Effluent polishing of ammoniacal supernatant containing Uranium-233 using TBP impregnated XAD
Creators
- 1. Fuel Reprocessing Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
233U is one of the key fissile materials in India's three stage nuclear program. 233U is produced by the irradiation of Thoria rods in research reactor and in power reactor. In Uranium Thorium Separation Facility (UTSF) Trombay, 233U is separated from thoria rods irradiated in research reactors where as 233U from Thoria rods irradiated from power reactors are separated in Power Reactor Thoria Reprocessing Facility (PRTRF). In the UTSF laboratory the product uranyl nitrate solution was subjected to sequential precipitation technique to separate Uranium from the contamination of Thorium and Iron. Ammoniacal supernatant generated during the sequential precipitation where first Thorium is precipitated as oxalate followed by Uranium as ADU contains milligram level of 233U. To recover the 233U, first the solution was acidified and adjusted the acidity to 2 M and treated with known excess of saturated KMnO4 to destruct oxalate ions then the excess KMnO4 was treated with H2O2. After keeping this oxalate free supernatant, overnight for the removal of nascent oxygen. Then the solution was passed through a column containing TBP impregnated XAD to load uranium. Loading effluent containing microgram level of Uranium was disposed through RSMS. Initial experiment was carried out with 5 ml solution of 233U (conc 1.6 g/l) was passed through a glass column containing a pre-conditioned TBP-XAD bed of 13 cm height and 1.0 cm dia containing 10 g of TBP-XAD. The flow rate was maintained at 0.3 ml per min (18 ml per hour). Loading effluent was collected at an interval of 3 min and analysed, after sufficient displacement of conditioned acid
Additional details
Publishing Information
- Publisher
- Indian Institute of Technology Guwahati
- Imprint Place
- Guwahati (India)
- Imprint Title
- Proceedings of the seventh DAE-BRNS biennial symposium on emerging trends in separation science and technology
- Imprint Pagination
- 280 p.
- Journal Page Range
- p. 110
Conference
- Title
- 7. DAE-BRNS biennial symposium on emerging trends in separation science and technology
- Acronym
- SESTEC-2016
- Dates
- 17-20 May 2016
- Place
- Guwahati (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 47086239
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADU; MATERIALS RECOVERY; TBP; THORIUM OXIDES; URANIUM 233
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AMMONIUM COMPOUNDS; AMMONIUM URANATES; BUTYL PHOSPHATES; CHALCOGENIDES; ESTERS; EVEN-ODD NUCLEI; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOTOPES; MANAGEMENT; NEON 24 DECAY RADIOISOTOPES; NUCLEI; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PHOSPHORIC ACID ESTERS; PROCESSING; RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; THORIUM COMPOUNDS; URANATES; URANIUM COMPOUNDS; URANIUM ISOTOPES; WASTE MANAGEMENT; WASTE PROCESSING; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 2 refs., 1 tab.