Currently, there are a number of Generation IV SuperCritical Water-cooled nuclear Reactor (SCWR) concepts under development worldwide. The main objectives for developing and utilizing SCWRs are: 1) Increase gross thermal efficiency of current Nuclear Power Plants (NPPs) from 30 – 35% to approximately 45 – 50%, and 2) Decrease capital and operational costs and, in doing so, decrease electrical-energy costs. SCW NPPs will have much higher operating parameters compared to current NPPs (i.e., steam pressures of about 25 MPa and steam outlet temperatures up to 625°C). Additionally, SCWRs will have a simplified flow circuit in which steam generators, steam dryers, steam separators, etc. will be eliminated. Furthermore, SCWRs operating at higher temperatures can facilitate an economical co-generation of hydrogen through thermo-chemical cycles (particularly, the copper-chlorine cycle) or direct high-temperature electrolysis. To decrease significantly the development costs of a SCW NPP, to increase its reliability, and to achieve similar high thermal efficiencies as the advanced fossil steam cycles it should be determined whether SCW NPPs can be designed with a steam-cycle arrangement that closely matches that of mature SuperCritical (SC) fossil-fired thermal power plants (including their SC-turbine technology). The state-of-the-art SC-steam cycles at fossil-fired power plants are designed with a single-steam reheat and regenerative feedwater heating. Due to that, they reach thermal steam-cycle efficiencies up to 54% (i.e., net plant efficiencies of up to 43% on a Higher Heating Value (HHV) Basis). This paper analyzes main parameters and performance in terms of thermal efficiency of a SCW NPP concept based on a direct regenerative steam cycle. To increase the thermal efficiency and to match current SC-turbine parameters, the cycle also includes a single steam-reheat stage. The cycle is comprised of: an SCWR, a SC turbine, which consists of one High-Pressure (HP) cylinder, one Intermediate-Pressure (IP) cylinder and two Low-Pressure (LP) cylinders, one deaerator, ten feedwater heaters, and pumps. Since this option includes a “nuclear” steam-reheat stage, the SCWR is based on a pressure-tube design. A thermal-performance simulation reveals that the overall thermal efficiency is approximately 50%.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4354-3
PROCEEDINGS PAPER
Thermodynamic Considerations for a Single-Reheat Cycle SCWR Available to Purchase
M. C. Naidin,
M. C. Naidin
University of Ontario Institute of Technology, Oshawa, ON, Canada
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R. Monichan,
R. Monichan
University of Ontario Institute of Technology, Oshawa, ON, Canada
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U. Zirn,
U. Zirn
Hitachi Power Systems America, Ltd., Basking Ridge, NJ
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K. Gabriel,
K. Gabriel
University of Ontario Institute of Technology, Oshawa, ON, Canada
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I. Pioro
I. Pioro
University of Ontario Institute of Technology, Oshawa, ON, Canada
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M. C. Naidin
University of Ontario Institute of Technology, Oshawa, ON, Canada
R. Monichan
University of Ontario Institute of Technology, Oshawa, ON, Canada
U. Zirn
Hitachi Power Systems America, Ltd., Basking Ridge, NJ
K. Gabriel
University of Ontario Institute of Technology, Oshawa, ON, Canada
I. Pioro
University of Ontario Institute of Technology, Oshawa, ON, Canada
Paper No:
ICONE17-75984, pp. 713-720; 8 pages
Published Online:
February 25, 2010
Citation
Naidin, MC, Monichan, R, Zirn, U, Gabriel, K, & Pioro, I. "Thermodynamic Considerations for a Single-Reheat Cycle SCWR." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition. Brussels, Belgium. July 12–16, 2009. pp. 713-720. ASME. https://doi.org/10.1115/ICONE17-75984
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