials Testing, Calculation of the decay power in nuclear fuels of light water reactors – Part 1: uranium oxide nuclear fuel for pressurized water reactors, English translation of DIN 25463-1:2014-02, Tech. Rep. DIN 25463-1:2014-02, DIN Standards Committee Materials Testing, Germany, February 2014 [Google Scholar]
  30. American Nuclear Society Standards Committee Working Group ANS-5.1, Decay heat power in light water reactors, Tech. Rep. ANSI/ANS-5.1-2014, American Nuclear Society, November 2014 [Google Scholar]
  31. A. Sotomayor-Rivera, Spent fuel heat generation in an independent spent fuel storage installation, Tech. Rep. US NRC Regulatory Guide 3.54, Rev.2, U.S. Nuclear Regulatory Commission, USA, 2018 [Google Scholar]
  32. A. Sotomayor-Rivera, Spent fuel heat generation in an independent spent fuel storage installation, Tech. Rep. US NRC Regulatory Guide 3.54, Rev.3, U.S. Nuclear Regulatory Commission, USA, 2022, https://www.nrc.gov/docs/ML2206/ML22067A014.pdf [Google Scholar]
  33. Technical Committee ISO/TC 85, Nuclear energy, Sub-Committee SC 6, Power reactor technology, Nuclear energy – Light water reactors – Calculation of the decay heat power in nuclear fuels, Tech. Rep., ISO International Standard, April 2022 [Google Scholar]
  34. S. Skutnik, Emerging visualization and utility capabilities for FULCRU, in SCALE Users’ Group Workshop (June 5–7, Oak Ridge National Laboratory, Oak Ridge, USA, 2024), https://www.ornl.gov/file/2024-sug-workshop-emerging-visualization-and-utility-capabilities-fulcrum/display [Google Scholar]
  35. A. Stankovskiy, G. Van den Eynde, Advanced method for calculations of core burn-up, activation of structural materials, and spallation products accumulation in accelerator-driven systems, Sci. Technol. Nucl. Install. 2012, 545103 (2012), https://doi.org/10.1155/2012/545103 [Google Scholar]
  36. R. Ferrer, J. Rhodes, Generation and initial validation of a new CASMO5 ENDF/B-VIII.0 nuclear data library, in Proceedings of the PHYSOR 2020 (March 29–April 2, Cambridge, UK, 2020) [Google Scholar]
  37. J. Rhodes, K. Smith, D. Lee, CASMO-5 Development and Applications, in Proceedings of the PHYSOR 2006 (September 10–14, Vancouver, BC, Canada, 2006), p. B144, https://www.studsvik.com/SharepointFiles/CASMO-5%20Development%20and%20Applications.pdf [Google Scholar]
  38. A. Persic, A. Trkov, The energy released by neutron capture in thermal reactors, 1999, https://inis.iaea.org/records/ceygs-34k05 [Google Scholar]
  39. L. San-Felice, R. Eschbach, P. Bourdot, Experimental validation of the DARWIN2.3 package for fuel cycle applications, Nucl. Technol. 184, 217 (2013), https://doi.org/10.13182/NT12-121 [Google Scholar]
  40. A. Santamarina, D. Bernard, P. Blaise, P. Leconte, R. Le Tellier, C. Vaglio-Gaudard, J.-F. Vidal, APOLLO2.8: a validated code package for PWR neutronics calculations, in 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV (American Nuclear Society, Vol. 2, 2009) [Google Scholar]
  41. A. Tsilanizara, T. Huynh, New feature of DARWIN/PEPIN2 inventory code: propagation of nuclear data uncertainties to decay heat and nuclide density, Ann. Nucl. Energy 164, 108579 (2021), https://doi.org/10.1016/j.anucene.2021.108579 [CrossRef] [Google Scholar]
  42. A. Santamarina, D. Bernard, P. Blaise, M. Coste, A. Courcelle, T. Huynh, C. Jouanne, P. Leconte, O. Litaize, S. Mengelle, G. Nogue, J.-M. Ruggiéri, O. Sérot, J. Tommasi, C. Vaglio, J.-F. Vidal, The JEFF-3.1.1 nuclear data library: JEFF report 22: validation results from JEF-2.2 to JEFF-3.1.1, Tech. Rep., Nuclear Energy Agency of the OECD (NEA), 2009, https://www.oecd-nea.org/upload/docs/application/pdf/2019-12/nea6807-jeff22.pdf [Google Scholar]
  43. F. Àlvarez Velarde, E. Gonzàlez-Romero, I.M. Rodrìguez, Validation of the burn-up code EVOLCODE 2.0 with PWR experimental data and with a Sensitivity/Uncertainty analysis, Ann. Nucl. Energy 73, 175 (2014), https://doi.org/10.1016/j.anucene.2014.06.049 [CrossRef] [Google Scholar]
  44. T. Goorley, M. James, T. Booth, F. Brown, J. Bull, L. Cox, J. Durkee, J. Elson, M. Fensin, R. Forster, J. Hendricks, H. Hughes, R. Johns, B. Kiedrowski, R. Martz, S. Mashnik, G. McKinney, D. Pelowitz, R. Prael, J. Sweezy, L. Waters, T. Wilcox, T. Zukaitis, Features of MCNP6, Ann. Nucl. Energy 87, 772 (2016), https://doi.org/10.1016/j.anucene.2015.02.020 [CrossRef] [Google Scholar]
  45. J. Sanz, O. Cabellos, N. García-Herranz, ACAB Inventory code for nuclear applications: user’s manual V. 2008, NEA-1839 6, 475 (2008) [Google Scholar]
  46. C. Wemple, H.-N. Gheorghiu, R. Stamm’ler, E. Villarino, Recent advances in the HELIOS-2 lattice physics code, in Proceedings of the Intl. Conf. on the Physics of Reactors (PHYSOR) (Sept. 14–19, Interlaken, Switzerland, 2008) [Google Scholar]
  47. W.A. Wieselquist, E.R.A. Lefebvre, SCALE 6.3.1 user manual, Tech. Rep., Oak Ridge National Laboratory, ORNL/TM-SCALE-6.3.1, 2023, https://doi.org/10.2172/1959594 [Google Scholar]
  48. T. Simeonov, C. Wemple, Advances in Studsvik’s system for spent fuel analysis, EPJ Web Conf. 247, 02021 (2021), https://doi.org/10.1051/epjconf/202124702021 [CrossRef] [EDP Sciences] [Google Scholar]
  49. W. Haeck, B. Decheneaux, VESTA user’s manual – version 2.2.0, Tech. Rep. PSN-EXP/SNC/2017-00251, IRSN, France, 2017 [Google Scholar]
  50. B. Cochet, A. Jinaphanh, L. Heulers, O. Jacquet, Capabilities overview of the MORET 5 Monte Carlo code, Ann. Nucl. Energy 82, 74 (2015), https://doi.org/10.1016/j.anucene.2014.08.022 [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.