Advertisement

The Integral Fast Reactor

  • Charles E. Till
  • Yoon I. Chang
Chapter
Part of the Advances in Nuclear Science and Technology book series (ANST, volume 20)

Abstract

The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) an integral fuel cycle, based on pyrometallurgical processing and injection-cast fuel fabrication, with the fuel cycle facility collocated with the reactor, if so desired.

Keywords

Steam Generator Oxide Fuel Fuel Cycle Reactor Plant Liquid Metal Cool 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    J. E. Cahalan, R. H. Sevy, and S. F. Su, “Accommodation of Unprotected Accidents by Inherent Safety Design Features in Metallic and Oxide-Fuelled LMFBRs,” Proc. International Topical Meeting on Fast Reactor Safety, Knoxville, Tennessee, CONF-850410, Vol. 1, p. 29 (1985).Google Scholar
  2. 2.
    J. F. Marchaterre, R. H. Sevy, and J. C. Cahalan, “Integral Fast Reactor Concept Inherent Safety Features,” Proc. ASME Winter Meeting, 86-WA/NE-14, Anaheim, California (December 7–12, 1986).Google Scholar
  3. 3.
    L. C. Walters, B. R. Scidel, and J. H. Kittel, “Performance of Metallic Fuels and Blankets in Liquid Metal Fast Breeder Reactors,” Nucl. Tech., 65, 179 (1984).Google Scholar
  4. 4.
    B. R. Scidel, D. L. Porter, L. C. Walters, and G. L. Hofman, “Experience with EBR-II Driver Fuel,” Proc. International Conf. on Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona (September 7–11, 1986).Google Scholar
  5. 5.
    B. R. Scidel, G. L. Batte, C. E. Lahm, R. M. Fryer, J. F. Koenig, and G. L. Hofman, “Off-Normal Performance of EBR-II Driver Fuel,” Proc. International Conf. on Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona (September 7–11, 1986).Google Scholar
  6. 6.
    L. Burris, M. Steindler, and W. Miller, “A Proposed Pyrometallurgical Process for Rapid Recycle of Discharged Fuel Materials from the Integral Fast Reactor,” Proc. ANS International Topical Meeting on Fuel Reprocessing and Waste Management, Jackson, Wyoming (August 26–29, 1984).Google Scholar
  7. 7.
    L. Burris, “Rekindled Interest in Pyrometallurgical Processing,” Chemical Engineering Progress (February 1986).Google Scholar
  8. 8.
    L. Burris, R. K. Steunenberg, and W. E. Miller, “The Application of Electrorefining for Recovery and Purification of Fuel Discharged from the Integral Fast Reactor,” Proc. Annual AIChE Meeting, Miami, Florida (November 2–7, 1986).Google Scholar
  9. 9.
    J. F. Marehaterre, J. E. Cahalan, R. H. Sevy, and A. E. Wright, “Safety Characteristics of the Integral Fast Reactor Concept,” Proc. ASME Winter Meeting, 85-WA/NE-14, Miami Beach, Florida (November 1985).Google Scholar
  10. 10.
    G. H. Golden, H. P. Planchon, Jr., J. I. Sackett, and R. M. Singer, “Evolution of Thermal-Hydraulics Testing in EBR-II,” Nuclear Engineering and Design, Vol. 101, No. 1, pp. 3–12 (1987).CrossRefGoogle Scholar
  11. 11.
    N. C. Messick, P. R. Betten, W. F. Booty, L. J. Christensen, R. M. Fryer, D. Mohr, H. P. Planchon and W. H. Radtke, “Modification of EBR-II Plant to Conduct Loss-of-Flow-Without-Seram Tests,” Nuclear Engineering and Design, Vol. 101, No. 1, pp. 13–23 (1987).CrossRefGoogle Scholar
  12. 12.
    C. E. Lahm, J. F. Koenig, P. R. Betten, J. H. Böttcher, W. K. Lehto, and B. R. Scidel, “EBR-II Driver Fuel Qualification for Loss-of-Flow and Loss of Heat-Sink Tests Without Scram,” Nuclear Engineering and Design, Vol. 101, No. 1, pp. 25–34 (1987).CrossRefGoogle Scholar
  13. 13.
    W. K. Lehto, R. M. Fryer, E. M. Dean, J. F. Koenig, L. K. Chang, D. Mohr, and E. E. Feldman, “Safety Analysis for the Loss-of-Flow and Loss-of-Heat Sink without Scram Tests in EBR-II,” Nuclear Engineering and Design, Vol. 101, No. 1, pp. 35–44 (1987).CrossRefGoogle Scholar
  14. 14.
    D. Mohr, L. K. Chang, E. E. Feldman, P. R. Betten, and H. P. Planchon, “Loss-of-Primary-Flow-Without-Scram Tests: Pretest Predictions and Preliminary Results,” Nuclear Engineering and Design, Vol. 101, No. 1, pp. 45–56 (1987).CrossRefGoogle Scholar
  15. 15.
    E. E. Feldman, D. Mohr, L. K. Chang, H. P. Planchon, E. M. Dean, and P. R. Betten, “EBR-II Unprotected Loss-of-Heat-Sink Predictions and Preliminary Test Results,” Nuclear Engineering and Design, Vol. 101, pp. 57–66 (1987).CrossRefGoogle Scholar
  16. 16.
    L. K. Chang, J.F. Koenig, and D. L. Porter, “Whole-core Damage Analysis of EBR-II Driver Fuel Elements Following SHRT Program,” Nuclear Engineering Design, Vol. 101, No. 1, pp. 67–74 (1987).CrossRefGoogle Scholar
  17. 17.
    H. P. Planchon, J. I. Sackett, G. H. Golden, and R. H. Sevy, “Implications of the EBR-II Inherent Safety Demonstration Tests,” Nuclear Engineering and Design, Vol. KM, No. 1, p. 75–90 (1987).CrossRefGoogle Scholar
  18. 18.
    “Nuclear Energy Cost Data Base: A Reference Data Base for Nuclear and Coal-fired Powerplant Power Generation Cost Analysis,” DOE/NE-0044/3 (June 1985).Google Scholar
  19. 19.
    F. E. Tippets, S. M. Davies, L. N. Salerno, and C. R. Snyder, “PRISM: A Passively Safe, Economic, and Testable Advanced Power Reactor,” Proc. American Power Conference, 48, 694 (1986).Google Scholar
  20. 20.
    J. E. Brunings, E. Guenther, and R. R. Hren, “Sodium Advanced Fast Reactor (SAFR) for Safe Economic Power,” Proc. American Power Conference, 48, 683 (1986).Google Scholar
  21. 21.
    Ting-Shu Wu and R. W. Scidensticker, “Sensitivity Studies of a Scismically Isolated System to Low Frequency Amplification,” Proc. ASME Meeting, San Diego, California (June 1987).Google Scholar
  22. 22.
    R. W. Scidensticker and Ting-Shu Wu, “Licensing Considerations for Application of Scismic Isolation Systems in Nuclear Facilities,” Proc. 9th International Conference on Structural Mechanics in Reactor Technology, Lausanne, Switzerland (August 17–21, 1987).Google Scholar
  23. 23.
    Ting-Shu Wu, B. J. Hsieh, and R. W. Scidensticker, “Comparative Studies of Isolation Systems Applied to a Compact LMR Reactor Module,” Proc. 9th International Conference on Structural Mechanics in Reactor Technology, Lausanne, Switzerland (August 17–21, 1987).Google Scholar

Copyright information

© Plenum Press, New York 1988

Authors and Affiliations

  • Charles E. Till
    • 1
  • Yoon I. Chang
    • 1
  1. 1.Argonne National LaboratoryArgonneUSA

Personalised recommendations