학술논문

THOREX PILOT PLANT: SYSTEM FOR CONCENTRATING SECOND URANIUM
Document Type
Technical Report
Author
Source
Other Information: Decl. May 4, 1960. Orig. Receipt Date: 31-DEC-60
Subject
CHEMISTRY ENRICHMENT
EVAPORATION
LEVELS
PLANNING
RADIATIONS
RECOVERY
REPROCESSING
SOLUTIONS
SOLVENT EXTRACTION
THOREX PROCESS
URANIUM 233
URANYL NITRATES
Language
English
Abstract
A system for concentrating uranyl nitrate solutions was designed and installed in the Thorex Pilot Plant. A total of 16,060 g of uranium was concentrated in the system in 68 batch runs. A total of 14,400 g total uranium (14.180 g U/sup 233/) was recovered as product suitable for shipment. Uranium loss to the evaporator condensate was 0.03% of ihe total uranium processed. The material balance across the system was 98.4%. The average concentration of uranium in the evaporator feed solution was 29 g/liter; the average concentration in the evaporated solution was 298 g U/liter and in the product solution was 199 g/liter. Radiation readings of bottles containing product solutions were taken with a hard-shell cutie pie immediately after each run, and these readings ranged from 35 to 1100 mr/hr. The radiation levels of the bottles of product solution shipped averaged 78 mr/hr. Bottles of product solution reading in excess of 300 mr/hr, maximum allowable for shipment. were reprocessed in the second-cycle solvent extraction system (Thorex) and reconcentrated. The products from seven runs had radiation levels in excess of 300 mr/hr at the time of concentration, or the activities had grown to that level by the time of shipment. The procedures used in the operation of the above system are described in detail. (auth)