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Fuels for Advanced Nuclear Energy Systems

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Abstract

Fuels for advanced nuclear reactors differ from conventional light water reactor fuels and also vary widely because of the specific architectures and intended missions of the reactor systems proposed to deploy them. Functional requirements of all fuel designs for advanced nuclear energy systems include (1) retention of fission products and fuel nuclides, (2) dimensional stability, and (3) maintenance of a geometry that can be cooled. In all cases, anticipated fuel performance is the limiting factor in reactor system design, and cumulative effects of increased utilization and increased exposure to inservice environments degrade fuel performance. In this article, the current status of each fuel system is reviewed, and technical challenges confronting the implementation of each fuel in the context of the entire advanced reactor fuel cycle (fabrication, reactor performance, recycle) are discussed.

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References

  1. M. Konomura, M. Ichimiya, J. Nucl. Mater. 371, 250 (2007).

    Google Scholar 

  2. B.W. Spencer, R.N. Hill, D.C. Wade, D.J. Hill, J.J. Sienicki, H.S. Khalil, J.E. Cahalan, M.T. Farmer, V.A. Maroni, L. Leibowitz, “An Advanced Modular HLMC Reactor Concept Featuring Economy, Safety and Proliferation Resistance,” in Proceedings of the 8th International Conference on Nuclear Engineering (ICONE’00) (ASME, New York, 2000), p. 8145.

    Google Scholar 

  3. T.R. Allen, D.C. Crawford, Sci. Technol. Nucl. Installations 2007, 97486 (2007).

    Google Scholar 

  4. D.C. Crawford, M.K. Meyer, S.L. Hayes, J.J. Laidler, “Requirements and Long-Term Development Plan for Fast-Spectrum Transmutation Fuels in the U.S.,” in Proceedings of the Seventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, (OECD-NEA, Jeju, Korea, 14–16 October 2002), p. 465.

    Google Scholar 

  5. K. Verfondern, H. Nabielek, J.M. Kendall, Nucl. Eng. Technol. 39 (5), 603 (2007).

    Google Scholar 

  6. “Fuel Performance and Fission Product Behaviour in Gas Cooled Reactors” (IAEA-TEC-DOC-978, IAEA, Vienna, Austria, November 1997).

  7. R. Gontard, H. Nabielek, “Performance Evaluation of Modern HTR TRISO Fuels” (Tech. Rep. HTA-IB-05/90, Forschungszentrum Jülich GmbH, Jülich, Germany, 1990).

    Google Scholar 

  8. D.A. Petti, J. Buongiorno, J.T. Maki, R.R. Hobbins, G.K. Miller, Nucl. Eng. Des. 222, 281 (2003).

    Google Scholar 

  9. D.A. Petti, S.B. Glover, J.T. Maki, “Status of the First Advanced Gas Reactor Fuel Irradiation Experiment in the Advanced Test Reactor,” paper presented at 4th International Topical Meeting on High Temperature Reactor Technology, HTR2008, Washington, D.C., 28 September–1 October 2008.

  10. J.H. Kittel, B.R.T. Frost, J.P. Mustellier, K.Q. Bagley, G.C. Crittenden, J.V. Dievoet, J. Nucl. Mater. 204, 1 (1993).

    Google Scholar 

  11. D.C. Crawford, D.L. Porter, S.L. Hayes, J. Nucl. Mater. 371, 202 (2007).

    Google Scholar 

  12. A. Boltax, in Fuel Pin Mechanical Behavior: Ten Years of LMR Experience (American Nuclear Society, La Grange Park, IL, 11–15 November 1990) pp. 217–222.

    Google Scholar 

  13. G.L. Hofman, L.C. Walters, T.H. Bauer, Prog. Nucl. Energy 31, 83 (1997).

    Google Scholar 

  14. H. Matzke, Ed., Science of Advanced LMFBR Fuels (Elsevier, New York, 1986), chap. 10.

  15. B. Raj, H.S. Kamath, R. Natarajan, P.R. Vasudeva Rao, Prog. Nucl. Energy 47, 369 (2005).

    Google Scholar 

  16. N. Chauvin, J.Y. Malo, J.C. Garnier, F. Bertrand, J.C. Bosq, A. Ravenet, D. Lorenzo, M. Pelletier, J.M. Escleine, I. Munoz, J.M. Bonnerot, “GFR Fuel and Core Pre-Conceptual Design Studies,” paper presented at GLOBAL’07 Conference on Advanced Nuclear Fuel Cycles and Systems, Boise, ID, 9–13 September 2007.

  17. C. Sauder, J. Lamon, J. Am. Ceram. Soc. 90 (4) 1146 (2007).

    Google Scholar 

  18. T. Mizuno, D.C. Crawford, M. Fromont, J.W. Lee, T. Abram, J.-F. Babelot, “Status of the Advanced Fuel Project for Sodium-Cooled Fast Reactor as a Generation IV Nuclear Energy System,” paper presented at GLOBAL 2005, Tsukuba, Japan, 9–13 October 2005.

  19. T. Kato, K. Uozumi, T. Inoue, O. Shirai, T. Iwai, Y. Arai, “Recovery of Plutonium and Uranium into Liquid Cadmium Cathodes at High Current Densities,” paper presented at GLOBAL 2003, New Orleans, LA, 16–20 November 2003.

  20. M. Inoue, T. Iwai, Y. Arai, T. Asaga, “Irradiation Performance of. Uranium-Plutonium Mixed Nitride Fuel Pins in JOYO,” paper presented at GLOBAL 2003, New Orleans, LA, 16–20, November 2003.

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Petti, D., Crawford, D. & Chauvin, N. Fuels for Advanced Nuclear Energy Systems. MRS Bulletin 34, 40–45 (2009). https://doi.org/10.1557/mrs2009.11

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  • DOI: https://doi.org/10.1557/mrs2009.11

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