Article ID Journal Published Year Pages File Type
1729908 Annals of Nuclear Energy 2008 12 Pages PDF
Abstract
The results of LOFA and RIA demonstrate the safety features of IEA-R1 under the investigated conditions. In both cases the thermal hydraulic design limits have not been exceeded. However, for the RIA case the maximum clad temperature exceeds the limit of 95 °C being chosen as operation criteria for limiting corrosion on the surface of the fuel elements.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Preview
Simulation of LOFA and RIA for the IEA-R1 research reactor using the code MERSAT
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