Influence of the processing and salt composition on the thorium molten salt reactor

Nuclear Technology

Volumn 163, Issue 3, 2008, Pages 358-365

  Merle Lucotte, Elsa ^a   Mathieu, Ludovic ^a   Heuer, Daniel ^a   Ghetta, Véronique ^a   Brissot, Roger ^a   Le Brun, Christian ^a   Liatard, Eric ^a  

^a UNIVERSITÉ JOSEPH FOURIER GRENOBLE 1   (France)

Author keywords

Reprocessing; Thorium fuel cycle; Thorium molten salt reactor

Indexed keywords

ACTINIDES; CHEMICAL BONDS; FISSION PRODUCTS; FUELS; FUSED SALTS; MOLTEN MATERIALS; NUCLEAR FUEL REPROCESSING; NUCLEAR REACTORS; SCRAP METAL REPROCESSING; THORIUM; TRANSURANIUM ELEMENTS;

ENERGY PRODUCTIONS; NEUTRONIC EFFECTS; PARTIAL PROCESSING; PROCESSING RATES; PROCESSING UNITS; THORIUM FUEL CYCLES; THORIUM MOLTEN SALTS; TRANSURANIC ELEMENTS;

MOLTEN SALT REACTOR;

EID: 51049118130     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT08-A3994     Document Type: Conference Paper

References (15)

1. M. W. ROSENTHAL et al., "Molten Salt Reactors - History, Status, and Potential," Nucl. Appl. Technol., 8, 107 1970).
2. D. LECARPENTIER, "Le concept AMSTER, aspects physiques et sûreté," PhD Thesis, Conservatoire National des Arts et Métiers, Paris (2001) (in French).
3. A. NUTTIN et al., "Potential of Thorium Molten Salt Reactors: Detailed Calculations and Concept Evolution with a View to Large Scale Energy Production," Prog. Nucl. Energy, 46, 1, 77 (2005).
4. C. LE BRUN, "Molten Salts and Nuclear Energy Production," J. Nucl. Mater., 360, 1, 1 (2007).
5. R. C. BRIANT and A. M. WEINBERG, "Molten Fluorides as Power Reactor Fuels," Nucl. Sci. Eng., 2, 797 (1957).
6. P. N. HAUBENREICH and J. R. ENGEL, "Experience with the Molten Salt Reactor Experiment," Nucl. Appl. Techol., 8, 107 (1970).
7. E. S. BETTIS and R. C. ROBERTSON, "The Design and Performance Features of a Single-Fluid Molten Salt Breeder Reactor," Nucl. Appl. Technol., 8, 190 (1970).
8. M. W. ROSENTHAL, P. N. HALBENREICH, and R. B. BRIGGS, "The Development Status of Molten-Salt Breeder Reactors," ORNL-4812, Oak Ridge National Laboratory (1972).
9. M. E. WHATLEY, L. E. MCNEESE, W. L. CARTER, L. M. FERRIS, and E. L. NICHOLSON, "Engineering Development of the MSBR Fuel Recycle," Nucl. Appl. Technol., 8, 170 (1970).
10. L. MATHIEU, "Potentialités des réacteurs à sels fondus en cycle Thorium dans les scénarios du futur: le concept de Thorium. Molten Salt Reactor," PhD Thesis, Institut National Poly-technique de Grenoble, France (2005) (in French).
11. L. MATHIEU, D. HEUER, R. BRISSOT, C. LE BRUN, E. LIATARD, J. M. LOISEAUX, O. MÉPLAN, E. MERLE-LUCOTTE, and A. NUTTIN, "The Thorium Molten Salt Reactor: Moving on from the MSBR," Prog. Nucl. Eng., 48, 664 (2006).
12. "MCNP4B-A General Monte Carlo N Particle Transport Code," LA-12625-M, J.F. BRIESMEISTER, Ed., Los Alamos National Laboratory (1997).
13. E. WALLE, J. FINNE, G. PICARD, S. SANCHEZ, O. CONOCAR, and J. LACQUEMENT, "Molten Salt Reactors: Chemistry of Fuel Salt and Fuel Salt Cleanup," Proc. Global 2003, New Orleans, Louisiana, November 16-20, 2003, American Nuclear Society (2003) (CD-ROM).
14. W. H. CARR, L. J. KING, F. G. KITTS, W. T. McDUFFEE, and F. W. MILES, "Molten-Salt Fluoride Volatility Pilot Plant: Recovery of Enriched Uranium from Aluminium-Clad Fuel Elements," ORNL-4574, Oak Ridge National Laboratory (1971).
15. R. E. THOMA, "Phase Diagrams of Nuclear Reactor Materials," ORNL-2548, p. 119, Oak Ridge National Laboratory (1959).