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Research Papers: Energy Systems Analysis

Thermodynamic Analysis of Power Generation Cycles With High-Temperature Gas-Cooled Nuclear Reactor and Additional Coolant Heating Up to 1600 °C

[+] Author and Article Information
Michał Dudek

Department of Fundamental Research in Energy
Engineering,
AGH—University of Science and Technology,
Kraków 30-059, Poland
e-mail: michald@agh.edu.pl

Zygmunt Kolenda

Department of Fundamental Research in Energy
Engineering,
AGH—University of Science and Technology,
Kraków 30-059, Poland
e-mail: kolenda@agh.edu.pl

Marek Jaszczur

Department of Fundamental Research in Energy
Engineering,
AGH—University of Science and Technology,
Kraków 30-059, Poland
e-mail: jaszczur@agh.edu.pl

Wojciech Stanek

Institute of Thermal Technology,
Silesian University of Technology,
Gliwice 44-100, Poland
e-mail: wojciech.stanek@polsl.pl

Contributed by the Advanced Energy Systems Division of ASME for publication in the JOURNAL OF ENERGY RESOURCES TECHNOLOGY. Manuscript received February 1, 2017; final manuscript received January 6, 2018; published online January 22, 2018. Assoc. Editor: Tatiana Morosuk.

J. Energy Resour. Technol 140(2), 020910 (Jan 22, 2018) (7 pages) Paper No: JERT-17-1053; doi: 10.1115/1.4038930 History: Received February 01, 2017; Revised January 06, 2018

Nuclear energy is one of the possibilities ensuring energy security, environmental protection, and high energy efficiency. Among many newest solutions, special attention is paid to the medium size high-temperature gas-cooled reactors (HTGR) with wide possible applications in electric energy production and district heating systems. Actual progress can be observed in the literature and especially in new projects. The maximum outlet temperature of helium as the reactor cooling gas is about 1000 °C which results in the relatively low energy efficiency of the cycle not greater than 40–45% in comparison to 55–60% of modern conventional power plants fueled by natural gas or coal. A significant increase of energy efficiency of HTGR cycles can be achieved with the increase of helium temperature from the nuclear reactor using additional coolant heating even up to 1600 °C in heat exchanger/gas burner located before gas turbine. In this paper, new solution with additional coolant heating is presented. Thermodynamic analysis of the proposed solution with a comparison to the classical HTGR cycle will be presented showing a significant increase of energy efficiency up to about 66%.

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References

Bae, S. J. , Lee, J. , Ahn, Y. , and Lee, J. I. , 2015, “ Preliminary Studies of Compact Brayton Cycle Performance for Small Modular High Temperature Gas-Cooled Reactor System,” Ann. Nucl. Energy, 75, pp. 11–19. [CrossRef]
Burns, E. M. , 2009, “ Next Generation Nuclear Plant–Emergency Planning Zone Definition at 400 Meters,” Westinghouse Electric Company LLC, Cranberry Township, PA, Report No. NGNP-LIC-GEN-RPT-L-00020. https://art.inl.gov/NGNP/Subcontractors%20Documents/Westinghouse/Next%20Generation%20Nuclear%20Plant-Emergency%20Planning%20Zone%20Definition%20at%20400%20Meters.pdf
Guven, U. , and Gurunadh, V. , 2011, “ Design of a Nuclear Power Plant With Gas Turbine Modular Helium Cooled Reactor,” J. Nucl. Eng. Technol., 1, pp. 1–15. http://www.academia.edu/1102981/Design_of_a_Nuclear_Power_Plant_with_Gas_Turbine_Modular_Helium_Cooled_Reactor
Marsden, B. J. , Fok, S. L. , and Hall, G. , 2003, “ High Temperature Gas-Cooled Reactor Core Design Future Material Consideration,” International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP), Kyoto, Japan, Sept. 15–19, Paper No. 1222. https://www.ipen.br/biblioteca/cd/genes4/2003/papers/1222-final.pdf
Ohashi, H. , Sato, H. , Goto, M. , Yan, X. , Sumita, J. , Tazawa, Y. , Nomoto, Y. , Aihara, J. , Inaba, Y. , Fukaya, Y. , Noguchi, H. , Imai, Y., and Tachibana, Y. , 2013, “ A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries,” Int. J. Nucl. Energy, 2013, p. 918567. [CrossRef]
RAHP, 2014, “ High Temperature Gas Cooled Reactor (HTGR) Developments in the Word Present Status and Future Plans March 2014,” Research Association of High Temperature Gas Cooled Reactor Plant, Tokyo, Japan, RAHP News Letter No. 13. https://www.iae.or.jp/htgr/pdf/05_newsletter/05_2/05_2_rahp_No13_201403_en.pdf
Fujimoto, N. , Tachibana, Y. , Sakaba, N. , Hino, R. , and Yu, S. , 2008, “ Information Exchange on HTGR and Nuclear Hydrogen Technology Between JAEA and INET in 2007,” Japan Atomic Energy Agency, Ibaraki, Japan, Report No. JAEA-REVIEW-2008-019. http://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?5013064&language=1
Stanek, W. , Szargut, J. , Kolenda, Z. , Czarnowska, L. , and Bury, T. , 2015, “ Thermo-Ecological Evaluation of Nuclear Power Plant Within the Whole Life Cycle,” Int. J. Thermodyn., 18(2), pp. 121–131. [CrossRef]
Gauthier, J. C. , Brinkmann, G. , Copsey, B. , and Lecomte, M. , 2006, “ Antares: The HTR/VHTR Project at Framatome ANP,” Nucl. Eng. Des., 236(5–6), pp. 526–533.
Kolenda, Z. , Hołda, A. , Jaszczur, M. , and Dudek, M. , 2014, “ Energy Analysis and Mathematical Model of Thermodynamic Cycle of High Temperature Nuclear Reactor to Electricity Production Without Carbon Dioxide Emissions,” Report for Project, The Development of High-Temperature Nuclear Reactors for Industrial Application HTRPL, University of Science and Technology in Cracow, Kraków, Poland, Internal University Report.
Behar, C. , 2014, “ Technology Roadmap Update for Generation IV Nuclear Energy Systems,” OECD Nuclear Energy Agency for the Generation IV International Forum, accessed Jan. 17, 2018, https://www.gen-4.org/gif/upload/docs/application/pdf/2014-03/gif-tru2014.pdf
Jaszczur, M. , Rosen, M. A. , Śliwa, T. , Dudek, M. , and Pieńkowski, L. , 2016, “ Hydrogen Production Using High Temperature Nuclear Reactors: Efficiency Analysis of a Combined Cycle,” Int. J. Hydrogen Energy, 41(19), pp. 7861–7871. [CrossRef]

Figures

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Fig. 1

HTR-50S (JAEA—Japan, 2012–2019) for cogeneration (power generation and district heating)

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Fig. 2

Areva HTR 600 MWth cycle

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Fig. 3

The classical cycle of electric energy production (N—power, Q—heat flux)

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Fig. 4

Extended cycle with additional helium heating (N—power, Q—heat flux)

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Fig. 5

Thermal efficiency, gas turbine power, steam turbine power, compressor demand, and exergy efficiency for standard and additional heating cycle

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