Sustainability and Economics of the Advanced High-Temperature Reactor
Publication: Journal of Energy Engineering
Volume 132, Issue 3
Abstract
The advanced high-temperature reactor is a new reactor concept that combines four technologies in a new way: coated-particle nuclear fuels traditionally used for helium-cooled reactors, Brayton power cycles, passive safety systems and plant designs from liquid-cooled fast reactors, and low-pressure liquid-salt coolants. The new combination of technologies may enable the development of a large high-efficiency, lower-cost high-temperature reactor for electricity and hydrogen production. As the peak reactor coolant temperatures approach , several technologies (Brayton cycles, passive reactor safety systems, available materials, etc.) work together to improve total system performance while significantly reducing costs relative to those for other reactors. A window of performance and lower capital costs exists between these temperatures and the practical temperature limits of materials. The higher temperatures and efficiency of the Brayton power cycle greatly reduce the total heat rejection compared with that achieved in current light-water reactors and may allow economic heat rejection with dry cooling towers, thus radically reducing the water consumption used in energy production. The option for dry cooling is facilitated by the characteristics of Brayton cycles, which reject heat over a temperature range of and thus match the requirements of dry cooling systems.
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References
Boardman, C. E., Dubberley, A. E., Carroll, D. G., Hui, M., Fanning, A. W., and Kwant, W. (2002). “A description of the S-prism plant.” ICONE-8168, Presented at the 8th Int. Conf. on Nucl. Eng., ASME, New York.
California Energy Commission. (2003). “Comparison of alternative cooling technologies for California power plants: Economics, environmental, and other tradeoffs.” PIER/EPRI Technical Report No. 500-02-079F, EPRI, Palo Alto, Calif., and California Energy Commission, Sacramento, Calif.
Forsberg, C. W. (2006). “Goals, requirements, and design implications for the advanced high-temperature reactor.” ICONE14-89305, Presented at the 14th Int. Conf. on Nucl. Eng. (ICONE-14), ASME, New York.
Forsberg, C. W., Peterson, P. F., and Pickard, P. (2004). “Maximizing temperatures of delivered heat from the advanced high-temperature reactor.” Proc., 2004 Int. Congress on Advances in Nuclear Power Plants (ICAPP ’04), Embedded International Topical Meeting 2004 American Nuclear Society Annual Meeting, American Nuclear Society, La Grange Park, Ill.
Forsberg, C. W., Peterson, P. F., and Williams, D. F. (2005). “Liquid-salt cooling for advanced high-temperature reactors.” Proc., 2005 Int. Congress on Advances in Nuclear Power Plants (ICAPP ’05), American Nuclear Society, La Grange Park, Ill.
Forsberg, C. W., Pickard, P. S., and Peterson, P. F. (2003). “Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity.” Nucl. Technol., 144, 289–302.
Fraas, A. P., and Savolainen, A. W. (1956). Design Rep. on the Aircraft Reactor Test, ORNL-2095, Oak Ridge National Laboratory, Oak Ridge, Tenn.
Ingersoll, D. T., et al. (2004). Status of preconceptual design of the advanced high-temperature reactor, ORNL/TM-2004/104, Oak Ridge National Laboratory, Oak Ridge, Tenn.
Kato, Y., Nitawaki, T., and Muto, Y. (2004). “Medium temperature carbon dioxide gas turbine reactor.” Nucl. Eng. Des., 230, 195–207.
LaBar, M. P. (2002). “The gas turbine-modular helium reactor: A promising option for near term deployment,” Proc., Int. Congress on Advanced Nuclear Power Plants, Embedded Topical American Nuclear Society 2002 Annual Meeting, GA-A23952, American Nuclear Society, La Grange Park, Ill.
Nucl. Appl. Technol. (1970) 8(2).
Nucl. Technol. (1977) 35(2).
Peterson, P. F. (2003). “Multiple-reheat Brayton cycles for nuclear power conversion with molten coolants.” Nucl. Technol., 144, 279–288.
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© 2006 American Society of Civil Engineers.
History
Received: Sep 7, 2005
Accepted: Sep 7, 2005
Published online: Dec 1, 2006
Published in print: Dec 2006
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