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
AGH—University of Science and Technology,
Kraków 30-059, Poland
e-mail: michald@agh.edu.pl

Zygmunt Kolenda

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

Marek Jaszczur

Department of Fundamental Research in Energy
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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Grahic Jump Location
Fig. 1

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

Grahic Jump Location
Fig. 2

Areva HTR 600 MWth cycle

Grahic Jump Location
Fig. 3

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

Grahic Jump Location
Fig. 4

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

Grahic Jump Location
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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