High-Temperature Liquid-Fluoride-Salt Closed-Brayton-Cycle Solar Power Towers

Author:

Forsberg Charles W.1,Peterson Per F.2,Zhao Haihua3

Affiliation:

1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6165

2. University of California, Berkeley, 4153 Etcheverry, Berkeley, CA 94720-1730

3. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415

Abstract

Liquid-fluoride-salt heat transfer fluids are proposed to raise the heat-to-electricity efficiencies of solar power towers to about 50%. The liquid salt would deliver heat from the solar furnace at temperatures between 700°C and 850°C to a closed multireheat Brayton power cycle using nitrogen or helium as the working fluid. During the daytime, hot salt may also be used to heat graphite, which would then be used as a heat storage medium to make night-time operations possible. Graphite is a low-cost high-heat-capacity solid that is chemically compatible with liquid fluoride salts at high temperatures. About half the cost of a solar power tower is associated with the mirrors that focus light on the receiver, and less than one-third is associated with the power cycle and heat storage. Consequently, increasing the efficiency by 20–30% has the potential for major reductions in the cost of electricity. Peak temperatures and efficiencies of current designs of power towers are restricted by (1) the use of liquid nitrate salts that decompose at high temperatures and (2) steam cycles in which corrosion limits peak temperature. The liquid-fluoride-salt technology and closed Brayton power cycles are being developed for high-temperature nuclear reactors. These developments may provide the technology and industrial basis for an advanced solar power tower.

Publisher

ASME International

Subject

Energy Engineering and Power Technology,Renewable Energy, Sustainability and the Environment

Reference17 articles.

1. Sargent & Lundy LLC Consulting Group, 2003, “Assessment of Parabolic Trough and Power Tower Solar Technology Cost and Performance Forecasts,” SL-5641, Chicago, Il.

2. Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants;Peterson;Nucl. Technol.

3. U. S. Department of Energy Nuclear Energy Research Advisory Committee and the Generation IV International Forum, 2002, “A Technology Roadmap for Generation IV Nuclear Energy Systems,” GIF-002-00, www.ne.doe.gov.

4. MacDonald, P. E. et al. , 2003, “NGNP Preliminary Point Design—Results of the Initial Neutronics and Thermal Hydraulic Assessments,” INEEL∕EXT-03-00870 Rev 1, Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

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