PRISM: A competitive small modular sodium-cooled reactor

Nuclear Technology

Volumn 178, Issue 2, 2012, Pages 186-200

  Triplett, Brian S ^a   Loewen, Eric P ^a   Dooies, Brett J ^a  

^a GE HITACHI NUCLEAR ENERGY   (United States)

Author keywords

Integral fast reactor; Pyroprocessing; Spent used nuclear fuel recycling

Indexed keywords

FAST REACTORS; FUELS; LIGHT WATER REACTORS; LIQUID METAL COOLED REACTORS; NUCLEAR REACTORS; NUCLEAR WEAPONS; RECYCLING; SODIUM;

FUEL RECYCLING; INTEGRAL FAST REACTORS; POWER REACTIVITY FEEDBACK; PYROPROCESSING; SAFETY EVALUATION REPORT; SMALL MODULAR REACTORS; SODIUM COOLED FAST REACTOR; U.S. NUCLEAR REGULATORY COMMISSION;

PRISMS;

EID: 84862096225     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT178-186     Document Type: Article

References (53)

1. "EBR-I Fact Sheet", 06-GA50269, Idaho National Laboratory (2006).
2. L. KOCH, "EBR-II Experimental Breeder Reactor-II", Argonne National Laboratory (1987).
3. E. L. GLUEKLER, "U. S. Advanced Liquid Metal Reactor (ALMR)", Prog. Nucl. Energy, 31, 43 (1997).
4. R. C. BERGLUND and R. B. TUPPER, "An Overview of Development Progress on PRISM: The Plant Design Concept for the U. S. Advanced Liquid Metal Reactor Program", Proc. Pacific Basin Nuclear Conf., Taipei, China, April 1992.
5. D. J. HILL, "Global Nuclear Energy Partnership Technology Development Plan", GNEP-TECH-TR-PP 2007, Idaho National Laboratory (2007).
6. C. L. COCKEY, T. WU, A. J. LIPPS, and R. N. HILL, "Higher Actinide Transmutation in the ALMR", Proc. Global'93, Future Nuclear Systems: Fuel Cycles and Waste Disposal Options, September 1993.
7. R. A. WIGELAND, T. H. BAUER, T. H. FANNING, and E. E. MORRIS, "Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository", Nucl. Technol., 154, 95 (2006).
8. D. C. WADE and Y. I. CHANG, "The Integral Fast Reactor Concept: Physics of Operation and Safety", Nucl. Sci. Eng., 100, 507 (1988).
9. C. E. BOARDMAN, C. S. EHRMAN, C. HESS, M. OCKER, and M. THOMPSON, "Integrating ALWR and ALMR Fuel Cycles", Proc. 4th Int. Conf. Nuclear Engineering (ICONE-4), New Orleans, Louisiana, March 10-14, 1996.
10. COMMITTEE ON ELECTROMETALLURGICALTECHNIQUES FOR DOE SPENT FUEL TREATMENT, Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report, National Academy Press, Washington, D. C. (2000).
11. W. H. HANNUM, D. C. WADE, H. F. McFARLANE, and R. N. HILL, "Nonproliferation and Safeguards Aspects of the IFR", Prog. Nucl. Energy, 31, 217 (1997).
12. C. S. EHRMAN and C. E. BOARDMAN, "System Considerations for Actinide Recycle in Fast Reactors", Proc. Global'95 Fuel Cycle Conference, Versailles, France, September 1995.
13. C. S. EHRMAN, C. HESS, M. OCKER, and D. WADE-KAMPER, "Design Consideration for a Pyroprocess Recycle Facility", Proc. Global'95 Fuel Cycle Conference, Versailles, France, September 1995.
14. L. N. SALERNO, R. C. BERGLUND, G. L. GYOREY, F. E. TIPPETS, and P. M. TSCHAMPER, "PRISM Concept, Modular LMR Reactors", Nucl. Eng. Des., 109, 79 (1988).
15. D. T. INGERSOLL, "Deliberately Small Reactors and the Second Nuclear Era", Prog. Nucl. Energy, 51, 589 (2009).
16. C. E. BOARDMAN, A. E. DUBBERLEY, D. G. CAR-ROLL, M. HUI, A. W. FANNING, and W. KWANT, "A Description of the S-PRISM Plant", Proc. 8th Int. Conf Nuclear Engineering (ICONE-8), Baltimore, Maryland, April 2-6, 2000.
17. W. KWANT and C. E. BOARDMAN, "PRISM-Liquid Metal Cooled Reactor Plant Design and Performance", Nucl. Eng. Des., 136, 111 (1992).
18. C. E. BOARDMAN, A. E. DUBBERLEY, and M. HUI, "Optimizing the Size of the S-PRISM Reactor", Proc. 8th Int. Conf. Nuclear Engineering (ICONE-8), Baltimore, Maryland, April 2-6, 2000.
19. A. E. DUBBERLEY, C. E. BOARDMAN, K. YOSHIDA, and T. WU, "S-PRISM Oxide and Metal Fuel Cord Designs", Proc. 8th Int. Conf Nuclear Engineering (ICONE-8), Baltimore, Maryland, April 2-6, 2000.
20. A. E. DUBBERLEY, T. WU, and S. KUBO, "S-PRISM High Burnup Metal-Fuel Core Design", Proc. Int. Conf. Advancement of Nuclear Power Plants (ICAPP'03), Cordoba, Spain, May 4-7, 2003.
21. J. E. QUINN, P. M. MAGEE, M. L. THOMPSON, and T. WU, "ALMR Fuel Cycle Flexibility", Proc. American Power Conf, 1993.
22. A. E. DUBBERLEY, C. E. BOARDMAN, D. G. CAR-ROLL, C. EHRMAN, and C. E. WALTER, "S-PRISM Fuel Cycle Study", Proc. Int. Conf Advancement of Nuclear Power Plants (ICAPP'03), Cordoba, Spain, May 4-7, 2003.
23. D. C. CRAWFORD, D. L. PORTER, and S. L. HAYES, "Fuels for Sodium-Cooled Fast Reactors: US Perspective", J. Nucl. Mater., 371, 202 (2007).
24. G. L. HOFMAN, L. C. WATERS, and T. H. BAUER, "Metallic Fast Reactor Fuels", Prog. Nucl. Energy, 31, 83 (1997).
25. D. E. BURKES, R. S. FIELDING, D. L. PORTER, D. C. CRAWFORD, and M. K. MEYER, "A US Perspective on Fast Reactor Fuel Fabrication Technology and Experience, Part I: Metal Fuels and Assembly Design", J. Nucl. Mater., 389, 458 (2009).
26. W. J. CARMACK et al. "Metallic Fuels for Advanced Reactors", J. Nucl. Mater., 392, 139 (2009).
27. "Design Data, Part 1: Structural Materials, Group 1: High Alloy Steels, Section 10-HT-9 Steel", Nuclear Systems Material Handbook, Vol. 1, Rev. 3, TID26666, Hanford Engineering Development Laboratory (1976).
28. D. S. GELLES, "Development of Martensitic Steels for High Neutron Damage Applications", J. Nucl. Mater., 239, 99 (1996).
29. R. L. KLUEH and A. T. NELSON, "Ferritic/Martensitic Steels for Next-Generation Reactors", J. Nucl. Mater., 371, 37 (2007).
30. A. E. DUBBERLEY, C. E. BOARDMAN, R. E. GAM-BLE, M. M. HUI, A. J. LIPPS, and T. WU, "Transient Performance of S-PRISM", Proc. 9th Int. Conf. Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001.
31. G. L. GYOREY, R. W. HARDY, and P. M. MAGEE, "Safety and Licensing of the PRISM Liquid Metal Cooled Reactor", Nucl. Eng. Des., 137, 181 (1992).
32. G. C. SLOVIK, G. J. VAN TUYLE, and S. SANDS, "Assessment of PRISM Response to Loss of Flow Events", BNL-NUREG-47818, Proc. Int. Conf. Design and Safety of Advanced Nuclear Power Plants, Tokyo, Japan, October 1992.
33. G. C. SLOVIK and G. J. VAN TUYLE, "Analysis of Unscrammed Events in PRISM", BNL-NUREG-46344, Brookhaven National Laboratory (1990).
34. G. C. SLOVIK and G. J. VAN TUYLE, "Analysis of Postulated Events for the Revised ALMR/PRISM Design", BNL-NUREG-46429, Proc. Nuclear Regulatory Commission Water Reactor Safety Information Mtg., Bethesda, Maryland, October 1991.
35. H. P. PLANCHON, R. M. SINGER, D. MOHR, E. E. FELDMAN, L. K. CHANG, and P. R. BETTEN, "The Experimental Breeder Reactor II Inherent Shutdown and Heat Removal Tests-Results and Analysis", Nucl. Eng. Des., 91, 287 (1986).
36. C. E. LAHM, J. F. KOENIG, P. R. BETTEN, J. H. BOTT-CHER, W. K. LEHTO, and B. R. SEIDEL, "EBR-II Driver Fuel Qualification for Loss-of-FIow and Loss-of-Heat-Sink Tests Without Scram", Nucl. Eng. Des., 101, 25 (1987).
37. 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", Nucl. Eng. Des., 101, 45 (1987).
38. W. K. LEHTO, R. M. FRYER, E. M. DEAN, J. F. KOENIG, L. K. CHANG, D. MOHR, and E. E. FELDMAN, "Safety Analysis from the Loss-of-Flow and Loss-of-Heat Sink Without Scram Tests in EBR-II", Nucl. Eng. Des., 101, 35 (1987).
39. T. H. BAUER, A. E. WRIGHT, W. R. ROBINSON, J. W. HOLLAND, and E. A. RHODES, "Behavior of Modern Metallic Fuel in TREAT Transient Overpower Tests", Nucl. Technol., 92, 325 (1990).
40. E. P. LOEWEN and C. E. BOARDMAN, "Selection of the Reference Steam Generator for the Advanced Liquid Metal Reactor", Proc. Global'07: Advanced Nuclear Fuel Cycles and Systems, Boise, Idaho, September 9-13, 2007, American Nuclear Society.
41. C. E. BOARDMAN and M. HUI, "A Competitive Integral Fast Reactor with Enhanced Diversion Resistance (S-PRISM)", Proc. Int. Conf. Future Nuclear Systems (GLOBAL-99), Jackson Hole, Wyoming, August 29-September 3, 1999.
42. G. J. VANTUYLE, "Simplified Analysis of PRISM RVACS Performance Without Linear Spill-Over", BNL-NUREG-44501, Proc. Int. Topi. Mtg. Fast Reactor Safety, Snowbird, Utah, August 1990.
43. C. E. BOARDMAN, A. E. DUBBERLEY, M. HUI, and K. IWASHIGE, "Containment Performance of S-PRISM Under Severe BDB Conditions", Proc. 9th Int. Conf. Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001.
44. E. L. GLUEKLER, C. C. BIGELOW, V. DEVITA, J. M. KELLY, R. W. SEIDENSTICKER, and F. F. TAJIRIAN, "Seismic Isolation Development for the US Advanced Liquid-Metal Reactor Program", Nucl. Eng. Des., 127, 295 (1991).
45. E. L. GLUEKLER, "Status of Reactor Seismic Isolation Technology Development in the USA and Summary of IAEA Specialists Meeting", Proc. Int. Post-SMIRT Conf. Seminar on Isolation Energy Dissipation and Control of Vibration of Structures, Napoli, Capri, August 1993.
46. "Global Nuclear Energy Partnership Business Development Plan", U. S. Department of Energy Report, GE Hitachi Nuclear Energy (2008).
47. E. P. LOEWEN, J. BOAZ, E. SAITO, and C. E. BOARD-MAN, "Commercialization of the Global Nuclear Energy Partnership (GNEP)", Proc. 15th Int. Conf. Nuclear Engineering (ICONE-15), Nagoya, Japan, April 2007.
48. "Global Nuclear Energy Partnership Advanced Recycling Center 2008 Cost & Schedule Report", U. S. Department of Energy Report, GE Hitachi Nuclear Energy (2008).
49. C. E. BOARDMAN, M. HUI, D. G. CARROLL, and A. E. DUBBERLEY, "Economic Assessment of S-PRISM Including Development and Generating Costs", Proc. 9th Int. Conf. Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001.
50. C. E. BOARDMAN, D. CARROLL, and M. HUI, "A Fast Track Approach to Commercializing the Sodium Cooled Fast Reactor", Proc. 7th Int. Conf. Nuclear Engineering (ICONE-7), Tokyo, Japan, April 10-23, 1999.
51. IEEE Std. 323-2003, "Qualifying Class IE Equipment for Nuclear Power Generating Stations", Institute of Electrical and Electronics Engineers (2003).
52. A. E. DUBBERLEY, C. E. BOARDMAN, A. J. LIPPS, and T. WU, "S-PRISM Metal Core Margins to Severe Core Damage", Proc. 8th Int. Conf. Nuclear Engineering (ICONE-8), Baltimore, Maryland, April 2-6, 2000.
53. K. A. EL-SHEIKH and D. HAHN, "Effectiveness of Natural Phenomena in Reducing the Source Term and Consequences of Severe Accidents in the ALMR", Proc. 3rd Int. Conf. Nuclear Engineering (ICONE-3), Kyoto, Japan, April 17-23, 1995.