[en] The Fuel Rod Analysis Program (FRAP-S3) is a fairly comprehensive computer code that is developed for the analysis of light water reactor fuel elements during steady-state operation. However, the code predicts an increase in the fuel radial temperature distribution with an increase in the fuel density, which is contrary to experiments. A simple modification of the code was used where the thermal conductivity is treated as porosity independent in the inner iteration loops of the program. The resulting temperature profile is corrected for the effects of porosity after it has converged. The modified code shows good agreement with the IFA-11 series of experiments using the Halden Boiling Water Reactor in Sweden. 7 refs