Significance of dose estimation and radiological data analysis in safe management of high active spent resins

High-activity resin hoppers from the Spent Fuel Storage Facility are fluidized and immobilized with a specific cement matrix in the Resin Fixation Facility before disposal in suitable engineered modules at the Near Surface Disposal Facility. Potential exposure rates at various locations within the plant were estimated, using standard codes, prior to radio-active operations. The estimation was essential to implement required radiological safety measures and protocols during actual radioactive operations in accordance with the as low as reasonably achievable (ALARA) principle. The dose estimation highlighted possible hot spots and required radiological safety protocols for safe operations. The estimated radiation levels correlated well with measured radiation levels during actual radioactive operations involving fluidization and immobilization of different levels of 137 Cs total activity, namely 14 Ci and 40 Ci, with an accuracy within 80%. This study demonstrated the effectiveness of the radiation field estimation tool and implemented safety measures in ensuring radiological safety for radiological workers following the ALARA principle.