Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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REVIEW OF 15 YEARS OF HIGH-DENSITY LOW-ENRICHED UMo DISPERSION FUEL DEVELOPMENT FOR RESEARCH REACTORS IN EUROPE

  • Van Den Berghe, S. (SCK.CEN, Nuclear Materials Science Institute (NMS)) ;
  • Lemoine, P. (Commissariat a l'Energie Atomique, CEA Saclay, Direction de l'Energie Nucleaire (DEN))
  • Received : 2014.02.22
  • Published : 2014.04.25
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Abstract

This review aims to provide a synthesis of the knowledge generated and the lessons learned in roughly 15 years of UMo dispersion fuel R&D in Europe through a series of irradiation experiments. A lot of irradiations were also performed outside of Europe, particularly in the USA, Russia, Canada, Korea and Argentina. In addition, a large number of out-of-pile investigations were done throughout the world, providing support to the understanding of the phenomena governing the UMo behaviour in pile. However, the focus of this article will be on the irradiations and Post-Irradiation Examination (PIE) results obtained in European experiments. The introduction of the article provides a historic overview of the evolution and progress in the high density UMo dispersion fuel development. The ensuing sections then provide further details on the various phases of the development, from the UMo dispersion in a pure Al matrix through the addition of Si to the matrix to address the interaction layer formation and finally to the more advanced solutions to the excessive swelling encountered in various experiments. This review was based only on published results or results that are currently in the process of being published.

Keywords

References

  1. A. Travelli, "The United-States Reduced Enrichment Research And Test Reactor (Rertr) Program - Accomplishments, Plans, And Schedules", Transactions Of The American Nuclear Society, vol. 35 (NOV), pp. 564-566 (1980).
  2. Office of Nuclear Reactor Regulation, NUREG-1313 (1988).
  3. A. Travelli, "The RERTR program: a status report", 21st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Sao Paulo, Brazil (1998).
  4. G. Hofman, M.K. Meyer, A.E. Ray, "Design of high density gamma-phase uranium alloys for LEU dispersion fuel applications", 21st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Sao Paulo, Brazil (1998).
  5. G.L. Hofman, L.A. Neimark, "Prospects for stable highdensity dispersion fuels", 10th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) Buenos Aires, Argentina (1987).
  6. G.L. Hofman, R.F. Domagala, G.L. Copeland, "Irradiation behavior of low-enriched U6Fe-Al dispersion fuel elements", J. Nucl. Mater., vol. 150, pp. 238-243 (1987). https://doi.org/10.1016/0022-3115(87)90079-1
  7. M.K. Meyer, G.L. Hofman, J.L. Snelgrove, C.R. Clark, S.L. Hayes, R.V. Strain, J.-M. Park, K.-H. Kim, "Irradiation behavior of Uranium-Molybdenum dispersion fuel : fuel performance data from RERTR-1 and RERTR-2", 22nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Budapest, Hungary (1999).
  8. M.K. Meyer, T.C. Wiencek, S.L. Hayes, G.L. Hofman, "Irradiation behavior of U6Mn-Al dispersion fuel elements", J. Nucl. Mater., vol. 278, pp. 358-363 (2000). https://doi.org/10.1016/S0022-3115(99)00280-9
  9. G.L. Hofman, M.K. Meyer, J.-M. Park, "Observations on the irradiation behavior of U-Mo alloy dispersion fuel", 23rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Las Vegas, Nevada (2000).
  10. M.K. Meyer, G.L. Hofman, S.L. Hayes, C.R. Clark, T.C. Wiencek, J.L. Snelgrove, R.V. Strain, K.-H. Kim, "Lowtemperature irradiation behavior of uranium-molybdenum alloy dispersion fuel", J. Nucl. Mater., vol. 304, pp. 221-236 (2002). https://doi.org/10.1016/S0022-3115(02)00850-4
  11. J.L. Snelgrove, G.L. Hofman, M.K. Meyer, C.L. Trybus, T.C. Wiencek, "Developement of very-high-density lowenriched uranium fuels.", Nucl. Eng. Des., vol. 178, pp. 119-126 (1997). https://doi.org/10.1016/S0029-5493(97)00217-3
  12. K.-H. Kim, J.-M. Park, C.-K. Kim, G.L. Hofman, M.K. Meyer, J.L. Snelgrove, "Stable in-reactor performances at low temperature of U-10 wt% Mo dispersion fuel containing centrifugally atomized powder", 22nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Budapest, Hungary (1999).
  13. G.L. Hofman, M.K. Meyer, "Progress in irradiation performance of experimental uranium-molybdenum dispersion fuel", 24th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), San Carlos de Bariloche, Argentina (2002).
  14. M.K. Meyer, G.L. Hofman, R.V. Strain, C.R. Clark, J.R. Stuart, "Metallographic analysis of irradiated RERTR-3 fuel test specimens", 23rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Las Vegas, Nevada (2000).
  15. K.H. Kim, J.M. Park, C.K. Kim, G.L. Hofman, M.K. Meyer, "Irradiation behavior of atomized U-10wt% Mo alloy aluminum matrix dispersion fuel meat at low temperature", Nucl. Eng. Des., vol. 211, pp. 229-235 (2002). https://doi.org/10.1016/S0029-5493(01)00459-9
  16. F. Huet, V. Marelle, J. Noirot, P. Sacristan, P. Lemoine, "Full-sized plates irradiation with high UMo fuel loading - Final results of IRIS 1 experiment.", 25th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Chicago, Illinois (2003).
  17. A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, M. Verwerft, "Post-irradiation examination of uranium-7wt% molybdenum atomized dispersion fuel.", 8th International Meeting on Research Reactor Fuel Management (RRFM), Munich, Germany (2004).
  18. P. Lemoine, J.L. Snelgrove, N. Arkhangelsky, L. Alvarez, "UMo dispersion fuel results and status of qualification programs", 8th International Meeting on Research Reactor Fuel Management (RRFM), Munich, Germany (2004).
  19. A.L. Izhutov, V.V. Alexandrov, N.G. Gataullin, A.Y. Novoselov, V.A. Starkov, G.V. Shevlyakov, A.A. Sheldyakov, V.Y. Shishin, I.V. Dobrikova, A.V. Vatulin, G.V. Kulakov, A.V. Morozov, "The irradiation test and preliminary PIE results of low enrichment U-Mo pin-type fuel", 27th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Boston, USA (2005).
  20. C.K. Kim, K.H. Kim, J.M. Park, D.S. Sohn, "Efforts to overcome the failure occuring in rod type U-Mo fuel irradiation test for Hanaro in Kaeri", 7th International Meeting on Research Reactor Fuel Management, Aix-en-Provence, France (2003).
  21. G.L. Hofman, Y.S. Kim, M.R. Finlay, J.L. Snelgrove, S.L. Hayes, M.K. Meyer, C.R. Clark, F. Huet, "Recent observations at the postirradiation examination of low-enriched UMo miniplates irradiated to high burnup", 25th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Chicago, Illinois (2003).
  22. G.L. Hofman, M.R. Finlay, Y.S. Kim, "Post-Irradiation Analysis of Low Enriched U-Mo/Al Dispersion Fuel Miniplate Tests, RERTR 4 & 5", 26th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Vienna, Austria (2004).
  23. A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, M. Verwerft, "Post-irradiation examination of uranium-7wt% molybdenum atomized dispersion fuel.", J. Nucl. Mater., vol. 335, pp. 39-47 (2004). https://doi.org/10.1016/j.jnucmat.2004.07.004
  24. S. Van den Berghe, W. Van Renterghem, A. Leenaers, "Transmission electron microscopy investigation of irradiated U-7wt%Mo dispersion fuel", J. Nucl. Mater., vol. 375, pp. 340-346 (2008). https://doi.org/10.1016/j.jnucmat.2007.12.006
  25. H.J. Ryu, Y.S. Kim, G. Hofman, J. Rest, J.M. Park, C.K. Kim, "Radiation induced recrystallization of UMo fuel particles and radiaion induced amorphisation of interaction products in UMo/Al dispersion fuel", Mater. Sci. Forum, vol. 558-559, pp. 319-322 (2007). https://doi.org/10.4028/www.scientific.net/MSF.558-559.319
  26. O.A. Golosov, V.B. Semerikov, S.G. Bogdanov, M.S. Lyutikova, "Small angle neutron scattering by U-9%Mo/Al dispersion fuel irradiated to high burnups", 29th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Prague, Czech Republic (2007).
  27. J. Gan, D.D. Keiser Jr, D.M. Wachs, A.B. Robinson, B.D. Miller, T.R. Allen, "TEM characterisation of irradiated RERTR dispersion fuel", 13th International Meeting on Research Reactor Fuel Management (RRFM), Vienna, Austria (2009).
  28. A. Leenaers, C. Detavernier, S. Van den Berghe, "The effect of silicon on the interaction between metallic uranium and aluminum: a 50 year long diffusion experiment.", J. Nucl. Mater., vol. 381, pp. 242-248 (2008). https://doi.org/10.1016/j.jnucmat.2008.08.018
  29. Y.S. Kim, G. Hofman, H.J. Ryu, J. Rest, "Thermodynamic and metallurgical considerations to stabilizing the interaction layers of U-Mo/Al dispersion fuel", 27th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Boston, USA (2005).
  30. G.L. Hofman, Y.S. Kim, H.J. Ryu, J. Rest, D.M. Wachs, M.R. Finlay, "Attempt to solve the instability in the irradiation behaviour of low enriched U-Mo/Al dispersion fuel", 10th International Meeting on Research Reactor Fuel Management (RRFM), Sofia, Bulgaria (2006).
  31. D.D. Keiser, A.B. Robinson, D.E. Janney, J.F. Jue, "Results of recent Microstructural Characterization of Irradiated UMo Dispersion Fuels with Al Alloy Matrices that contain Si", 12th International Meeting on Research Reactor Fuel Management (RRFM), Hamburg (Germany) (2008).
  32. J.L. Snelgrove, P. Lemoine, L. Alvarez, "High-density U-Mo fuels - latest results and reoriented qualification programs", 9th International Meeting on Research Reactor Fuel management (RRFM), Budapest, Hungary (2005).
  33. S. Dubois, J. Noirot, J.M. Gatt, M. Ripert, P. Lemoine, P. Boulcourt, "Comprehensive Overview of the IRIS Program: Irradiation Tests and PIE on High Density UMo/Al Dispersion Fuel", 11th International Meeting on Research Reactor Fuel Management (RRFM), Lyon, France (2007).
  34. M. Ripert, S. Dubois, P. Boulcourt, S. Naury, P. Lemoine, "IRIS3 experiment - Status and result of thickness increases", 10th International Meeting on Research Reactor Fuel Management (RRFM), Sofia, Bulgaria (2006).
  35. J.M. Hamy, P. Lemoine, F. Huet, C. Jarousse, J.L. Emin, "The French U-Mo group contribution to new LEU fuel development", 9th International Meeting on Research Reactor Fuel Management (RRFM), Budapest, Hungary (2005).
  36. W. Petry, A. Rohrmoser, P. Boulcourt, A.Chabre, S. Dubois, P. Lemoine, C. Jarousse, J. Falgoux, S.v.d. Berghe, A. Leenaers, "UMo full size plate irradiation experiment IRISTUM - a progress report", 12th International Meeting on Research Reactor Fuel Management (RRFM), Hamburg (Germany) (2008).
  37. A. Leenaers, S. Van den Berghe, M. Ripert, J. Noirot, P. Lemoine, A. Rohrmoser, W. Petry, "Irradiation Behavior of Atomized and Ground U(Mo) Dispersion Fuel", 30th International Meeting On Reduced Enrichment For Research And Test Reactors, Washington, D.C. USA (2008).
  38. A. Leenaers, S. Van den Berghe, F. Charollais, P. Lemoine, C. Jarousse, A. Rohrmoser, W. Petry, "Microstructural Analysis of Ground U(Mo) Fuel with and without Si in the Matrix, Irradiated to High Burn-Up", 31st International Meeting On Reduced Enrichment For Research And Test Reactors, Beijing, China (2009).
  39. A. Leenaers, S. Van den Berghe, F. Charollais, P. Lemoine, C. Jarousse, A. Rohrmoser, W. Petry, "EPMA of ground U(Mo) fuel with and without Si added to the matrix, irradiated to high burn up", 14th International Meeting on Research Reactor Fuel Management (RRFM), Marrakech, Morocco (2010).
  40. A. Leenaers, S. Van den Berghe, W. Van Renterghem, F. Charollais, P. Lemoine, C. Jarousse, A. Rohrmoser, W. Petry, "Irradiation Behaviour of Ground U(Mo) fuel with and without Si added to the matrix", J. Nucl. Mater., vol. 412, pp. 41-52 (2011). https://doi.org/10.1016/j.jnucmat.2011.02.002
  41. M. Ripert, V. Marelle, X. Iltis, H. Palancher, C. Valot, F. Charollais, M.C. Anselmet, X. Tiratay, P. Lemoine, S. Van den Berghe, A. Leenaers, C. Jarousse, "Synthetic review of the IRIS3 experiment", 15th International Meeting of Research Reactor Fuel Management (RRFM), Rome, Italy (2011).
  42. Y.S. Kim, G.L. Hofman, P.G. Medvedev, G.V. Shevlyakov, A.B. Robinson, H.J. Ryu, "Post-irradiation Analysis and Performance Modeling of Dispersion and Monolithic UMo Fuels", 29th International Meeting On Reduced Enrichment For Research And Test Reactors, Prague, Czech Republic (2007).
  43. G.L. Hofman, Y.S. Kim, H.J. Ryu, M.R. Finlay, D. Wachs, "Improved Irradiation Behavior of Uranium-Molybdenum /Aluminium Dispersion Fuel", 11th International Meeting on Research Reactor Fuel Management (RRFM), Lyon, France (2007).
  44. Y.S. Kim, G. Hofman, A.B. Robinson, "Effect of Si addition in Al in U-Mo/Al dispersion plates: observations from side-by-side irradiations from RERTR-6, -7A, -9A and -9B", 13th International Meeting of Research Reactor Fuel Management (RRFM), Vienna, Austria (2009).
  45. G.L. Hofman, Y.S. Kim, A.B. Robinson, "Method of Utilizing the Stabilizing Effect of Silicon in U-Mo/Al Dispersion Fuel and Minimum Si Addition Required for Given Operating Conditions", 31st International Meeting On Reduced Enrichment For Research And Test Reactors, Beijing, China (2009).
  46. J.M. Park, H.J. Ryu, S.J. Oh, D.B. Lee, C.K. Kim, Y.S. Kim, G.L. Hofman, "Effect of Si and Zr on the interdiffusion of U-Mo alloy and Al", J. Nucl. Mater., vol. 374 (3), pp. 422-430 (2008). https://doi.org/10.1016/j.jnucmat.2007.09.059
  47. J.M. Park, H.J. Ryu, J.H. Yang, Y.S. Lee, B.O. Yoo, Y.H. Jung, H.M. Kim, C.K. Kim, Y.S. Kim, G. Hofman, "KOMO-4 test PIE results", 32nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Lisbon, Portugal (2010).
  48. E. Koonen, H. Guyon, P. Lemoine, C. Jarousse, D.M. Wachs, J. Stevens, "The LEONIDAS and US partnership for UMo dispersion fuel qualification", 31st International Meeting On Reduced Enrichment For Research And Test Reactors, Beijing, China (2009).
  49. F. Frery, H. Guyon, E. Koonen, S. Van den Berghe, P. Lemoine, F. Charollais, C. Jarousse, D. Geslin, "LEONIDAS U(Mo) dispersion fuel qualification program : progress and prospects", 32nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Lisbon, Portugal (2010).
  50. F. Charollais, P. Lemoine, Y. Calzavara, H. Guyon, E. Koonen, S. Van den Berghe, B. Stepnik, C. Jarousse, D. Geslin, "LEONIDAS U(Mo) Dispersion Fuel Qualification Program: Progress and Perspectives", 33rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Santiago, Chile (2011).
  51. S. Van den Berghe, A. Leenaers, Y. Parthoens, "The EFUTURE experiment: Non-destructive PIE results", 33rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Santiago, Chili (2011).
  52. A. Leenaers, J. Van Eyken, S. Van den Berghe, E. Koonen, F. Charollais, P. Lemoine, Y. Calzavara, H. Guyon, C. Jarousse, B. Stepnik, D. Wachs, A. Robinson, "LEONIDAS E-FUTURE : Results of the Destructive Analyses of the U(Mo)-Al(Si) Fuel Plates", 16th International Meeting of Research Reactor Fuel Management (RRFM), Prague, Czech Republic (2012).
  53. S. Van den Berghe, Y. Parthoens, F. Charollais, Y.S. Kim, A. Leenaers, E. Koonen, V. Kuzminov, P. Lemoine, C. Jarousse, H. Guyon, D. Wachs, D. Keiser Jr, A. Robinson, J. Stevens, G. Hofman, "Swelling of U(Mo)-Al(Si) dispersion fuel under irradiation - Non-destructive analyses of the LEONIDAS E-FUTURE plates", J. Nucl. Mater., vol. 430 (1-3), pp. 246-258 (2012). https://doi.org/10.1016/j.jnucmat.2012.06.045
  54. H. Palancher, X. Iltis, A. Bonnin, F. Charollais, P. Lemoine, S. Van den Berghe, A. Leenaers, E. Koonen, B. Stepnik, C. Jarousse, Y. Calzavara, H. Guyon, "LEONIDAS EFUTURE- II: Characteristics of the fresh fuel plates", 16th International Meeting on Research Reactor Fuel Management (RRFM), Prague, Czech Republic (2012).
  55. B. Stepnik, M. Grasse, D. Geslin, C. Jarousse, F. Charollais, P. Lemoine, Y. Calzavara, H. Guyon, E. Koonen, S. Van den Berghe, "LEONIDAS UMo Dispersion Fuel Qualification Program: Progress And Perspectives; Highlight On The EFUTURE- II Fuel Plate Manufacturing", 16th International Meeting of Research Reactor Fuel Management (RRFM), Prague, Czech Republic (2012).
  56. A. Leenaers, S. Van den Berghe, C. Detavernier, "AlSi matrices for U(Mo) dispersion fuel plates", J. Nucl. Mater., vol. 439, pp. 7-18 (2013). https://doi.org/10.1016/j.jnucmat.2013.03.047
  57. M. Ripert, S. Dubois, J. Noirot, P. Boulcourt, P. Lemoine, S. Van den Berghe, A. Leenaers, A. Rohrmoser, W. Petry, C. Jarousse, "Overview on High Density UMo fuel in-pile experiments in OSIRIS", 12th International Meeting of Research Reactor Fuel Management (RRFM), Hamburg (Germany) (2008).
  58. F. Charollais, M. Ripert, M.C. Anselmet, P. Boulcourt, X. Tiratay, P. Lemoine, C. Jarousse, "IRIS program: IRIS-4 first results", 13th International Meeting on Research Reactor Fuel Management (RRFM), Vienna, Austria (2009).
  59. M. Ripert, F. Charollais, M.C. Anselmet, X. Tiratay, P. Lemoine, "Results of the IRIS4 irradiation in OSIRIS reactor: oxidised U-Mo particles dispersed in Al (with 0 or 2.1%Si)", 31st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Beijing, China (2009).
  60. S. Van den Berghe, A. Leenaers, C. Detavernier, "SELENIUM Fuel : Surface Engineering of U(Mo) Particles to Optimise Fuel Performance", 14th International Meeting of Research Reactor Fuel Management (RRFM), Marrakech, Marocco (2010).
  61. S. Van den Berghe, A. Leenaers, E. Koonen, L. Sannen, "From high to low enriched uranium fuel in research reactors", Adv. Sci. Techn., vol. 73, pp. 78-90 (2010). https://doi.org/10.4028/www.scientific.net/AST.73.78
  62. A. Leenaers, S. Van den Berghe, C. Detavernier, "Surface Engineering of Low Enriched Uranium-Molybdenum", J. Nucl. Mater., vol. 440, pp. 220-228 (2013). https://doi.org/10.1016/j.jnucmat.2013.04.068
  63. A.L. Izhutov, V.V. Alexandrov, N. A.E., V.A. Starkov, V.E. Fedoseev, V.V. Pimenov, A.V. Sheldyakov, V.Y. Shishin, V.V. Yakovlev, I.V. Dobrikova, A.V. Vatulin, V.B. Suprun, K. G.V., "The main results of investigation of modified dispersion LEU U-Mo fuel tested in the MIR reactor", 32nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Lisbon, Portugal (2010).
  64. Y.S. Lee, E.K. Park, W.H. Cho, J.S. Park, Y.H. Yang, Y.J. Jeong, H.J. Ryu, J.M. Park, C.K. Kim, "Si Coating on atomized U-Mo particles as as barrier of U-Mo/Al interdiffusion", 15th International Meeting on Research Reactor Fuel Management (RRFM), Rome, Italy (2011).
  65. H.J. Ryu, J.S. Park, J.M. Park, C.K. Kim, "The effect of Si-layer coating on U-Mo vs Al interdiffusion", Nuclear Engineering and Technology, vol. 43 (2), pp. 159-166 (2011). https://doi.org/10.5516/NET.2011.43.2.159
  66. H.J. Ryu, J.S. Park, J. Shim, Y. Lee, J.M. Park, C.K. Kim, "Fabrication of coated U-Mo powder and the effect of Si content on the interaction layer growth", 31st International Meeting On Reduced Enrichment For Research And Test Reactors (RERTR), Beijing, China (2009).
  67. H.J. Ryu, J.M. Park, K.H. Lee, B.O. Yoo, Y.H. Jung, Y.J. Jeong, Y.S. Lee, "Post-Irradiation Examination of the KOMO-5 Irradiation Test for U-Mo Dispersion Fuels", 17th International Meeting of Research Reactor Fuel Management (RRFM), St. Petersburgh, Russia (2013).
  68. N. Herlet, G. Ferlay, P. Dancausse, A. Juvenelle, "Reprocessing U-Mo spent fuels: dissolution experiments on non-irradiated and irradiated materials", 9th International Meeting on Research Reactor Fuel Management (RRFM), Budapest, Hungary (2005).
  69. B. Guigon, H. Vacelet, D. Dornbusch, "A new MTR fuel for a new MTR reactor: UMo for the Jules Horowitz reactor", 4th International Meeting of Research Reactor Fuel Management (RRFM), Colmar, France (2000).
  70. A.R. Kaufmann, in, U.S., 1963.
  71. C.R. Clark, M.K. Meyer, "Fuel powder production from ductile uranium alloys", International Meeting on Reduced Enrichment for Research and Test Reactors, Sao Paulo, Brazil (1998).
  72. C.-K. Kim, K.-H. Kim, C.-T. Lee, I.-H. Kuk, "Atomisation of U3Si2 for research reactor fuel", 14th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Jakarta, Indonesia (1991).
  73. C.-K. Kim, K.-H. Kim, Y.-S. Lee, S.-B. Park, G.L. Hofman, "An investigation on g-U phase stability and thermal compatibility of dispersion fuel meats prepared with atomized U-16 at% Mo, U-14 at% Mo-2 at% Ru and U-14 at% Mo-2 at% Os", 22nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Budapest, Hungary (1999).
  74. K.H. Kim, D.B. Lee, C.K. Kim, G.L. Hofman, K.W. Paik, "Thermal compatibility of centrifugally atomized U-Mo powders with aluminum in a dispersion fuel.", Nucl. Engin. Design, vol. 178, pp. 111-117 (1997). https://doi.org/10.1016/S0029-5493(97)00216-1
  75. K.H. Kim, D.B. Lee, C.K. Kim, G.L. Hofman, K.W. Paik, "Characterization of U-2 wt% Mo and U-10 wt% Mo alloy powders prepared by centrifugal atomization", J. Nucl. Mater., vol. 245, pp. 179-184 (1997). https://doi.org/10.1016/S0022-3115(97)00011-1
  76. S.-J. Jang, C.-K. Kim, K.-H. Kim, E.-S. Kim, I.-H. Kuk, D.-S. Sohn, Dispersion fuel with spherical uranium alloy, and the fuel fabrication process, in, U.S., 1998.
  77. C. Jarousse, J.P. Durand, Y. Lavastre, M. Grasse, "CERCA UMo development status as of March 2003", 7th International Meeting on Research Reactor Fuel Management (RRFM), Aix-en-Provence, France (2003).
  78. J.P. Durand, B. Maugard, A. Gay, "Technical ability of new MTR high density fuel alloys regarding the whole fuel cycle", 2nd International Meeting on Research Reactor Fuel Management (RRFM), Bruges, Belgium (1998).
  79. A. Languille, J.P. Durand, A. Gay, "New high density MTR fuel; the CEA-CERCA-COGEMA development program", 3rd International Meeting on Research Reactor Fuel Management (RRFM), Bruges, Belgium (1999).
  80. S. Van den Berghe, W. Van Renterghem, A. Leenaers, "Transmission Electron Microscopy investigation of irradiated U-7%Mo dispersion fuel", 29th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Prague, Czech Republic (2007).
  81. J. Gan, D.D. Keiser Jr, D.M. Wachs, A.B. Robinson, B.D. Miller, T.R. Allen, "Transmission electron microscopy characterization of irradiated U-7Mo/Al-2Si dispersion fuel", J. Nucl. Mater., vol. 396 (2-3), pp. 234 (2010). https://doi.org/10.1016/j.jnucmat.2009.11.015
  82. J. Gan, D.D. Keiser Jr, B.D. Miller, A.B. Robinson, J.F. Jue, P. Medvedev, D.M. Wachs, "TEM characterization of U-7Mo/Al-2Si dispersion fuel irradiated to intermediate and high fission densities", J. Nucl. Mater., vol. 424 (1-3), pp. 43-50 (2012). https://doi.org/10.1016/j.jnucmat.2012.02.001
  83. W. Van Renterghem, A. Leenaers, S. Van den Berghe, "TEM Investigation of Irradiated Atomised and Ground U(Mo) Dispersion Fuel, with or without Si added to the Matrix", 31st International Meeting On Reduced Enrichment For Research And Test Reactors, Beijing, China (2009).
  84. A. Leenaers, S. Van den Berghe, S. Dubois, J. Noirot, M. Ripert, P. Lemoine, "Microstructural Analysis of Irradiated Atomized U(Mo) Dispersion Fuel in an Al Matrix with Si addition", 12th International Meeting on Research Reactor Fuel Management (RRFM), Hamburg (Germany) (2008).
  85. Y.S. Kim, G.L. Hofman, "Fission product induced swelling of U-Mo alloy fuel", J. Nucl. Mater., vol. 419 (1-3), pp. 291-301 (2011). https://doi.org/10.1016/j.jnucmat.2011.08.018
  86. K.T. Conlon, D.F. Sears, "Neutron Powder Diffraction of Irradiated Low-Enriched Uranium-Molybdenum Dispersion Fuel", 10th International Meeting on Research Reactor Fuel Management (RRFM), Sofia, Bulgaria (2006).
  87. W. Van Renterghem, A. Leenaers, S. Van den Berghe, "Transmission Electron Microscopy Investigation of UAlx Based MTR Fuel", 14th International Meeting on Research Reactor Fuel Management (RRFM), Marrakech, Marocco (2010).
  88. J. Gan, B. Miller, D. Keiser Jr, A. Robinson, P. Medvedev, D. Wachs, "TEM Characterization of Irradiated U3Si2/Al Dispersion Fuel", 32nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Lisbon, Portugal (2010).
  89. R.C. Birtcher, J.W. Richardson, M.H. Mueller, "Amorphization of U3Si2 by ion or neutron irradiation", J. Nucl. Mater., vol. 230 (2), pp. 158 (1996). https://doi.org/10.1016/0022-3115(96)00160-2
  90. M. Ugajin, M. Akabori, A. Itoh, N. Ooka, Y. Nakakura, "Behavior of neutron-irradiated U3Si", J. Nucl. Mater., vol. 248, pp. 204-208 (1997). https://doi.org/10.1016/S0022-3115(97)00199-2
  91. A. Leenaers, E. Koonen, Y. Parthoens, P. Lemoine, S. Van den Berghe, "Post-irradiation examination of AlFeNi cladded U3Si2 fuel plates irradiated under severe conditions", J. Nucl. Mater., vol. 375, pp. 243-251 (2008). https://doi.org/10.1016/j.jnucmat.2008.01.013
  92. A. Leenaers, S. Van den Berghe, E. Koonen, P. Jacquet, C. Jarousse, B. Guigon, A. Ballagny, L. Sannen, "Microstructure of U3Si2 fuel plates submitted to a high heat flux", J. Nucl. Mater., vol. 327, pp. 121-129 (2004). https://doi.org/10.1016/j.jnucmat.2004.01.025
  93. A. Leenaers, S. Van den Berghe, "Microstructure Of 50 Year Old SCK•CEN BR1 Research Reactor Fuel", 29th International Meeting On Reduced Enrichment For Research And Test Reactors (RERTR), Prague, Czech Republic (2007).
  94. Oak Ridge National Lab, AECD-3901 (1956).
  95. J.E. Cunningham, R.E. Adams, "Techniques for canning an bonding metallic uranium with aluminum", Fuel Elements Conference, Paris, France (1957).
  96. D.D. Keiser, A.B. Robinson, J.F. Jue, P. Medvedev, D.M. Wachs, M.R. Finlay, "Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel", J. Nucl. Mater., vol. 393 (2), pp. 311-320 (2009). https://doi.org/10.1016/j.jnucmat.2009.06.018
  97. M.I. Mirandou, S. Arico, L. Gribaudo, S. Balart, "Out of pile diffusion studies between U-7wt%Mo and Al-Si alloys", 27th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) Boston, USA (2005).
  98. M. Mirandou, S. Arico, A.M. Fortis, S. Balart, "Out and in pile diffusion experiments between U-Mo alloys and Al- Si alloys : work status", 10th International Meeting on Research Reactor Fuel Management (RRFM), Sofia, Bulgaria (2006).
  99. S. Dubois, F. Mazaudier, J.P. Piron, P. Martin, J.C. Dumas, F. Huet, H. Noel, O. Tougait, C. Jarousse, P. Lemoine, "Out of pile French research program on the UMo/Al system: first results", 9th International Meeting on Research Reactor Fuel Management (RRFM), Budapest, Hungary (2005).
  100. E. Perez, B. Yao, Y.H. Sohn, D.D. Keiser, "Interdiffusion in Diffusion Couples: U-Mo vs. Al and Al-Si", 31st International Meeting On Reduced Enrichment For Research And Test Reactors, Beijing, China (2009).
  101. H.J. Ryu, Y.S. Kim, G.L. Hofman, J.M. Park, C.K. Kim, "Heats of formation of (U,Mo)Al3 and U(Al,Si)3", J. Nucl. Mater., vol. 358, pp. 52-56 (2006). https://doi.org/10.1016/j.jnucmat.2006.06.013
  102. A. Leenaers, S. Van den Berghe, C. Detavernier, "Determination of activation energies of the U(Mo)/Si and U(Mo)/Al solid state reaction using in-situ X-ray diffraction and Kissinger analysis", Solid State Science, vol. 14, pp. 1133-1140 (2012). https://doi.org/10.1016/j.solidstatesciences.2012.04.031
  103. R. Jungwirth, H. Breitkreutz, W. Petry, A. Rohrmoser, W. Schmid, H. Palancher, C. Bertrand-Drira, C. Sabathier, X. Iltis, N. Tarisien, C. Jarousse, "Optimization of the Si Content in UMo/Al(Si) fuel plates", 31st International Meeting On Reduced Enrichment For Research And Test Reactors (RERTR), Beijing, China (2009).
  104. J. Allenou, H. Palancher, X. Iltis, M. Cornen, O. Tougait, R. Tucoulou, E. Welcomme, P. Martin, C. Valot, F. Charollais, M.C. Anselmet, P. Lemoine, "U-Mo/Al-Si interaction : Influence of Si concentration", J. Nucl. Mater., vol. 399, pp. 189-199 (2010). https://doi.org/10.1016/j.jnucmat.2010.01.018
  105. X. Iltis, F. Charollais, M.C. Anselmet, P. Lemoine, A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, D. Geslin, F. Frery, H. Guyon, "Microstructural Characterization of the E-Future Fresh Fuel Plates", 32nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Lisbon, Portugal (2010).
  106. D. Keiser Jr, J.F. Jue, N. Woolstenhulme, A. Ewh, "Potential annealing treatments for tailoring the starting microstructure of low-enriched U-Mo dispersion fuels to optimize performance during irradiation", J. Nucl. Mater., vol. 419, pp. 226-234 (2011). https://doi.org/10.1016/j.jnucmat.2011.08.039
  107. H. Palancher, A. Bonnin, V. Honkimaki, T. Buslaps, M. Grasse, B. Stepnik, T. Zweifel, "Quantitative crystallographic ananlysis of as-fabricated full size U-Mo/Al(Si) nuclear fuel plates", J. Alloys Compd., vol. 527, pp. 53-65 (2012). https://doi.org/10.1016/j.jallcom.2012.02.010
  108. A. Leenaers, S. Van den Berghe, J. Van Eyken, E. Koonen, F. Charollais, P. Lemoine, Y. Calzavara, H. Guyon, C. Jarousse, D. Geslin, D. Wachs, D. Keiser Jr, A. Robinson, G. Hofman, Y.S. Kim, "Microstructural evolution of U(Mo)- Al(Si) dispersion fuel under irradiation - Destructive analyses of the LEONIDAS E-FUTURE plates", J. Nucl. Mater., vol. 441, pp. 439-448 (2013). https://doi.org/10.1016/j.jnucmat.2013.06.027
  109. G.L. Hofman, M.K. Meyer, J.L. Snelgrove, M.L. Dietz, R.V. Strain, K.-H. Kim, "Initial assessment of radiation behaviour of very-high-density low-enriched-uranium fuels", 22nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Budapest, Hungary (1999).
  110. Y.S. Kim, G. Hofman, J.S. Cheon, "Recrystallization and fission gas bubble swelling of U-Mo fuel", J. Nucl. Mater., vol. 436, pp. 14-22 (2013). https://doi.org/10.1016/j.jnucmat.2013.01.291
  111. Y.S. Kim, G. Hofman, J.S. Cheon, "Recrystallisation and swelling of U-Mo fuel during irradiation", 16th International Meeting on Research Reactor Fuel Management (RRFM), Prague, Czech Republic (2012).
  112. A.L. Izhutov, V.V. Iakovlev, V.M. Kosenkov, A.Y. Novoselov, V.A. Starkov, A.A. Sheldyakov, V.Y. Shishin, I.V. Dobrikova, G.V. Kulakov, A.V. Vatulin, V.B. Suprun, "Structural Changes In The Dispersed U-Mo Fuel Irradiated In The Mir Reactor", 15th International Meeting on Research Reactor Fuel Management (RRFM), Rome (Italy) (2011).
  113. G.L. Hofman, Y.S. Kim, "A Classification of Uniquely Different Types of Nuclear Fission Gas Behaviour", Nucl. Eng. Techn., vol. 37 (4), pp. 299-308 (2005).
  114. V.V. Rondinella, T. Wiss, "The high burn-up structure in nuclear fuel - Review article", Mater. Today, vol. 13 (12), pp. 24-32 (2010).
  115. K. Nogita, K. Une, "Irradiation-induced recrystallization in high burnup UO2 fuel", J. Nucl. Mater., vol. 226 (3), pp. 302-310 (1995). https://doi.org/10.1016/0022-3115(95)00123-9
  116. J. Rest, G. Hofman, "Irradiation-induced Recrystallisation of Cellular Dislocation Networks in Uranium-Molybdenum Alloys", Mat. Res. Soc. Symp. Proc., vol. 650, pp. R1.7.1-R1.7.6 (2001).
  117. S. Van den Berghe, Y. Parthoens, G. Cornelis, A. Leenaers, E. Koonen, V. Kuzminov, C. Detavernier, "Swelling of U(Mo) dispersion fuel under irradiation - Non-destructive analyses of the SELENIUM plates", J. Nucl. Mater., vol. 442, pp. 60-68 (2013). https://doi.org/10.1016/j.jnucmat.2013.08.020
  118. A. Leenaers, S. Van den Berghe, C. Detavernier, "Out-of-pile study on the influence of Si present as coating layer or matrix element on the U(Mo)-Al interaction", 15th International Meeting on Research Reactor Fuel Management (RRFM), Rome, Italy (2011).
  119. C. Jarousse, G. Bourdat, M. Ripert, P. Boulcourt, P. Lemoine, "Latest Dispersed UMo Fuel Plate Manufacturing Results at AREVA-CERCA", 12th International Meeting on Research Reactor Fuel Management (RRFM), Hamburg, Germany (2008).
  120. S. Van den Berghe, A. Leenaers, C. Detavernier, "The SELENIUM Fuel Experiment - Progress Report After 2 Cycles", 34th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Warsaw, Poland (2012).
  121. S. Van den Berghe, A. Leenaers, C. Detavernier, "Coated Particle Production in the SELENIUM Project", 15th International Meeting on Research Reactor Fuel Management (RRFM), Rome, Italy (2011).
  122. A. Leenaers, S. Van den Berghe, C. Detavernier, "Microstructural evolution of Si and ZrN coated UMo fuel : destructive results of the SELENIUM irradiation", J. Nucl. Mater., in preparation (2014).

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