CESIUM REMOVAL

Cesium extractant BOBCalixC6 was invented by Oak Ridge National Lab for the removal of cesium from aqueous salt feedstocks. Cs-7SB modifier improves the solubility of BOBCalixC6 in the formulated solvent system, and increases its effectiveness in capturing cesium ions. They are key components for Caustic-Side Solvent Extraction (CSSX)^{a, b} and Fission-Product Extraction (FPEX)^c processes. The Caustic-Side Solvent Extraction (CSSX) process has been demonstrated in plant-scale operations at the US Department of Energy’s Savannah River Site^d,e.

BEHBCalixC6 is a next-generation cesium extractant with superior solubility properties and greatly improved efficiency^f. It can process higher-curie feeds and accommodate streams with heavier loadings of potassium.

(a) B.A. Moyer, et al. (2001) “Calixarene crown ether solvent composition and use thereof for extraction of cesium from alkaline waste solutions”. US Patent 6,174,503.

(b) L.H. Delmau, et al. (2002) “Caustic-Side Solvent Extraction: chemical and physical properties of the optimized solvent” Oak Ridge National Lab Report ORNL/TM-2002/190.

(c) J.Law, et al. (2008) “Simultaneous separation of cesium and strontium from spent nuclear fuel using the Fission-Product Extraction process”. Solvent Extraction: Fundamentals to Industrial Applications: Proceedings of ISEC 2008 International Solvent Extraction Conference, Vol. 1, 659-664.

(d) M.R.Poirier, et al.(2008) “Full-scale testing of a Caustic Side Solvent Extraction system to remove cesium from Savannah River site radioactive waste”. Separation Science and Technology, 43:2797-2813.

(e) E.A. Brass et al. (2008) “First plant-scale operation of Caustic-Side Solvent Extraction process for removal of cesium at the Savannah River site”. Presentation at 18th International Solvent Extraction Conference, Tucson, Arizona, September 15-19, 2008.

(f) L.H. Delmau, et al.(2009) “Alternatives to nitric acid striping in the Caustic-Side Solvent Extraction (CSSX) process for cesium removal from alkaline high-level waste”. Solvent Extraction and Ion Exchange, 27:172-198.

Phenyl trifluoromethyl sulfone (FS-13) is used as diluent or process solvent in nuclear applications, such as the UNEX process^a, the HCCD-PEG process ^b,c, and the separation of minor actinides from lanthanides^d .

(a) E.K.Rzhekhina, et al. (2007) “Processing of spent solvent of the UNEX process”. Radiochemistry, 49(5): 493-498.

(b) R.S. Herbst et al. (2008) “PEG-400 Partitioning in the HCCD/PEG process for Cs and Sr recovery”. Separation Science and Technology, 43:2557-2571.

(c) R.S. Herbst et al. (2008) “Fundamental chemistry of cesium extraction from acidic media by HCCD in FS-13” Solvent Extraction and Ion Exchange, 26(2):163-174.

(d) D.R. Peterman, et al. (2008) “Separation of minor actinides from lanthanides by dithiophosphinic acid extractants”. Solvent Extraction: Fundamentals to Industrial Applications: Proceedings of ISEC 2008 International Solvent Extraction Conference, Vol. 2, 1427-1432.

CMPO is used as an actinides extractant in TRUEX process^a.

(a) R.C. Gatrone, et al. (1987) “The synthesis and purification of the carbamoylmethylphosphine oxides”. Solvent Extraction and Ion Exchange, 5:1075-1116.

MINOR ACTINIDE SEPARATION

Bis(o-Trifluoromethylphenyl)dithiophosphinic acid was first reported by Idaho National Laboratory for the separation of minor actinides from lanthanides^a.
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(a) J.R.Klaehan, et al. (2008) “Synthesis of symmetric dithiophosphinic acids for “minor actinide” extraction”. Inorganica Chimica Acta 361: 2522-2532.

10-Hydroxybenzo[h]quinoline-7-sulfonate (HBQS) is used as a fluorescence reagent^a for determination of Beryllium with high sensitivity and selectivity. NIOSH Methods 7704 and 9110 detail analytical procedures which are readily adaptable to field testing conditions.

(a) H. Matsumiya et al. (2001) “A novel fluorescent reagent, 10-Hydroxybenzo[h]quinoline-7-sulfonate, for selective determination of beryllium(II) ion at pg cm-3 levels”. Analyst, 126: 2082-2086.

DDCP is an analytical reagent for detection of Pu and Am^{a, b}

(a) P.C. Doto et al.(1981) “ Solvent extraction process for recovery of Americium-241 at Hanford”. Transplutonium Elements-Production and Recovery. Ch7:109-129.

(b) USTUR 300: Anion exchange isolation of americium from prepared tissue solutions.