AMP-PAN column tests for the removal of 137Cs from actual and simulated INEEL high-activity wastes

Author:

Brewer K. N.,Todd T. A.,Wood D. J.,Tullock P. A.,Sebesta F.,John J.,Motl A.

Publisher

Springer Science and Business Media LLC

Subject

General Physics and Astronomy

Reference11 articles.

1. J. D. Law et al.: Demonstration of the TRUEX Process for partitioning Actinides from Actual ICPP Tank Waste Using Centrifugal Contactors in a Shielded Cell Facility, Lockheed Martin Idaho Technologies Co., INEL-96/0353, September 1996.

2. J. D. Law et al.: TRUEX Flowsheet Development Applied to ICPP Sodium-Bearing Waste Using Centrifugal Contactors, Lockheed Martin Idaho Technologies Co., INEL-95/0130, February 1995.

3. J. D. Law et al.: Demonstration of a SREX Flowsheet for the Partitioning of Strontium and Lead from Actual ICPP Sodium-Bearing Waste, Lockheed Martin Idaho Technologies Co., INEEL/Ext-97-00832, August, 1997.

4. K. N. Brewer et al.: Partitioning of Radionuclides from ICPP Sodium-Bearing Waste Using Russian Phosphine Oxide and Cobalt Dicarbollide Technologies, Westinghouse Idaho Nuclear Co., WINCO-1230, September 1994.

5. J. D. Law et al.: Flowsheet Development Studies Using Cobalt Dicarbollide and Phosphine Oxide Solvent Extraction Technologies for the Partitioning of Radionuclides from ICPP Sodium-Bearing Waste with Centrifugal Contactors, Lockheed Martin Idaho Technologies Co., INEL/95-0500, September 1995.

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