101. Purification of Gaseous Emissions by C Removal During Reprocessing of Spent Uranium-Plutonium Nuclear Fuel.
- Author
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Yakunin, S., Ustinov, O., Shadrin, A., and Shudegova, O.
- Subjects
GAS purification ,PLUTONIUM as fuel ,URANIUM as fuel ,SPENT reactor fuels ,RADIATION trapping ,CALCIUM carbonate - Abstract
Methods for trapping the C in waste gases by means of a combined technology are examined. The wastes gases from pyrochemical production can be purified by removing C by passing the gases at rates to 5 m/h through a 0.5 m high layer of Ba(OH)·8HO granules in a 0.14 m in diameter apparatus after dilution with atmospheric air. The purification of the waste gases from hydrometallurgical production by removal of C (50 m/h) is best accomplished by passage through a 0.28 m in diameter packed tower with 2.7-4 m high packing irrigated by an alkali solution which is regenerated by means of calcium hydroxide. The waste gases from pyrochemical production can also be passed through a packed tower. In this case the C is fixed in insoluble calcium carbonate and is placed in a storage facility and subsequently buried. The proposed technologies make it possible to purify the waste gases formed during the reprocessing of spent uraniumplutonium nitride nuclear fuel in a reprocessing module used in an on-site nuclear fuel cycle by removing C to a level admissible for air in production enclosures. [ABSTRACT FROM AUTHOR]
- Published
- 2016
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