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Title: Testing of stripping columns for the removal of benzene from aqueous radioactive salt solution

Abstract

Radioactive high level wastes (HLW) generated from production of special nuclear materials at the Savannah River Site (SRS) are held in interim storage in 51 underground, million gallon tanks. Radioactive cesium ({sup 137}Cs) is segregated by evaporation of aqueous waste solution for interim storage in a salt matrix comprised of Na and K salts or in concentrated salt solution. The saltcake will be dissolved and {sup 137}Cs will be separated from the nonradioactive salts in solution in the In-Tank Precipitation (ITP) Process. The cesium will be combined with other radioactive species and glass formers to be melted and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). The salt solution remaining after decontamination in the ITP process will be incorporated into grout for disposal at the site`s Saltstone facility. In the ITP facility, sodium tetraphenylborate (STPB) will be added to precipitate the cesium. Potassium in the waste solution also reacts with STPB and precipitates. Due to radiolytic and chemical degradation of the tetraphenylborate (TPB) precipitate, benzene is generated. The benzene dissolves into the decontaminated salt solution (DSS) and into water (WW) used to {open_quotes}wash{close_quotes} the precipitate to lower the soluble salt content of the slurry. Safety andmore » processing requirements for disposal of the DSS and for temporary storage of the WW dictate that the benzene concentration be reduced.« less

Authors:
;  [1];  [2]
  1. Westinghouse Savannah River Co., Aiken, SC (United States)
  2. Elf Atochem North America, Inc., King of Prussia, PA (United States) [and others
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
120889
Report Number(s):
WSRC-MS-95-0035; CONF-9507119-6
ON: DE96001915; TRN: 95:024574
DOE Contract Number:  
AC09-89SR18035
Resource Type:
Conference
Resource Relation:
Conference: Summer national meeting of the American Institute of Chemical Engineers, Boston, MA (United States), 30 Jul - 2 Aug 1995; Other Information: PBD: 27 Jun 1995
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; BENZENE; SEPARATION PROCESSES; CONCENTRATION RATIO; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE PROCESSING; DECONTAMINATION; EVAPORATION; PRECIPITATION; SALTS; SAVANNAH RIVER; SODIUM COMPOUNDS; TANKS; CESIUM 137; COLUMN PACKING; NITROGEN

Citation Formats

Georgeton, G.K., Taylor, G.A., and Gaughan, T.P. Testing of stripping columns for the removal of benzene from aqueous radioactive salt solution. United States: N. p., 1995. Web.
Georgeton, G.K., Taylor, G.A., & Gaughan, T.P. Testing of stripping columns for the removal of benzene from aqueous radioactive salt solution. United States.
Georgeton, G.K., Taylor, G.A., and Gaughan, T.P. Tue . "Testing of stripping columns for the removal of benzene from aqueous radioactive salt solution". United States. https://www.osti.gov/servlets/purl/120889.
@article{osti_120889,
title = {Testing of stripping columns for the removal of benzene from aqueous radioactive salt solution},
author = {Georgeton, G.K. and Taylor, G.A. and Gaughan, T.P.},
abstractNote = {Radioactive high level wastes (HLW) generated from production of special nuclear materials at the Savannah River Site (SRS) are held in interim storage in 51 underground, million gallon tanks. Radioactive cesium ({sup 137}Cs) is segregated by evaporation of aqueous waste solution for interim storage in a salt matrix comprised of Na and K salts or in concentrated salt solution. The saltcake will be dissolved and {sup 137}Cs will be separated from the nonradioactive salts in solution in the In-Tank Precipitation (ITP) Process. The cesium will be combined with other radioactive species and glass formers to be melted and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). The salt solution remaining after decontamination in the ITP process will be incorporated into grout for disposal at the site`s Saltstone facility. In the ITP facility, sodium tetraphenylborate (STPB) will be added to precipitate the cesium. Potassium in the waste solution also reacts with STPB and precipitates. Due to radiolytic and chemical degradation of the tetraphenylborate (TPB) precipitate, benzene is generated. The benzene dissolves into the decontaminated salt solution (DSS) and into water (WW) used to {open_quotes}wash{close_quotes} the precipitate to lower the soluble salt content of the slurry. Safety and processing requirements for disposal of the DSS and for temporary storage of the WW dictate that the benzene concentration be reduced.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {6}
}

Conference:
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