A combined nonfertile and UO2 PWR fuel assembly for actinide waste minimization

Nuclear Technology

Volumn 149, Issue 3, 2005, Pages 281-303

  Shwageraus, Eugene ^a,b   Hejzlar, Pavel ^a   Kazimi, Mujid S ^a  

^a MASSACHUSETTS INSTITUTE OF TECHNOLOGY   (United States)

^b BEN GURION UNIVERSITY OF THE NEGEV   (Israel)

Author keywords

Advanced fuel cycle; Fertile free fuel; PWR actinide recycling

Indexed keywords

ACTINIDES; COMPUTER SIMULATION; ISOTOPES; NUCLEAR FUELS; RADIOACTIVE WASTES; REACTOR CORES; RECYCLING; THERMODYNAMICS; TOXICITY; WASTE MANAGEMENT;

ADVANCED FUEL CYCLE; FERTILE FREE FUEL; NEUTRONIC SIMULATION; PWR ACTINIDE RECYCLING; RADIOTOXICITY; THERMAL-HYDRAULIC ANALYSIS;

PRESSURIZED WATER REACTORS;

EID: 17644398217     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT05-A3596     Document Type: Article

References (28)

1. OECD/NEA, Accelerator-Driven Systems (ADS) and Fast reactors (FR) in Advanced Nuclear Fuel Cycles: A Comparative Study, Paris, France (2002).
2. G. J. VAN TUYLE, "Candidate Approaches for an Integrated Nuclear Waste Management Strategy - Scoping Evaluations," LA-UR-01-5572, Los Alamos National Laboratory (Nov. 2001).
3. N. KODOCHIGOV, YU. SUKHAREV, E. MAROVA, N. PONOMAREV-STEPNOY, E. GLUSHKOV, and P. FOMICHENKO, "Neutronic Features of the GT-MHR Reactor," Proc. 1Oth Int. Conf. Nuclear Engineering (ICONE-10), Arlington, Virginia, April 14-18, 2002 (2002).
4. C. RUBBIA, S. BRUNO, Y. KADI, and J. A. RUBIO, "Fast Neutron Incineration in the Energy Amplifier as Alternative to Geologic Storage: The Case of Spain," CERN/LHC/97-01, European Organization for Nuclear Research (1997).
5. D. E. BELLER, G. J. VAN TUYLE, D. BENNETT, G. LAWRENCE, K. THOMAS, K. PASAMEHMETOGLU, N. LI, D. HILL, J. LAIDLER, and P. FINK, "The U.S. Accelerator Transmutation of Waste Program," Nucl. Instrum. Methods Phys. Research, A463, 468 (2001).
6. P. HEJZLAR, M. J. DRISCOLL, and M. S. KAZIMI, "Conceptual Neutronic Design of a Lead-Bismuth-Cooled Actinide Burning Reactor," Nucl. Sci., Eng., 139, 1 (2001).
7. R. N. HILL, D. C. WADE, J. R. LIAW, and E. K. FUJITA, "Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle," Nucl. Sci. Eng., 121, 17 (1995).
8. H. KURAISHI, T. SAWADA, and H. NINOKATA, "Inherent and Passive Safety Sodium-Cooled Fast Reactor Core Design with Minor Actinide and Fission Product Incineration," Nucl. Sci. Eng., 138, 205 (2001).
9. A. VASILE, PH. DUFOUR, H. GOLFIER, J. P. GROUILLER, J. L. GUILLET, CH. POINOT, G. YOUINOU, and A. ZAETTA, "Advanced Fuels for Plutonium Management in Pressurized Water Reactors," J. Nucl. Materials, 319, 173 (2003).
10. E. SHWAGERAUS, P. HEJZLAR, and M. S. KAZIMI, "Use of Th for Transmutation of Pu and Minor Actinides in PWRs," Nucl. Technol., 147, 53 (2004).
11. A. GALPERIN, M. SEGEV, and M. TODOSOW, "A Pressurized Water Reactor Plutonium Incinerator Based on Thorium Fuel and Seed-Blanket Assembly Geometry," Nucl. Technol., 132, 214 (2000).
12. M. EDENIUS, K. EKBERG, B. H. FORSSEN, and D. KNOTT, "CASMO-4, A Fuel Assembly Burnup Program: User's Manual," STUDSVIK/SOA-95/1, Studsvik of America (1995).
13. A. S. DIGIOVINE and J. D. RHODES, "SIMULATE-3 User's Manual," Studsvik/ SOA-95/15, Studsvik of America (1995).
14. M. J. DRISCOLL, T. J. DOWNAR, and E. E. PILAT, The Linear Reactivity Model for Nuclear Fuel Management, American Nuclear Society, La Grange Park, Illinois (1990).
15. J. M. CUTA, A. S. KOONTZ, C. W. STEWART, S. D. MONTGOMERY, and K. K. NOMURA, "VIPRE-01: A Thermal-Hydraulic Code for Reactor Cores," EPRI NP-2511-CCMA, Electric Power Research Institute (July 1985).
16. Z. XU, P. HEJZLAR, M. J. DRISCOLL, and M. S. KAZIMI, "An Improved MCNP-ORIGEN Depletion Program (MCODE) and Its Verification for High burnup Applications," Proc. PHYSOR 2002, Seoul, Korea, October 7-10, 2002 (2002).
17. "RSICC Computer Code Collection - ORIGEN 2.1, Isotope Generation and Depletion Code Matrix Exponential Method," CCC-371, Rev. version, Oak Ridge National Laboratory (May 2002).
18. E. SHWAGERAUS, P. HEJZLAR, and M. S. KAZIMI, "Optimization of the LWR Nuclear Fuel Cycle for Minimum Waste Production," MIT-NFC-TR-060, Department of Nuclear Engineering, Massachusetts Institute of Technology (Oct. 2003).
19. O. COURSON, R. MALMBECK, G. PAGLIOSA, K. RÖMER, B. SÄTMARK, J. P. GLATZ, P. BARON, and C. MADIC, "Separation of Minor Actinides from Genuine HLLW using the DIAMEX Process," Proc. Fifth OECD/NEA Information Exchange Mtg. on Actinide and Fission Product Partitioning and Transmutation, SCK-CEN, Mol, Belgium, November 25-27, 1998 (1998).
20. M. OZAWA, Y. SANO, K. NOMURA, Y. KOMA, and M. TAKANASHI, "A New Reprocessing System Composed of PUREX and TRUEX Processes for Total Separation of Long-Lived Radionuclides," Proc. Fifth OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, SCK-CEN, Mol, Belgium, November 25-27, 1998 (1998).
21. Y. YUAN, H. C. NO, and M. S. KAZIMI, "A Preliminary Investigation of Performance of Rock-Like Oxide Fuel for High Burnup in LWRs," MIT-NFC-TR-037, Department of Nuclear Engineering, Massachusetts Institute of Technology (Dec. 2001).
22. Y. LONG, Y. ZHANG, and M. S. KAZIMI, "A Survey of Inert Matrix Materials as Hosts of Actinide Nuclear Fuels," MIT-NFC-TR-055, Massachusetts Institute of Technology (Mar. 2003).
23. J. F. BRIESMEISTER, Ed., "MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709M, Los Alamos National Laboratory (Apr. 2000).
24. "ICRP Publication 68: Dose Coefficients for Intakes of Radionuclides by Workers: A Report of a Task Group of Committee 2 of the International Commission on Radiological Protection," Edited by ICRP, 0-08-042651-4 (1995).
25. "Report to Congress on Advanced Fuel Cycle Initiative: The Future Path for Advanced Spent Fuel Treatment and Transmutation Research," U.S. Department of Energy, Office of Nuclear Energy (Jan. 2003).
26. P. BRUSSELAERS, TH. MALDAGUE, S. PILATE, J. L. KLOOSTERMAN, K. ABRAHAMS, and J. M. LI, "Possible Transmutation of Long-lived Fission Products in Usual Reactors," Proc. Int. Conf Physics of Reactors: PHYSOR 96, 3, M-101, Mito, Japan, September 16-20, 1996 (1996).
27. H. BAIRIOT and C. VANDENBERG, "Use of MOX Fuels," Nuclear Fuel Cycle in the 1990s and Beyond the Century: Some Trends and Foreseeable Problems, Technical Reports Series No. 305, p. 73, IAEA, Vienna (1989).
28. T. A. TAIWO, T. K. KIM, and M. SALVATORES, "Feasibility Study of a Proliferation Resistant Fuel Cycle for LWR-Based Transmutation of Transuranics," ANL-AAA-027, Argonne National Laboratory (Sep. 2002).