Thermal analysis of heat and power plant with high temperature reactor and intermediate steam cycle

• Autorzy: Fic A. , Składzień J. , Gabriel M.

Identyfikatory

DOI

10.1515/aoter-2015-0001

• Języki publikacji: EN

Abstrakty

EN

Thermal analysis of a heat and power plant with a high temperature gas cooled nuclear reactor is presented. The main aim of the considered system is to supply a technological process with the heat at suitably high temperature level. The considered unit is also used to produce electricity. The high temperature helium cooled nuclear reactor is the primary heat source in the system, which consists of: the reactor cooling cycle, the steam cycle and the gas heat pump cycle. Helium used as a carrier in the first cycle (classic Brayton cycle), which includes the reactor, delivers heat in a steam generator to produce superheated steam with required parameters of the intermediate cycle. The intermediate cycle is provided to transport energy from the reactor installation to the process installation requiring a high temperature heat. The distance between reactor and the process installation is assumed short and negligable, or alternatively equal to 1 km in the analysis. The system is also equipped with a high temperature argon heat pump to obtain the temperature level of a heat carrier required by a high temperature process. Thus, the steam of the intermediate cycle supplies a lower heat exchanger of the heat pump, a process heat exchanger at the medium temperature level and a classical steam turbine system (Rankine cycle). The main purpose of the research was to evaluate the effectiveness of the system considered and to assess whether such a three cycle cogeneration system is reasonable. Multivariant calculations have been carried out employing the developed mathematical model. The results have been presented in a form of the energy efficiency and exergy efficiency of the system as a function of the temperature drop in the high temperature process heat exchanger and the reactor pressure.

Słowa kluczowe

EN

cogeneration system; high-temperature reactor; exergy analysis; gas heat pumps; numerical simulation

PL

system kogeneracyjny; reaktor wysokotemperaturowy; analiza egzergii; gazowe pompy ciepła; symulacja numeryczna

• Wydawca: Wydawnictwo Instytutu Maszyn Przepływowych PAN ; Komitet Termodynamiki i Spalania PAN
• Czasopismo: Archives of Thermodynamics
• Rocznik: 2015
• Tom: Vol. 36, no. 1
• Strony: 3--18
• Opis fizyczny: Bibliogr. 14 poz., rys., wz., wykr.

Twórcy

autor

Fic A.

• Silesian University of Technology, Institute of Thermal Technology, Konarskiego 22, 44-100 Gliwice, Poland

autor

Składzień J.

• Silesian University of Technology, Institute of Thermal Technology, Konarskiego 22, 44-100 Gliwice, Poland

autor

Gabriel M.

• Silesian University of Technology, Institute of Thermal Technology, Konarskiego 22, 44-100 Gliwice, Poland

Bibliografia

• [1] Mikielewicz D., Mikielewicz J.: Utilisation of bleed steam heat to increase the upper heat source temperature in low-temperature ORC. Arch. Thermodyn. 32(2011), 3, 57–71.
• [2] Chmielniak T., Lepszy S., Czaja D.: The use of air-bottoming cycle as a heat source for the carbon dioxide capture installation of a coal-fired power unit. Arch. Thermodyn. 32(2011), 3, 89–103.
• [3] Celiński Z., Strupczewski A.: Fundamentals of Nuclear Power, PWN, Warsaw 1984 (in Polish).
• [4] Yildis B., Kazimi M.S.: Efficiency of hydrogen production systems using alternative nuclear energy technologies. Int. J. Hydrogen Energ. 31(2006), 77–92.
• [5] Yanhui X., Huaiming J., Daxin Z.: HTGR Process Heat Application Study. Tsinghua Science and Technology 10/19(1996), 1, 40–44, ISSN 1007-2024.
• [6] Kurh R.: HTR’s role in process heat applications. Nucl. Eng. Des. 238(2008), 3013–3017.
• [7] Marmier A., Fütterer M.A.: Nuclear powered heat pumps for near-term process heat applications. Nuc. Eng. Des. 238(2008), 2272–2284.
• [8] Hanuszkiewicz-Drapała M., Jędrzejowski J.: Thermodynamic analysis of a cogeneration system. J. Power Technologies, papers.itc.pw.edu.pl, 2015.
• [9] EBSILON Professional Documentation, https://www.steag-systemtechnologies.com
• [10] Rietschel H., Reiss W.: Heiz und Luftungstechnik, 14th Edn. Springer Verlag, Berlin 1963.
• [11] Szargut J., Morris D.R., Steward F.R.: Exergy Analysis of Thermal, Chemical, and Metallurgical Processes. Hemisphere Publishing Corporation, Springer- Verlag, Berlin 1988.
• [12] Tani F., Haldi P. A., Favrat D.: Exergy-Based Comparison of the Nuclear Fuel Cycles of Light Water and Generation IV Rectors, http://moodle.epfl.ch/pluginfile.php/1092351/mod_resource/content/0/exergy_-analysis_ucycle.pdf
• [13] http://www.fchart.com/ees/
• [14] List Reference Fluid Thermodynamic and Transport Properties Database (REFPROP), Ver. 9.1. National Institute of Standatrds and technology, Bouler 2013.

Uwagi

EN

This work was supported by the National Centre for Research and Development, Poland, under the strategic project Technologies Supporting Development of Safe Nuclear Power Engineering, task 1: ‘Development of high temperature reactors for industrial purposes (HTRPL)’, grant number SP/J/1/166183/12.