The irradiation test of Inert-Matrix Fuel in comparison to uranium plutonium mixed oxide fuel at the Halden Reactor

Conservative modelling for pin layout shows that the relatively low thermal conductivity of Inert-Matrix Fuel (IMF) causes higher temperatures and the refore higher fission gas release than in uranium plutonium mixed oxide (MO X). According to neutronic calculations, performance differences will also arise from different evolutions of the respective radial power and burnup d istributions. Modelling of these effects as well as a similar to 10% greate r production of Xe in the thermal spectrum of the Halden reactor is well wi thin the capabilities of appropriate codes. Some of the data and models use d for the pre-calculations are preliminary and will be revised after the fi rst experimental data have become available. (C) 2001 Published by Elsevier Science Ltd. All rights reserved.