Demonstration of the UNEX Process for the Simultaneous Separation of Cesium, Strontium, and the Actinides from Actual INEEL Tank Waste
- Idaho National Engineering and Environmental Laboratory
- INEEL
- V. G. Khlopin Radium Institute
- MAYAK Production Association
A universal solvent extraction (UNEX) process for the simultaneous separation of cesium, strontium, and the actinides from actual radioactive acidic tank waste was demonstrated at the Idaho National Engineering and Environmental Laboratory. The waste solution used in the countercurrent flowsheet demonstration was obtained from tank WM-185. The UNEX process uses a tertiary solvent containing 0.08 M chlorinated cobalt dicarbollide, 0.5% polyethylene glycol-400 (PEG-400), and 0.02 M diphenyl-N,N-dibutylcarbamoyl phosphine oxide (Ph2Bu2CMPO) in a diluent consisting of phenyltrifluoromethyl sulfone (FS-13). The countercurrent flowsheet demonstration was performed in a shielded cell facility using 24 stages of 2-cm diameter centrifugal contactors. Removal efficiencies of 99.4%, 99.995%, and 99.96% were obtained for 137Cs, 90Sr, and total alpha, respectively. This is sufficient to reduce the activities of 137Cs, 90Sr, and actinides in the WM-185 waste to below NRC Class A LLW requirement s. Flooding and/or precipitate formation were not observed during testing. Significant amounts of the Zr (87%), Ba (>99%), Pb (98.8%), Fe (8%), Ca (10%), Mo (32%), and K (28%) were also removed from the feed with the universal solvent extraction flowsheet. 99Tc, Al, Hg, and Na were essentially inextractable (<1% extracted).
- Research Organization:
- Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (US)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM) (US)
- DOE Contract Number:
- AC07-99ID13727
- OSTI ID:
- 774229
- Report Number(s):
- INEEL/EXT-99-00954
- Country of Publication:
- United States
- Language:
- English
Similar Records
Demonstration of the UNEX Process for the Simultaneous Separation of Cesium, Strontium, and the Actinides from Actual INEEL Sodium-Bearing Waste
The Universal Solvent Exchange (UNEX) Process II: Flowsheet Development & Demonstration of the UNEX Process for the Separation of Cesium, Strontium, and Actinides from Actual Acidic Radioactive Waste
Universal Solent Extraction (UNEX) Flowsheet Testing of the Removal of Cesium, Strontium, and Actinide Elements from Radioactive, Acidic Dissolved Calcine Waste
Technical Report
·
Sun Oct 31 23:00:00 EST 1999
·
OSTI ID:911483
The Universal Solvent Exchange (UNEX) Process II: Flowsheet Development & Demonstration of the UNEX Process for the Separation of Cesium, Strontium, and Actinides from Actual Acidic Radioactive Waste
Journal Article
·
Sun Dec 31 23:00:00 EST 2000
· Solvent Extraction and Ion Exchange
·
OSTI ID:912115
Universal Solent Extraction (UNEX) Flowsheet Testing of the Removal of Cesium, Strontium, and Actinide Elements from Radioactive, Acidic Dissolved Calcine Waste
Journal Article
·
Mon Jul 01 00:00:00 EDT 2002
· Solvent Extraction and Ion Exchange (USA)
·
OSTI ID:912043