MOX and UOX Fuel Melt Margin for European Pressurized Reactor

  • Patryk Oskar Stręciwilk Warsaw University of Technology, Faculty of Power and Aeronautical Engineering, Institute of Heat Engineering, ul. Nowowiejska 21/25, 00-665 Warszawa, Poland
  • Piotr Darnowski Warsaw University of Technology, Faculty of Power and Aeronautical Engineering, Institute of Heat Engineering, ul. Nowowiejska 21/25, 00-665 Warszawa, Poland
  • Adam Dominiak Warsaw University of Technology, Faculty of Power and Aeronautical Engineering, Institute of Heat Engineering, ul. Nowowiejska 21/25, 00-665 Warszawa, Poland
  • Roman Domański Warsaw University of Technology, Faculty of Power and Aeronautical Engineering, Institute of Heat Engineering, ul. Nowowiejska 21/25, 00-665 Warszawa, Poland

Abstract

Safety of Nuclear Power Plants (NPP) is the most important issue during its design and maintenance. Crucial area is nuclear isle where irradiated elements occur. During severe accidents in nuclear reactor core very dangerous is possibility of fuel melt which can lead to release of enormous amounts of radioactive elements. Nowadays Uranium Oxide fuels (UOX) as well as Mixed Oxides fuels (MOX) is under consideration for operating existing and planned NPPs. In this paper prepared Thermal-Hydraulics (TH) model and reliable thermal conductivity of UOX and MOX fuels relations are used for the margin to melt for UOX and MOX fuels calculations. This evaluation is performed for European Pressurized Reactor (EPR) geometry and thermophysical parameters.
Published
2013-08-06
How to Cite
STRĘCIWILK, Patryk Oskar et al. MOX and UOX Fuel Melt Margin for European Pressurized Reactor. Journal of Power Technologies, [S.l.], v. 93, n. 3, p. 169--177, aug. 2013. ISSN 2083-4195. Available at: <https://papers.itc.pw.edu.pl/index.php/JPT/article/view/434>. Date accessed: 22 dec. 2024.
Citation Formats
Issue
Vol 93 No 3 (2013)
Section
Nuclear Power

Keywords

fuel melt, nuclear fuel, thermal-hydraulics model
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