Technical summary: Nuclear Waste Vitrification Project
Earl J. Wheelwright, William J. Bjorklund, Larry M. Browne, Garry H. Bryan, Langdon K. Holton, Everett R. Irish, Dan H. Siemens
Abstract
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Earl J. Wheelwright, William J. Bjorklund, Larry M. Browne, Garry H. Bryan, Langdon K. Holton, Everett R. Irish, Dan H. Siemens
Abstract
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Six PWR fuel assemblies, containing 2.3 metric tons uranium from Point Beach, have been processed by a conventional Purex-type process. U and other chemicals were added to the dilute HLLW, and the waste was then vitrified to produce two canisters of glass. The on-stream efficiency of the waste preparation facility exceeded 90% for the first 3 weeks; the overall average was 62%. The only processing difficulty in the vitrification facility was a partial failure in the spray calciner nozzle. The Pu byproduct of waste preparation was purified by ion exchange and calcined to oxide; one can of oxide ruptured due to self-heating. 27 figures, 16 tables. (DLC)
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Six PWR fuel assemblies, containing 2.3 metric tons uranium from Point Beach, have been processed by a conventional Purex-type process. U and other chemicals were added to the dilute HLLW, and the waste was then vitrified to produce two canisters of glass. The on-stream efficiency of the waste preparation facility exceeded 90% for the first 3 weeks; the overall average was 62%. The only processing difficulty in the vitrification facility was a partial failure in the spray calciner nozzle. The Pu byproduct of waste preparation was purified by ion exchange and calcined to oxide; one can of oxide ruptured due to self-heating. 27 figures, 16 tables. (DLC)
Key concepts: Vitrification, Radioactive waste, Waste management, Environmental science, Engineering, Physics, Nuclear physics