Preliminary Study on Enhancing the Performance of Thorium Based Fuel Inserted in Improved Candu C37M Bundle

The aims of this study was to assess the behavior of innovative C37M (CANDU 37 Modified) nuclear fuel bundle project with 37 elements, containing mixed oxides of Thorium and Uranium fuel by means of ELESIM-TORIU computer code developed in Fuel Performances Evaluation Department from RATEN ICN Pitesti, based on the original ELESIM computer code. Fuel performance analysis suggested by the evaluation of temperature sensitive parameters such as: fission gas release, internal pressure and plastic sheath strain, etc., indicates a slight elevation of nearly 3%, due to a correspondent elevation of linear power output. Beginning from this result, the increase of discharged burnup and a more efficient utilization of fissile material was revealed, proving the efficiency increase of this fuel bundle project.