[en] COMETHE-IIIJ, a mechanistic fuel performance modeling code, has been used to predict the fuel centerline temperatures in eighteen highly enriched BWR-6 type rods which were irradiated in assemblies IFA-431, IFA-432, and IFA-513 at the Halden Boiling Water Reactor. Several figures of merit have been used to compare the predicted values to temperatures measured with in-fuel thermocouples. The comparisons suggest that a COMETHE simulation of commercial light water reactor fuel will, on the average, tend to slightly overpredict fuel center line temperatures. The overall mean error was on the order of + 10⁰C, with a standard deviation on the order of 75⁰C