The purpose of this paper is to highlight the importance of the applied detailed 3-D fuel modeling in the highly heterogeneous, high flux MTR reactor BR2 for the accurate assessment of the reactor safety characteristics during the reactor operation. The combined MCNP&ORIGEN-S full-scale 3-D heterogeneous geometry model with detailed 3-D isotopic fuel profile in the whole core is used for the neutronics calculations. The effects of three burn up profiles on the reactivity variations are investigated: axial burn up profile in a fuel plate, radial in a fuel assembly and azimuth depletion profile in each axial segment of the annular fuel plates. The uncertainties in the maximum values of the heat flux due to different orientations of the fuel element in the core are estimated.
|Name||Research Reactor Fuel Management|
|Conference||2006 - RRFM - Research Reactor Fuel Management|
|Period||2006-04-30 → 2006-05-03|