Issue
EPJ Nuclear Sci. Technol.
Volume 11, 2025
Euratom Research and Training in 2025: ‘Challenges, achievements and future perspectives’, edited by Roger Garbil, Seif Ben Hadj Hassine, Patrick Blaise, and Christophe Girold
Article Number 18
Number of page(s) 7
DOI https://doi.org/10.1051/epjn/2025012
Published online 27 May 2025
  1. EU-CONVERSION, European Commission Research and Development Information Service (CORDIS) https://cordis.europa.eu/project/id/101163752 [Google Scholar]
  2. EU-QUALIFY, European Commission Research and Development Information Service (CORDIS) https://cordis.europa.eu/project/id/945009 [Google Scholar]
  3. LEU-FOREVER, European Commission Research and Development Information Service (CORDIS) https://cordis.europa.eu/project/id/754378 [Google Scholar]
  4. S. Valance, B. Baumeister, W. Petry, J. Höglund, Innovative and safe supply of fuels for reactors, EPJ Nuclear Sci. Technol. 6, 40 (2020) [CrossRef] [EDP Sciences] [Google Scholar]
  5. HERACLES-CP: European Commission Research and Development Information Service (CORDIS), Towards the Conversion of High Performance Research Reactors in Europe, https://doi.org/10.3030/661935 [Google Scholar]
  6. HERACLES CP, Comprehension Phase, https://www.heracles-consortium.eu/cp.php [Google Scholar]
  7. “Safety Evaluation Report Related to the Evaluation of Low-Enriched Uranium Silicide-Aluminum Dispersion Fuel for Use in Non-Power Reactors”, U.S. Nuclear Reactor Regulation, NUREG-1313 (1988) [Google Scholar]
  8. A. Leenaers, Ph.D. thesis, University of Ghent–SCK CEN, 2014 [Google Scholar]
  9. A. Leenaers, J. Wight, S. Van den Berghe, H. Jin Ryu, J.-F. Valery, Chapter 5.15 – U-Si based fuel system, Compr. Nucl. Mater. (Second Edition) 5, 485 (2020) [CrossRef] [Google Scholar]
  10. J. Wight, High Density Silicide Irradiations at BR2:Irradiation Results of the HiPROSIT and COBRA-FUTURE Experiments, in Transactions European Research Reactor Conference, RRFM (2020) [Google Scholar]
  11. B. Stepnik, Report on existing process on U3Si2, LEU-FOREVER Deliverable D2.1 (2020) [Google Scholar]
  12. J. Allenou, Report on improvement process on U3Si2, LEU-FOREVER Deliverable D2.2 (2019) [Google Scholar]
  13. B. Stepnik, J. Wight, et al., High density fuel plate developments in LEU FOREvER Project, in European Research Reactor Conference (RRFM2019), presentation, Jordan (March 2019) [Google Scholar]
  14. B. Stepnik, J. Wight, et al., Manufacturing of the HiPROSIT irradiation experiment: High density U3Si2 fuel plates, presentation, in International meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Zagreb Croatia (October 2019) [Google Scholar]
  15. A. Leenaers, B. Ye, J. Van Eyken, S. Van den Berghe, ZrN coating as diffusion barrier in U(Mo) dispersion fuel systems, J. Nucl. Mater. 552, 153000 (2021) [CrossRef] [Google Scholar]
  16. S. Van den Berghe, P. Lemoine, Review of 15 Years of High-Density Low-Enriched UMo Dispersion Fuel Development for Research Reactors in Europe, Nucl. Eng. Technol. 46, 125 (2014) [CrossRef] [Google Scholar]
  17. A. Leenaers, J. Wight, S. Van den Berghe, H. Jin Ryu, J.-F. Valery, Chapter 5.16 – U-Mo based fuel system, Compr. Nucl. Mater. (Second Edition) 5, 499 (2020) [CrossRef] [Google Scholar]
  18. W.A. Hanson, et al., Non-destructive analysis of swelling in the EMPIrE fuel test, J. Nucl. Mater. 564, 153683 (2022) [CrossRef] [Google Scholar]
  19. A. Leenaers, et al., Status of the SEMPER FIDELIS and HiPROSIT post irradiation examinations, presentation RERTR-2021 International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) (2021) [Google Scholar]
  20. D. Wachs, C. Clark, R. Duvant, Conceptual Process for the Manufacture of Low-enriched Uranium/Molybdenum Fuel for the High Flux Isotope Reactor, ORNL/TM-2007/39 (Oak Ridge National Laboratory, 2007) [Google Scholar]
  21. X. Hu, X. Wang, V. Joshi, C. Lavender, The effect of thermomechanical processing on second phase particle redistribution in U-10wt%Mo, J. Nucl. Mater. 500, 270 (2018) [CrossRef] [Google Scholar]
  22. K. Choi, et al., Carbide Particle Redistribution in U-10Mo Alloy during Hot and Cold Rolling Processes, PNNL-29771 (2020) [Google Scholar]
  23. R. Kalsar, et al., Characterization Report for the MP-1 Experiment Fabrication Campaign, High Performance Research Reactor Project, PNNL-30372 (2020) [Google Scholar]
  24. C. Wang, Z. Xu, D. Fagan, D. Field, C. Lavender, V. Joshi, Quantifying and qualifying alloys based on level of homogenization: A U-10Mo alloy case study, J. Eng. Mater. Technol. 142, 011012 (2020) [CrossRef] [Google Scholar]
  25. D. Perez, et al., AFIP-4 Irradiation Summary Report, INL/EXT-11-23297 (Idaho National Laboratory, Idaho Falls, 2012) [Google Scholar]
  26. D. Perez, et al., AFIP-6 Mark II Irradiation Summary Report, INL/EXT-12-26305 (Idaho National Laboratory, Idaho Falls, Idaho 83415, 2012) [Google Scholar]
  27. D.M. Perez, et al., AFIP-7 Irradiation Summary Report, INL/EXT-12-25915 (Idaho National Laboratory, Idaho Falls, Idaho 83415, 2012) [Google Scholar]
  28. C. Schwartz, et al., PVD and C2TWP for the fabrication of monolithic U-Mo fuel plates – status update, in Transactions European Research Reactor Conference, RRFM 2021, Finland (2021) [Google Scholar]
  29. B. Baumaster, et al., The EMPIrE irradiation test Destructive PIE of the U-Mo Monolithic plates, in Transactions European Research Reactor Conference, RRFM 2021, Finland (2021) [Google Scholar]
  30. S. Holmstrom, Y. Parthoens, N. Castin, E. Sikik, L. Adriaensen, A. Leenaers, N. Vanhove, J. Wight, Study of classical PIE methodologies for burnup and their comparability, Proceedings RRFM 2024, https://www.euronuclear.org/scientific-resources/conference-proceedings/ [Google Scholar]
  31. S. Holmstrom, J. Wight, A. Leenaers, S. Kalcheva, High loaded and high density fuel irradiations within the EU QUALIFY project, Proceedings RRFM 2023, https://www.euronuclear.org/scientific-resources/conference-proceedings/ [Google Scholar]
  32. S. Holmstrom, J. Wight, TRL analysis of existing RR fuel systems and manufacturing methods Low Enriched Uranium Fuel fOR REsEarch Reactors (LEU FOREvER), Deliverable D4.8 (2022) [Google Scholar]
  33. Horizon 2020 Work Programme 2014–2015 defined Technology Readiness Levels [Google Scholar]
  34. B. Rossaert, J. Wight, BR2 Reactor Irradiation Test Facilities for Research Reactor Fuel Development and Qualification, Proceedings RRFM 2022, https://www.euronuclear.org/scientific-resources/conference-proceedings/ [Google Scholar]

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