Liquid-salt cooling for Advanced High-Temperature Reactors

Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05

Volumn 4, Issue , 2005, Pages 2080-2095

  Forsberg, C W ^a   Peterson, P F ^b   Williams, D F ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b UNIVERSITY OF CALIFORNIA   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ADVANCED HIGH TEMPERATURE REACTOR (AHTR); COOLANT TEMPERATURE; LIQUID SALT COOLING;

BOILING POINT; BRAYTON CYCLE; COATED FUEL PARTICLES; COOLING; FAST REACTORS; LIQUID METAL COOLED REACTORS;

HIGH TEMPERATURE REACTORS;

EID: 34248997531     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (14)

1. C. W. FORSBERG, P. F. Peterson, and D. W. Williams, "Practical Aspects of Liquid-Salt-Cooled Fast-Neutron Reactors," 2005 International Conference on Advances in Nuclear Power Plants, Seoul, Korea, May 15-19, 2005, American Nuclear Society, La Grange Park, IL (2005).
2. Nucl. Appl. Technol., 8(2) (Entire issue) (1970).
3. R. W. MOIR, et al., "HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design-Final Report," Fusion Energy, 25, 5-25 (1994).
4. C. W. FORSBERG, P. S. Pickard, and P. F. Peterson, "Molten-Salt- Cooled Advanced High-Temperature Reactor for Production of Hydrogen and Electricity," Nucl. Technol. 144, 289-302 (2003).
5. D. T. INGERSOLL, et al., Status of Preconceptual Design of the Advanced High-Temperature Reactor, ORNL/TM-2004/104, Oak Ridge National Laboratory, Oak Ridge, Tennessee (2004).
6. C. W. FORSBERG, "Reactors with Molten Salts: Options and Missions," Proc. Frederic Joliot & Otto Han Summer School on Nuclear Reactors: Physics, Fuels, and Systems, Cadarache, France, August 25-September 3, 2004 (2004).
7. P. F. PETERSON and J. Zhao, "Material Input for Advanced Brayton Cycle Power Conversion Systems," Trans. 2004 American Nuclear Society Winter Meeting, November 14-18, 2004, Washington, D.C. (2004).
8. H. E. McCOY and B. McNabb, Postirradiation Examination of Materials from the MSRE, ORNL/TM-4174, Oak Ridge National Laboratory, Oak Ridge, Tennessee (1972).
9. M. W. ROSENTHAL, R. B. Briggs, and P. R. Kasten, Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1968, ORNL-4344, Oak Ridge National Laboratory, Oak Ridge, Tennessee (1969).
10. P. F. PETERSON, C. W. Forsberg, and P. S. Pickard, "Advanced CSiC Composites for High-Temperature Nuclear Heat Transport with Helium, Molten Salts, and Sulfur-Iodine Thermochemical Hydrogen Process Fluids," Proc. OECD/NEA Second Information Exchange Meeting on Nuclear Production of Hydrogen, October 2-3, 2003, Argonne National Laboratory, Argonne, Illinois Nuclear Energy Agency, Paris (2003).
11. D. F. WILLIAMS, D. F. Wilson, L. M. Toth, J. Caja, and J. K. Keiser, "Research on Molten Fluorides as High-Temperature Heat Transfer Agents," Global 2003, Embedded Topical Within 2003 American Nuclear Society Winter Meeting, November 16-20, 2003, New Orleans, Louisiana (2003).
12. UNITED STATES NUCLEAR REGULATORY COMMISSION, "Allowable Positive MTC Limit" (see Fig. 3.1.3-1) in Standard Technical Specifications Combustion Engineering Plants, NUREG-1432, Vol. 1, (June 2004).
13. NUCLEAR ENERGY AGENCY, Proc. OECD/NEA Second Information Exchange Meeting on Nuclear Production of Hydrogen, October 2-3, 2003, Argonne National Laboratory, Argonne, Illinois, Nuclear Energy Agency, Paris (2003).
14. 2 Cycles, MIT-NES-TR-002, Center for Advanced Nuclear Energy Systems, Department of Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts (December 2004).