New fuel cycle and fuel management options in heavy liquid metal-cooled reactors

Nuclear Technology

Volumn 151, Issue 2, 2005, Pages 177-191

  Greenspan, Ehud ^a   Hejzlar, Pavel ^b   Sekimoto, Hiroshi ^c   Toshinsky, Georgy ^d   Wade, David ^e  

^a UNIVERSITY OF CALIFORNIA   (United States)

^b MASSACHUSETTS INSTITUTE OF TECHNOLOGY   (United States)

^c TOKYO INSTITUTE OF TECHNOLOGY   (Japan)

^d INSTITUTE OF PHYSICS AND POWER ENGINEERING   (Russian Federation)

^e ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

Deep burn; Nuclear battery; Sustainable energy

Indexed keywords

COOLANTS; FAST REACTORS; NUCLEAR BATTERIES; REACTOR CORES; RECYCLING; SPENT FUELS; URANIUM;

DEEP BURN; FUEL CYCLE; FUEL MANAGEMENT; HIGH BURNUP; SUSTAINABLE ENERGY;

LIQUID METAL COOLED REACTORS;

EID: 22944480867     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT05-A3642     Document Type: Article

References (49)

1. B. F. GROMOV et al., "Use of Lead-Bismuth Coolant in Nuclear Reactors and Accelerator-Driven Systems," Nucl. Eng. Des., 173, 207 (1997).
2. Proc. Int. Conf. Heavy Liquid Metal Coolants in Nuclear Technologies, Obninsk, Russia, October 5-9, 1998.
3. E. O. ADAMOV, V. V. ORLOV, A. I. FILIN, V. N. LEONOV, A. G. SILA-NOVITSKI, V. S. SMIRNOV, and V. S. TSIKUNOV, "The Next Generation of Fast Reactors," Nucl. Eng. Des., 173, 143 (1997).
4. Z. SU'UD and H. SEKIMOTO, "A Concept of Long-Life Small Safe Reactor," presented at Int. Specialists' Mtg. Potential of Small Nuclear Reactors for Future Clean and Safe Energy Sources (SR/TIT), Tokyo, Japan, 1991.
5. H. SEKIMOTO and Z. SU'UD, "Design Study of Lead- and Lead-Bismuth-Cooled Small Long-Life Nuclear Power Reactors Using Metallic and Nitride Fuel," Nucl. Technol., 109, 307 (1995).
6. C. RUBBIA et al., "Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier," CERN/AT/95-44 (ET), European Organization for Nuclear Research (1995).
7. N. E. BROWN, J. HASSBERGER, E. GREENSPAN, and E. ELIAS, "Proliferation Resistant Fission Energy Systems," Proc. Global'97: Int. Conf. Future Nuclear Systems, Yokohama, Japan, October 5-10, 1997, p. 879.
8. E. GREENSPAN, K. AOKI, E. ELIAS, W. E. KASTENBERG, N. STONE, and N. W. BROWN, "Compact Long Fuel-Life Reactors for Developing Countries," Proc. 9th Int. Conf. Emerging Nuclear Energy Systems (ICENES'98), Herzlia, Israel, June 28-July 2, 1998, p. 74
9. E. GREENSPAN, K. AOKI, E. ELIAS, W. E. KASTENBERG, N. STONE, and N. W. BROWN, Trans. Am. Nucl. Soc., 78, 239 (1998).
10. E. GREENSPAN and D. C. WADE, "Encapsulated Nuclear Reactor Heat Source Module," Trans. Am. Nucl. Soc., 80, 197 (1999).
11. B. W. SPENCER et al., "An Advanced Modular HLMC Reactor Concept Featuring Economy, Safety, and Proliferation Resistance," Proc. 8th Int. Conf. Nuclear Engineering (ICONE8), Baltimore, Maryland, April 2-6, 2000 (2000).
12. D. C. WADE, B. W. SPENCER, R. D. DOCTOR, K. L. PEDDICORD, C. BOARDMAN, and G. MARUCCI, "A Proposed Modular-Sized, Integrated Nuclear and Hydrogen-Based Energy Supply/Carrier System," Proc. First Information Exchange Mtg. Nuclear Production of Hydrogen, Paris, France, October 2-3, Organization for Economic and Cooperative Development/Nuclear Energy Agency (2000).
13. E. GREENSPAN, A. BARAK, L. BLUMENAU, H. BRANOVER, A. EL-BOHER, E. SPERO, and S. SUKORIANSKY, "Liquid Metal MHD Conversion of Nuclear Energy to Electricity - Possibilities and Implications," Progress in Astronautics and Aeronautics, M. SUMMERFIELD, Ed., Vol. 111, p. 129, American Institute of Aeronautics and Astronautics (1988).
14. H. BRANOVER, A. EL-BOHER, E. GREENSPAN, and A. BARAK, "Promising Applications of the Liquid Metal MHD Energy Conversion Technology," Proc. 24th Intersociety Energy Conversion Engineering Conf., Washington, D.C., August 6-11, 1989, p. 1051.
15. A. BARAK, L. BLUMENAU, H. BRANOVER, A. EL-BOHER, E. GREENSPAN, E. SPERO, and S. SUKORIANSKY, "Possibilities for Improvements in Liquid-Metal Reactors Using Liquid Metal Magnetohydrodynamic Energy Conversion," Nucl. Technol., 89, 36 (1990).
16. H. BRANOVER, E. GREENSPAN, S. SUKORIANSKY, and G. TALMAGE, "MHD Considerations in the Design of Self-Cooled Liquid-Metal Blankets for Fusion Reactors," Proc. 9th Int. Conf MHD Electrical Power Generation, Tsukuba, Ibaraki, Japan, November 1986.
17. H. BRANOVER, E. GREENSPAN, S. SUKORIANSKY, and G. TALMAGE, "Turbulence and the Feasibility of Self-Cooled Liquid-Metal Blankets for Fusion Reactors," Fusion Technol., 10, 822 (1986).
18. E. GREENSPAN, N. W. BROWN, M. D. CARELLI, L. CONWAY, M. DZODZO, Q. HOSSAIN, D. SAPHIER, J. J. SIENICKI, and D. C. WADE, "The Encapsulated Nuclear Heat Source Reactor - A Generation IV Reactor," Proc. GLOBAL-2001, Paris, France, September 2001.
19. E. GREENSPAN, N. W. BROWN, M. D. CARELLI, L. CONWAY, M. DZODZO, Q. HOSSAIN, D. SAPHIER, J. J. SIENICKI, and D. C. WADE, "The Encapsulated Nuclear Heat Source Reactor for Proliferation-Resistant Nuclear Energy," Proc. GLOBAL-2001, Paris, France, September 2001.
20. E. GREENSPAN and ENHS PROJECT TEAM, "The Long-Life Core Encapsulated Nuclear Heat Source Generation IV Reactor," Proc. Int. Congress Advanced Nuclear Power Plant (ICAPP), Hollywood, Florida, June 9-13, 2002, American Nuclear Society (2002).
21. S.G. HONG, E. GREENSPAN, and Y. I. KIM, "Once-for-Life Core for the Encapsulated Nuclear Heat Source (ENHS) Reactor," Proc. Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing (PHYSOR-2002), Seoul, Korea, October 7-10, 2002.
22. D. C. WADE and Y. I. CHANG, "The Integral Fast Reactor Concept: Physics of Operation and Safety," Nucl. Sci. Eng., 100, 507 (1988).
23. D. C. WADE and R. N. HILL, "The Design Rationale of the IFR," Prog. Nucl. Energy, 31, 13 (1997).
24. S.G. HONG, E. GREENSPAN, Y. I. KIM, and H. R. KIM, "ENHS (Encapsulated Nuclear Heat Source) Core Designs Using Nitride Fuel," Proc. GLOBAL'03, New Orleans, Louisiana, November 2003.
25. J.J. SIENICKI, "Updated Thermal Hydraulic Analyses for Recent ENHS Design Improvements," Proc. Int. Congress Advances Nuclear Power Plants, Cordoba, Spain, May 4-7, 2003.
26. D. SAPHIER, M. DZODZO, and E. GREENSPAN, "Applying the DSNP Modular Modeling System to Transient and Accident Simulations of Lead Cooled Reactors," Proc. 9th Int. Conf. Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001.
27. D. SAPHIER, E. GREENSPAN, D. C. WADE, M. DZODZO, L. CONWAY, and N. W. BROWN, "Some Safety Aspects of the Encapsulated Nuclear Heat Source LMR Plant," Proc. 9th Int. Conf. Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001.
28. S. HATTORI and A. MINATO, "Current Status of 4S Plant Design," Proc. 2nd Int. Conf. Nuclear Engineering (ICONE-2), California, March 21-24, 1993, American Society of Mechanical Engineers-Japan Society of Mechanical Engineers (1993).
29. J. S. STEWART, A. D. LAMONT, G. S. ROTHWELL, C. F. SMITH, E. GREENSPAN, N. BROWN, and A. BARAK, "An Economic Analysis of Generation IV Small Modular Reactors," UCRL-ID-148437, Lawrence Livermore National Laboratory (Mar. 1, 2002).
30. H. SEKIMOTO and K. RYU, "A New Reactor Burnup Concept 'CANDLE,'" Proc. PHYSOR 2000, Pittsburgh, Pennsylvania, May 7-11, 2000, American Nuclear Society (2000) (CD-ROM).
31. H. SEKIMOTO, K. RYU, and Y. YOSHIMURA, "CANDLE: The New Burnup Strategy," Nucl. Sci. Eng., 139, 3, 306 (2001).
32. H. FEINROTH, J. GUON, and D. MAJUMDAR, "An Overview of the AIROX Process and Its Potential for Nuclear Fuel Recycle," Proc. Global Int. Fuel Cycle Conf., Seattle, Washington, 1993.
33. S. JAHSHAN and T. McGEEHAN, "Ah Evaluation of the Development of AIROX-Recycled Fuel in Pressurize Water Reactors," Nucl. Technol., 106, 350 (1994).
34. J. S. LEE, K. C. SONG, M. S. YANG, K. S. CHUN, B. W. RHEE, J. S. HONG, H. S. PARK, C. S. RIM, and H. KEIL, "Research and Development Program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors)," Proc. Int. Conf. Future Energy Systems: Emerging Nuclear Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington (September 1993).
35. E. GREENSPAN, N. Z. CHO, S. G. HONG, T. H. KIM, and W. E. KASTENBERG, "Multi-Recycling of Spent Fuel with Low Proliferation Risk," Proc. 9th Int. Conf. Emerging Nuclear Energy Systems (ICENES'98), Herzelia, Israel, June 1998.
36. C. E. BOARDMAN, A. E. DUBBERLEY, D. G. CARROLL, M. HUI, A. W. FANNING, and W. KWANT, "A Description of the S-PRISM Plant," Proc. ICONE-8, Baltimore, Maryland, April 2-6, 2000.
37. G. I. TOSHINSKY, "LMFBR Operation in the Nuclear Cycle Without Fuel Reprocessing," Proc. Int. Topl. Mtg. Advanced Reactors Safety (ARS'97), Vol. 1, p. 39, Orlando, Florida, June 1-5, 1997.
38. S. M. FEINBERG and E. P. KUNEGIN, "Nuclear Power Plants, Part 2, Discussion," Proc. 2nd U.N. Int. Conf. Peaceful Uses of Atomic Energy, Vol. 9, p. 447, United Nations, Geneva (1958).
39. K. FUCHS and H. HESSEL, "Uder die Moglichkeiten des Betriebs eines Namruranbrutreaktors ohne Brennstoffaufbereimng," Kernenergie, 4, 8, 619 (1961).
40. P. HEJZLAR, M. J. DRISCOLL, and M. S. KAZIMI, "Conceptual Neutronic Design of a Lead-Bismuth-Cooled Actinide Burning Reactor," Nucl. Sci. Eng., 139, 138 (2001).
41. P. HEJZLAR, M. J. DRISCOLL, M. S. KAZIMI, and N. E. TODREAS, "Minor Actinide Burning in Dedicated Lead-Bismuth Cooled Fast Reactors," Proc. 9 Int. Conf. Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001.
42. P. HEJZLAR, P. E. MacDONALD, N. E TODREAS, J. BUONGIORNO, M. J. DRISCOLL, and K. D. WEAVER, "Design Strategies for Lead-Alloy-Cooled Reactors for Actinide Burning and Low-Cost Electricity Production," Proc. 10th Int. Conf. Nuclear Engineering (ICONE-10), Arlington, Virginia, April 14-18, 2002.
43. P. HEJZLAR, J. BUONGIORNO, P. E. MacDONALD, and N. E. TODREAS, "Design Strategy and Constraints for Medium-Power Lead-Alloy-Cooled Actinide Burners," Nucl. Technol., 147, 321 (2004).
44. P. HEJZLAR and C. B. DAVIS, "Performance of the Lead-Alloy-Cooled Concept Balanced for Actinide Burning and Electricity Production," Nucl. Technol., 147, 344 (2004).
45. A. ROMANO, "Optimisation of Actinide Transmutation in Innovative Lead-Cooled Fast Reactors," PhD Thesis, Massachusetts Institute of Technology, Department of Nuclear Engineering (June 2003).
46. A. ROMANO, P. HEJZLAR, and N. E TODREAS, "Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning," Nucl. Technol., 147, 368 (2004).
47. W. MASCHEK, K. MORITA, and M. FLAD, "SIMMER III Analysis of Enhanced Fuel Removal Process Under Core Disruptive Accident Conditions," Proc. 6th Int. Conf. Nuclear Engineering (ICONE-6), New Orleans, Louisiana, May 10-15, 1998.
48. D. C. WADE and E. K. FUJITA, "Trends Versus Reactor Size of Passive Reactivity Shutdown and Control Performance," Nucl. Sci. Eng., 103, 182 (1989).
49. "Report of the Fuel Cycle Crosscut Group (FCCG)," on Generation IV Technology Roadmap Web Site, available on the Internet ar (http://gif.inel.gov/roadmap) (Dec. 2002).