Accident tolerant fuels to replace uranium dioxide

Autor: A B Kruglov, V B Kruglov, A Z Alhmoud
Rok vydání: 2020
Předmět:
Zdroj: Journal of Physics: Conference Series. 1679:022063
ISSN: 1742-6596
1742-6588
Popis: The thermal conductivities for the traditional fuel UO2 and for the Accident Tolerant Fuel (uranium Molybdenum alloy, U-10Mo and uranium silicide, U3Si2) are calculated and compared. Then the temperature distributions on these core reactor, namely on the surface of the rod and in the center line of the rod were determined. The calculation is carried out using MATHCAD program. The calculations showed enhancement of thermal conductivity of the Accident Tolerant Fuel as they increased linearly with increasing temperature, and reduction of their center line temperatures of the rods. Beside, their steep thermal gradient, which may reduce the induced heat stresses in the core of the reactor.
Databáze: OpenAIRE