Modeling of fuel performance and metallic fission product release behavior during HTTR normal operating conditions

摘要

The computer codes PANAMA and FRESCO developed at the Research Center Julich have been used for the prediction of fuel performance and fission product release behavior during the normal operation of the Japanese High-Temperature Engineering Test Reactor, HTTR. Basis for the calculations was the so-called 'Standard HTTR Operation Plan' with a nominal operation time of 660 efpd including a 110 efpd period with enhanced fuel Temperatures. Fuel performance model calculation with the PANAMA code have shown that for the temperature Distribution given, only a small additional failure fraction is expected.