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TERRAPOWER, LLC TRAVELING WAVE REACTOR DEVELOPMENT PROGRAM OVERVIEW

  • Received : 2013.09.23
  • Accepted : 2013.10.02
  • Published : 2013.11.25

Abstract

Energy security is a topic of high importance to many countries throughout the world. Countries with access to vast energy supplies enjoy all of the economic and political benefits that come with controlling a highly sought after commodity. Given the desire to diversify away from fossil fuels due to rising environmental and economic concerns, there are limited technology options available for baseload electricity generation. Further complicating this issue is the desire for energy sources to be sustainable and globally scalable in addition to being economic and environmentally benign. Nuclear energy in its current form meets many but not all of these attributes. In order to address these limitations, TerraPower, LLC has developed the Traveling Wave Reactor (TWR) which is a near-term deployable and truly sustainable energy solution that is globally scalable for the indefinite future. The fast neutron spectrum allows up to a ~30-fold gain in fuel utilization efficiency when compared to conventional light water reactors utilizing enriched fuel. When compared to other fast reactors, TWRs represent the lowest cost alternative to enjoy the energy security benefits of an advanced nuclear fuel cycle without the associated proliferation concerns of chemical reprocessing. On a country level, this represents a significant savings in the energy generation infrastructure for several reasons 1) no reprocessing plants need to be built, 2) a reduced number of enrichment plants need to be built, 3) reduced waste production results in a lower repository capacity requirement and reduced waste transportation costs and 4) less uranium ore needs to be mined or purchased since natural or depleted uranium can be used directly as fuel. With advanced technological development and added cost, TWRs are also capable of reusing both their own used fuel and used fuel from LWRs, thereby eliminating the need for enrichment in the longer term and reducing the overall societal waste burden. This paper describes the origins and current status of the TWR development program at TerraPower, LLC. Some of the areas covered include the key TWR design challenges and brief descriptions of TWR-Prototype (TWR-P) reactor. Selected information on the TWR-P core designs are also provided in the areas of neutronic, thermal hydraulic and fuel performance. The TWR-P plant design is also described in such areas as; system design descriptions, mechanical design, and safety performance.

Keywords

References

  1. T. ELLIS, R. Petroski et. al., "Traveling-Wave Reactors: A Truly Sustainable and Full-Scale Resource for Global Energy Needs," Proceedings of ICAPP '10, Paper 10189, San Diego, CA (2010).
  2. R. PETROSKI, L. Wood, "Sustainable, Full-Scope Nuclear Fission Energy at Planetary Scale," Sustainability, Vol. 4 Issue 11, p. 3088-3123, 2012 https://doi.org/10.3390/su4113088
  3. S. M. FEINBERG, "Discussion Comment," Rec. of Proc. Session B-10, ICPUAE, No. 2, Vol. 9, p. 447, United Nations, Geneva, Switzerland, (1958).
  4. G. J. FISCHER, et al., "Physics and Feasibility Study of the Fast-Mixed-Spectrum Reactor Concept," BNL-25598, (Jan. 1, 1979).
  5. W. T. LOH, M. J. Driscoll, D. D. Lanning, "An Evaluation of the Fast Mixed Spectrum Reactor," MITNE-232, (Feb. 1980).
  6. G. I. TOSHINSKY, "LMFBR Operation in the Nuclear Cycle without Fuel Reprocessing," Proceedings of the International Topical Meeting on Advanced Reactors Safety, 39-44 vol.1, Orlando, FL, USA, (1-5 June 1997).
  7. V. G. TOSHINSKY, H. Sekimoto, G. I. Toshinsky, "A Method to Improve Multiobjective Genetic Algorithm Optimization of a Self-Fuel-Providing LMFBR by Niche Induction Among Non-dominated Solutions," Annals of Nuclear Energy 27, 397-410, (2000). https://doi.org/10.1016/S0306-4549(99)00065-1
  8. P. YARSKY, M. J. Driscoll, P. Hejzlar, "Integrated Design of a Breed and Burn Gas-Cooled Fast Reactor Core," MIT -ANP-TR-107, (Sept. 2005).
  9. E. TELLER, M. Ishikawa, L. Wood, "Completely Automated Nuclear Power Reactors for Long-Term Operation," Proc. Of the Frontiers in Physics Symposium, American Physical Society and the American Association of Physics Teachers Texas Meeting, Lubbock, Texas, United States, 1995.
  10. H. SEKIMOTO, K. Ryu, Y. Yoshimura, "CANDLE: The New Burnup Strategy," Nuclear Science and Engineering 139, 306-317, (2001). https://doi.org/10.13182/NSE01-01
  11. M. YAN, H. Sekimoto, "Study on Small Long-Life LBE Cooled Fast Reactor with CANDLE Burn-up - Part 1: Steady State Research," Progress in Nuclear Energy 50, 286-289, (2008). https://doi.org/10.1016/j.pnucene.2007.11.005
  12. K. RYU, H. Sekimoto, "A Possibility of Highly Efficient Uranium Utilization with a Pebble Bed Fast Reactor," Annals of Nuclear Energy 27, 1139-1145, (2000). https://doi.org/10.1016/S0306-4549(99)00116-4
  13. R. W. SCHLEICHER, et al., "Improved Utilization of U.S. Nuclear Energy Resources Without Reprocessing," Transactions of the American Nuclear Society vol.101, 257, Washington DC, USA, (Nov. 15-19, 2009).
  14. H. VAN DAM, "The Self-stabilizing Criticality Wave Reactor," Proc. of the Tenth International Conference on Emerging Nuclear Energy Systems (ICENES 2000), p. 188, NRG, Petten, Netherlands (2000).
  15. X. N. CHEN, W. Maschek, "Transverse Buckling Effects on Solitary Burn-up Waves," Annals of Nuclear Energy 32, 1377-1390, (2005). https://doi.org/10.1016/j.anucene.2005.01.012
  16. S. P. FOMIN, et al., "Initiation and Propagation of Nuclear Burning Wave in Fast Reactor", Progress in Nuclear Energy 50, 163-169, (2008). https://doi.org/10.1016/j.pnucene.2007.10.020
  17. J. GILLELAND, C. Ahlfeld, D. Dadiomov, R. Hyde, Y. Ishikawa, D. McAlees, J. McWhirter, N. Myhrvold, J. Nuckolls, A. Odedra, K. Weaver, C. Whitmer, L. Wood and G. Zimmerman, "Novel Reactor Designs to Burn Non- Fissile Fuel," Proc. of the 2008 International Congress on Advances in Nuclear Power Plants (ICAPP 2008), ANS, Anaheim, Calif., United States, Paper 8319, (2008).
  18. K. WEAVER, C. Ahlfeld, J. Gilleland, C. Whitmer, G. Zimmerman, "Extending the Nuclear Fuel Cycle with Traveling-Wave Reactors," roceedings of Global 2009, Paper 9294, Paris, France, (Sept. 6-11, 2009).
  19. C. AHLFELD, P. Hejzlar, K. Weaver, R. Petroski, J. McWhirter, A. Odedra, T. Burke, T. Weaver, "Cost and Safety Features of 500 MWe to 1150 MWe Traveling Wave Reactor Plants," 2009 American Nuclear Society Winter Meeting, (2009).
  20. C. AHLFELD, T. Burke, T. Ellis, P. Hejzlar, K. Weaver, C. Whitmer, J. Gilleland, M. Cohen, B. Johnson, S. Mazurkiewicz, J. McWhirter, A. Odedra, N. Touran, C. Davidson, J. Walter, R. Petroski, G. Zimmerman, T. Weaver, P. Schweiger, R. Russick, "Conceptual Design of a 500 MWe Traveling Wave Demonstration Reactor Plant," Proceedings of ICAPP 2011, Paper 11199, Nice, France, (May 2-5 2011).
  21. M. B. TOLOCZKO, F. A. Garner, and C. R. Eiholzer, "Irradiation Creep and Swelling of the U.S. Fusion Heats of HT9 and 9Cr-1Mo to 208 DPA at -$400^{\circ}C$", Journal of Nuclear Materials, 212-215, pp. 604-607, (1994). https://doi.org/10.1016/0022-3115(94)90131-7
  22. B. TOPPEL, A. Rago, D. O'Shea, "MC2: A Code to Calculate Multigroup Cross Sections," ANL-7318, Argonne National Laboratory (1967).
  23. A. P. OLSON, "A Users Guide for the REBUS-PC code, Version 1.4." ANL/RERTR/TM-32, Argonne National Laboratory (2002).
  24. J. FRICANO, "COBRA4i-MIT: an Updated Subchannel Analysis Code for Sodium Fast Reactor Design", Proc. ICAPP2011, Paper 11022, Nice, France, May 2-5, (2011).
  25. C. R. KAKARALA and C. E. Boardman, "Advanced Liquid Metal Reactor Helical Coil Steam Generator", American Society of Mechanical Engineers, NE - Vol. 5, Thermal hydraulics of Advanced Heat Exchangers, Book No. G00548, (1990).
  26. C. E. BOARDMAN, A. E. Dubberley, and D. G. Carroll, "S-PRISM's Advanced Steam Generator Leak Protection System", Proceedings of ICAPP '03, Cordoba, Spain, May 4-7, (2003).
  27. Y. I. CHANG, "Technical Rational for Metal Fuel in Fast Reactors", Nuclear Engineering and Technology, Volume 39, No. 3, (June 2007).
  28. J. E. CAHALAN, SASSYS Manual, ANL-FRA-1996-3, Volume 1, (August 1996).

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