Journal of Radiation Safety and Measurement

Journal of Radiation Safety and Measurement

Management of potential radioactive wastes from fission molybdenum-99 production from low-enriched uranium target

Document Type : Original Article

Authors
Nafise Salek
Ali Yadollahi
Hamid Sepehrian
Reza Davarkhah
Javad Fasihi Ramandi
Mohsen Tabasi
Nuclear fuel cycle Research School, Nuclear Science and Technology Research Institute, P.O.BOX 14893-836, Tehran, Iran
10.22052/rsm.2024.253441.1036
Abstract
In this paper, we have tried to provide details about possible radioactive wastes produced in the fission molybdenum-99 production process using LEU uranium targets in the country and how to manage them throughout the production process. Potential solid, liquid, and gaseous wastes are a combination of low-level (LLW), and medium-level (ILW) wastes that contain enriched uranium and other fission products and actinides. Based on the results of radiation calculations and heat generated by the radionuclides in each waste package, it seems that no high-level waste (HLW) is generated from the 99Mo production facility, as this waste contains long-lived or alpha-emitting radionuclides with more activity of 400 Bq/g which their heat generation is not more than 2 kW/m3. The economic aspects of 99Mo-related waste management are important and can substantially influence the final price of 99Mo and by-products. In the fission 99Mo production process, the recovery of unburnt uranium is highly recommended, preferably the uranium should be segregated from the waste streams within the production facility.
Keywords
Molybdenum-99
Low-enriched uranium
Radiation calculations
Waste classification
Waste management
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