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• W2170919052 abstract "The core design of a pebble-bed type Very High Temperature Reactor (VHTR) is optimized, aiming for an increase of the coolant outlet temperature to 1000 C, while retaining its inherent safety features. The VHTR has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. The high coolant outlet temperature results in a high plant efficiency and would allow for the coupling with a hydrogen production plant. However, the resulting increase in the peak fuel temperature could be detrimental for the fuel integrity. The fuel temperature during normal operation and accident scenarios has been investigated for a reference VHTR design by coupling computer codes that model the neutronics and the thermal-hydraulics of the core. Code validation has been performed using steady state and dynamic experiments of the HTR-10 and AVR reactors. The fuel temperature determines the mechanical stresses in the fuel coating layers, which form the containment of the fission products. The coating stresses and the resulting failure probability have been analyzed for the desired fuel temperatures in the reference design. It was found that an increase in the operating temperature would be allowable with respect to the fuel failure probability during normal operation. However, the high peak temperatures during accident scenarios, i.e. a Depressurized Loss Of Forced Cooling incident, calls for an improved design. Alternative core designs that use an optimized pebble (re)loading pattern and/or a modification of the coolant flow direction can be operated at lower fuel temperatures, thereby increasing the safety margins of the coating stresses." @default.
• W2170919052 created "2016-06-24" @default.
• W2170919052 creator A5080110451 @default.
• W2170919052 date "2009-01-15" @default.
• W2170919052 modified "2023-09-27" @default.
• W2170919052 title "Optimized Core Design and Fuel Management of a Pebble-Bed Type Nuclear Reactor" @default.
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• W2170919052 hasPublicationYear "2009" @default.
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