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Method for enhanced control of radioiodine in the production of fission product molybdenum 99

Patent ·
OSTI ID:6005756
A method is disclosed for controlling the release of radioiodine produced by the fission of uranium 235 during the process for the production of molybdenum 99. In the process for producing molybdenum 99, an aluminum-uranium alloyed target is irradiated with a neutron flux to bring about fission of the uranium 235 producing molybdenum 99, radioiodine and other fission byproducts. The method herein comprises reacting the irradiated target with a caustic solution. A reactive silver is then mixed with the caustic solution in an amount sufficient to react with substantially all of the radioiodine present in the caustic solution thereupon forming a silver precipitate of radioiodine. The precipitate formed is then separated from the caustic solution resulting in a substantially radioiodine-free caustic solution containing molybdenum 99.
Assignee:
General Electric Co
Patent Number(s):
US 4284472
OSTI ID:
6005756
Country of Publication:
United States
Language:
English

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