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Tytuł artykułu

Performance comparison of PWR/EPR and steam generator with and without economizer

Treść / Zawartość
Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
The article presents a model of a steam generator based on mass and energy balance equations, heat transfer coefficients, criterion relations and Peclet’s law. The presented model was applied to a steam generator without and with an economizer for a PWR/EPR nuclear power plant. Based on the calculations, the steam pressure at the outlet of the steam generator without the economizer is 74.17 bar, and for the model with the economizer it is 77.2 bar. The pressure difference for these two variants, based on the calculations, was therefore 3 bar. Higher steam pressure at the outlet of the steam generator translates into a greater enthalpy drop in the turbine and greater power generated by the steam turbine and the efficiency of the entire nuclear power plant. Based on the economic calculations carried out for 60 years of operation of a nuclear power plant with four steam generators, the profit from the use of the economizer amounted to about PLN 0.6 billion.
Słowa kluczowe
Czasopismo
Rocznik
Tom
2
Strony
21--27
Opis fizyczny
Bibliogr. 13 poz., rys., tab.
Twórcy
  • Warsaw University of Technology, Faculty of Power and Aeronautical Engineering, Institute of Heat Engineering, Warsaw, Poland
Bibliografia
  • 1. Cengel Y.A., Boles: Thermodynamics: an Engineering Approach (4th Edn.). McGraw-Hill, New York 2002.
  • 2. Laskowski R., Smyk A., Jurkowski R., Ancé J., Wołowicz M., Uzunow N.: Selected aspects of the choice of live steam pressure in PWR nuclear power plant, Archives of Thermodynamics, Vol. 43(2022), No. 3, 85–109, DOI: 10.24425/ather.2022.143173.
  • 3. Review of design approaches of advanced pressurized LWRs. https://inis.iaea.org/collection/NCLCollectionStore/_Public/27/031/27031989.pdf?r=1 (accessed 30 March 2023).
  • 4. EPR Design Description. https://www.nrc.gov/docs/ML0522/ML052280170.pdf (accessed 30 March 2023).
  • 5. Wang C., Yan C., Wang J., Tian C., Yu S.: Parametric optimization of steam cycle in PWR nuclear power plant using improved genetic-simplex algorithm, Applied Thermal Engineering, Vol.125, 2017, pp. 830-845.
  • 6. Sayyaadi H., Sabzaligol T.: Various approaches in optimization of a typical pressurized water reactor power plant, Applied Energy 86 (2009) 1301–1310.
  • 7. Teyssedoua A., Dipamaa J., Hounkonnoua W., Aubé F.: Modeling and optimization of a nuclear power plant secondary loop, Nuclear Engineering and Design 240 (2010) 1403–1416.
  • 8. Laskowski R., Lewandowski J.: A simplified mathematical model of a U-tube steam generator under variable load conditions, Archives of Thermodynamics, 34(2013), 3, 75–88.
  • 9. EPR Brochure http://www.epr-reactor.co.uk/ssmod/liblocal/docs/EPR%20Interactive/Brochures/30070_EPR_52pages.pdf (accessed 30 March 2023).
  • 10. Jurkowski R.: EPR Circuit -,Overview, Framatome, December, 2019, materials from the lecture at Institute of Heat Engineering at Warsaw University of Technology.
  • 11. Nag P.K.: Power Plant Engineering, Tata McGraw-Hill Edu. New York 2002.
  • 12. Szargut J.: Thermodynamics, PWN, Warszawa 2000 (in Polish).
  • 13. Kiełkiewicz M.: Theory of nuclear reactors, PWN, Warszawa 1987.
Uwagi
Opracowanie rekordu ze środków MEiN, umowa nr SONP/SP/546092/2022 w ramach programu "Społeczna odpowiedzialność nauki" - moduł: Popularyzacja nauki i promocja sportu (2022-2023).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-ccb1cc65-abd8-4308-b0b0-a588719fcf13
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