A physics study on thorium fuel recycling in a CANDU reactor using dry process technology

Nuclear Technology

Volumn 153, Issue 2, 2006, Pages 132-145

  Choi, Hangbok ^a   Park, Chang Je ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

CANDU reactor; Dry process; Thorium recycle

Indexed keywords

DEUTERIUM COMPOUNDS; MATHEMATICAL MODELS; MODERATORS; NUCLEAR FUELS; NUCLEAR REACTORS; REACTIVITY (NUCLEAR); THERMOMECHANICAL TREATMENT; THORIUM; VOLUME FRACTION;

CANADA DEUTERIUM URANIUM (CANDU) REACTOR; DRY PROCESS FUEL TECHNOLOGY; NUCLEAR ENERGY SYSTEM; REACTIVITY COEFFICIENTS; THORIUM FUEL;

NUCLEAR ENERGY;

EID: 31744432361     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT06-A3695     Document Type: Article

References (20)

1. "Generation 4 Roadmap Fuel Cycle Crosscut Group Executive Summary," U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum (2001).
2. E. CRITOPH, S. BANERJEE, F. W. BARCLAY, D. HAMEL, M. S. MILGRAM, and J. I. VEEDER, "Prospects for Self-Sufficient Equilibrium Thorium Cycles in CANDU Reactors," AECL-5501, Atomic Energy of Canada Limited (1976).
3. D. F. TORGERSON, P. G. BOCZAR, and A. R. DASTUR, "CANDU Fuel Cycle Flexibility," Bull. Canadian Nucl. Soc., 15, 24 (1994).
4. P. G. BOCZAR, P. S. W. CHAN, G. R. DYCK, R. J. ELLIS, R. T. JONES, J. D. SULLIVAN, and P. TAYLOR, "Thorium Fuel Cycle Studies for CANDU Reactors," IAEA-TECODC-1319, International Atomic Energy Agency (2002).
5. 2 Fuel in CANDU Reactors Through Dry Reprocess Technology," Trans. Am. Nucl. Soc., 88, 389 (2003).
6. H. CHOI, C. J. PARK, M. S. YANG, and H. FEINROTH, "Transmutation of Thorium/DUPIC Fuel in a CANDU Reactor," Proc. GLOBAL 2003, Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, New Orleans, Louisiana, November 16-20, 2003, p. 194, American Nuclear Society (2003).
7. O. V. SKIBA, A. A. MAYORSHIN, P. T. PORODNOV, and A. V. BYCHKOV, "Nuclear Fuel Cycle Based on 'Dry' Methods for Fuel Reprocessing and Fuel Elements Manufacture Automated Processes," Proc. Int. Conf. Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 934, American Nuclear Society (1993).
8. 2 Vibropac Fuel Elements Capable of Operation up to Super-High Burnups," Proc. Int. Conf. Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, September 11-14, 1995, p. 1417, American Nuclear Society (1995).
9. A. V. BYCHKOV, O. V. SKIBA, A. A. MAYORSHIN, V. A. KISLY, S. K. VAVILOV, M. V. KORMILITZYN, L. S. DEMIDOVA, L. G. BABIKOV, and R. A. KUZNETSOV, "Fuel Cycle of Actinide Bumer-Reactor. Review of Investigations by «DOVITA» Program," Proc. Int. Conf. Future Nuclear Systems, Challenge Towards Second Nuclear Era with Advanced Fuel Cycles, Yokohama, Japan, October 5-10, 1997, p. 657, American Nuclear Society (1997).
10. J. S. LEE, K. C. SONG, M. S. YANG, K. S. CHUN, B. W. RHEE, J. S. HONG, H. S. PARK, and H. KEIL, "Research and Development Program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors)," Proc. Int. Conf. Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 733, American Nuclear Society (1993).
11. H. CHOI, B. W. RHEE, and H. S. PARK, "Physics Study on Direct Use of Spent PWR Fuel in CANDU (DUPIC)," Nucl. Sci. Eng., 126, 80 (1997).
12. W. W. R. INCH, P. D. THOMPSON, and H. C. SUK, "Introduction of the New Fuel Bundle 'CANFLEX' into an Existing CANDU Reactor," Proc. 12th Pacific Basin Nuclear Conf. (PBNC 2000), Seoul, Korea, October 29-November 2, 2000, p. 579, Korea Atomic Industrial Forum (2000).
13. M. S. YANG, Y. W. LEE, K. K. BAE, and S. H. NA, "Conceptual Study on the DUPIC Fuel Manufacturing Technology," Proc. Int. Conf. Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 740, American Nuclear Society (1993).
14. S. N. JAHSHAN and T. J. McGEEHAN, "An Evaluation of the Development of AIROX-Recycled Fuel in Pressurized Water Reactors," Nucl. Technol., 106, 350 (1994).
15. H. W. GRAVES, Jr., Nuclear Fuel Management, p. 276, John Wiley & Sons, New York (1979).
16. J. V. DONNELLY, "WIMS-CRNL: A User's Manual for the Chalk River Version of WIMS," AECL-8955, Atomic Energy of Canada Limited (1986).
17. A. G. CROFF, "A User's Manual for the ORIGEN2 Computer Code," ORNL/TM-7175, Oak Ridge National Laboratory (1980).
18. W. I. KO, H. CHOI, and M. S. YANG, "Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - IV: DUPIC Fuel Cycle Cost," Nucl. Technol., 134, 167 (2001).
19. "The Economics of the Nuclear Fuel Cycle," Organization for Economic Cooperation and Development/Nuclear Energy Agency (1993).
20. H. CHOI, C. J. JEONG, and M. S. YANG, "Composition Adjustment on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU," Nucl. Sci. Eng., 131, 62 (1999).