Thermodynamic analysis of a generation IV SCWR nuclear power plant cycle

• Autorzy: Dzida M. , Frost J.
• Języki publikacji: EN

Abstrakty

EN

This article presents a flow and thermodynamic analysis of a Generation IV nuclear cycle. An SCWR (Supercritical water reactor) is a high temperature and high pressure reactor that uses water at a temperature above its thermodynamic critical point as the working fluid. The cycle used for the calculations consists of one interstage superheater and 7 regenerative heat exchangers. Division pressure was optimized in view of the cycle efficiency, and the possibility of using another pressure value that would be more beneficial due to the structure of the grid of blades was mentioned.

Słowa kluczowe

EN

nuclear reactors; steam turbines; thermodynamic cycle; SCWR reactor

PL

reaktory jądrowe; turbiny parowe; obiegi termodynamiczne; reaktory SCWR

• Wydawca: Faculty of Ocean Engineering and Ship Technology, Gdańsk University of Technology
• Czasopismo: Journal of Polish CIMAC
• Rocznik: 2014
• Tom: Vol. 9, no 1
• Strony: 17--24
• Opis fizyczny: Bibliogr. 5 poz., rys., tab., wykr.

Twórcy

autor

Dzida M.

• Gdańsk University of Technology Ul. Narutowicza 11/12, 80

autor

Frost J.

• Gdańsk University of Technology Ul. Narutowicza 11/12, 80

Bibliografia

• [1.] http://www.mg.gov.pl/ 24.05.2014
• [2.] Mikielewicz J., Mikielewicz D., Dziś i jutro technologii energetyki jądrowej - szanse i zagrożenia, Energetyka Jądrowa w Polsce, Wolters Kluwer Polska Sp. z.o.o, Warsaw 2012
• [3.] http://www.elektroonline.pl/ 24.05.2014
• [4.] http://www.inl.gov/ 24.05.2014
• [5.] Pawlik M., Strzelczyk F., Elektrownie WNT, Warsaw 2012