engleski

Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6.0 Code Package

The gas-cooled fast reactor is one of the reactor concepts selected by the Generation IV International Forum for the next generation of innovative nuclear energy systems. Several fuel design concepts (plates, rod pins, and pebbles) are being investigated. In this paper we modeled depletion of a pin-type fuel (Uranium and Plutonium carbide fuel, Silicon carbide clad) using the SCALE (Standardized Computer Analysis for Licensing Evaluation) code package, developed at Oak Ridge National Laboratory. The TRITON6 control module of the SCALE code package, which includes KENO-VI 3D Monte Carlo transport code and ORIGEN-S code, was used to support three-dimensional fuel depletion. Calculations were made for an equivalent homogeneous model of fuel rods in a hexagonal mesh assembly. Total reflections conditions were applied on the six lateral faces and the two axial faces of the assembly. The infinite multiplication factors as function of the irradiation time obtained by SCALE6 calculations were compared with the results of MCNPX and TRIPOLI-4 modeling. The comparison showed that results obtained by our modeling are very similar to results obtained by MCNPX and TRIPOLI-4. TSUNAMI-3D (Tools for Sensitivity and Uncertainty Analysis Methodology Implementation in Three Dimensions) control module of SCALE was used to determine the sensitivity coefficients and uncertainty of the calculated k-infinity values.

pin-type GFR fuel assembly; SCALE6.0 code package; TRITON6 control module; TSUNAMI-3D; sensitivity analysis

nije evidentirano