Demonstration of the iodine and NO/sub x/ removal systems in the Oak Ridge National Laboratory integrated equipment test facility
This report summarizes the findings from three sets of experiments on iodine and NO/sub x/ removal performance using dual downdraft condensers in the dissolver off-gas line. The initial experiments were conducted in the laboratory using glassware in proof-of-principle tests. Two additional sets of condenser experiments were conducted using equipment prototyical for a 0.5-t/d plant in the Integrated Equipment Test (IET) facility at the Oak Ridge National Laboratory. This report also describes the NO/sub x/ removal performance of a packed scrubber in the IET during the dissolution of depleted uranium oxides. The overall iodine pass-through efficiency of the condensers in the IET was high as desired. Removal efficiencies ranged from only 0.35 to 6.29%, indicating that the bulk of the iodine in the off-gas will be transferred on through the condensers to the iodox process for final disposal rather than recycled to the dissolver. The optimum operating temperature for the first condenser was in the range of 50 to 70/sup 0/C, with the temperature of the second condenser held near 20/sup 0/C. The NO/sub x/ removal performance of the combined dual condensers and packed scrubber resulted in effluent off-gas stream NO/sub x/ compositions of approx.0.4 to 1.0%, which are acceptable levels for the iodox process. The NO/sub x/ removal efficiency of the condensers ranged from approx.5 to 58%, but was generally around 20%. The removal efficiency of the packed tower scrubber was observed to be in the range of 40 to 60%. The NO/sub x/ removal performance of the condensers tended to complement the performance of the scrubber in that the condenser removal afficiency was high when the scrubber efficiency was low and vice versa.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6984703
- Report Number(s):
- ORNL/TM-10261; ON: DE87007884
- Country of Publication:
- United States
- Language:
- English
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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