Temperature transients induced by beam interruptions of different duration in a lead-bismuth-cooled and MOX-fuelled experimental ADS are investigated as a computational benchmark problem. This second phase of calculations aims to investigate the impact on the transient results and uncertainties of different fuel power density conditions. Temperature variations are investigated assuming fresh fuel conditions, four different fuel power densities and two interruption durations. The results provided by the nine participants are presented and compared in this final report. In addition, uncertainty components due to the different assumptions on model and data recommended in the benchmark specification is evaluated by means of the sensitivity studies carried out by some participants as supplementary contributions.
|Publisher||Nuclear Energy Agency|