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Title: Actinide partitioning from actual ICPP dissolved zirconium calcine using the TRUEX solvent

Abstract

The TRansUranic EXtraction process (TRUEX), as developed by E.P. Horwitz and coworkers at Argonne National Laboratory (ANL), is being evaluated as a TRU extraction process for Idaho Chemical Processing Plant (ICPP) wastes. A criteria that must be met during this evaluation, is that the aqueous raffinate must be below the 10 nCi/g limit specified in 10 CFR 61.55. A test was performed where the TRUEX solvent (0.2 M octyl(phenyl)-N-N-diisobutyl-carbamoylmethyl-phosphine oxide (CMPO), and 1.4 M tributylphosphate (TBP) in an Isopar-L diluent) was contacted with actual ICPP dissolved zirconium calcine. Two experimental flowsheets were used to determine TRU decontamination factors, and TRU, Zr, Fe, Cr, and Tc extraction, scrub, and strip distribution coefficients. Results from these two flowsheets show that >99.99% of the TRU alpha activity was removed from the acidic feed after three contacts with the TRUEX solvent (fresh solvent being used for each contact). The resulting aqueous raffinate solution contained an approximate TRU alpha activity of 0.02 nCi/g, which is well below the non-TRU waste limit of 10 nCi/g specified in 10 CFR 61.55. Favorable scrub and strip distribution coefficients were also observed for Am-241, Pu-238, and Pu-239, indicating the feasibility of recovering these isotopes from the TRUTEX solvent. Amore » solution of 0.04 M 1-hydroxyethane-1,1-diphosphonic acid (HEDPA) in 0.04 M HNO{sub 3} was used to successfully strip the TRUs from the TRUEX solvent. The results of the test using actual ICPP dissolved zirconium calcine, and subsequent GTM evaluation, show the feasibility of removing TRUs from the dissolved zirconium calcine with the TRUEX solvent and the deleterious effects zirconium poses with the ICPP zirconium calcine waste. Test results using actual ICPP zirconium calcine reveal the necessity of preventing zirconium from following the TRUs.« less

Authors:
; ;  [1]
  1. and others
Publication Date:
Research Org.:
Fermi National Accelerator Lab., Batavia, IL (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
114585
Report Number(s):
INEL-95/0225
ON: DE96001184; TRN: 95:024405
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: May 1995
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; IDAHO CHEMICAL PROCESSING PLANT; RADIOACTIVE WASTE MANAGEMENT; SPENT FUELS; REPROCESSING; ALPHA-BEARING WASTES; SEPARATION PROCESSES; EXTRACTION APPARATUSES; EVALUATION; PERFORMANCE TESTING; ACTINIDES; TRUEX PROCESS; ZIRCONIUM

Citation Formats

Brewer, K N, Herbst, R S, and Tranter, T J. Actinide partitioning from actual ICPP dissolved zirconium calcine using the TRUEX solvent. United States: N. p., 1995. Web. doi:10.2172/114585.
Brewer, K N, Herbst, R S, & Tranter, T J. Actinide partitioning from actual ICPP dissolved zirconium calcine using the TRUEX solvent. United States. https://doi.org/10.2172/114585
Brewer, K N, Herbst, R S, and Tranter, T J. Mon . "Actinide partitioning from actual ICPP dissolved zirconium calcine using the TRUEX solvent". United States. https://doi.org/10.2172/114585. https://www.osti.gov/servlets/purl/114585.
@article{osti_114585,
title = {Actinide partitioning from actual ICPP dissolved zirconium calcine using the TRUEX solvent},
author = {Brewer, K N and Herbst, R S and Tranter, T J},
abstractNote = {The TRansUranic EXtraction process (TRUEX), as developed by E.P. Horwitz and coworkers at Argonne National Laboratory (ANL), is being evaluated as a TRU extraction process for Idaho Chemical Processing Plant (ICPP) wastes. A criteria that must be met during this evaluation, is that the aqueous raffinate must be below the 10 nCi/g limit specified in 10 CFR 61.55. A test was performed where the TRUEX solvent (0.2 M octyl(phenyl)-N-N-diisobutyl-carbamoylmethyl-phosphine oxide (CMPO), and 1.4 M tributylphosphate (TBP) in an Isopar-L diluent) was contacted with actual ICPP dissolved zirconium calcine. Two experimental flowsheets were used to determine TRU decontamination factors, and TRU, Zr, Fe, Cr, and Tc extraction, scrub, and strip distribution coefficients. Results from these two flowsheets show that >99.99% of the TRU alpha activity was removed from the acidic feed after three contacts with the TRUEX solvent (fresh solvent being used for each contact). The resulting aqueous raffinate solution contained an approximate TRU alpha activity of 0.02 nCi/g, which is well below the non-TRU waste limit of 10 nCi/g specified in 10 CFR 61.55. Favorable scrub and strip distribution coefficients were also observed for Am-241, Pu-238, and Pu-239, indicating the feasibility of recovering these isotopes from the TRUTEX solvent. A solution of 0.04 M 1-hydroxyethane-1,1-diphosphonic acid (HEDPA) in 0.04 M HNO{sub 3} was used to successfully strip the TRUs from the TRUEX solvent. The results of the test using actual ICPP dissolved zirconium calcine, and subsequent GTM evaluation, show the feasibility of removing TRUs from the dissolved zirconium calcine with the TRUEX solvent and the deleterious effects zirconium poses with the ICPP zirconium calcine waste. Test results using actual ICPP zirconium calcine reveal the necessity of preventing zirconium from following the TRUs.},
doi = {10.2172/114585},
url = {https://www.osti.gov/biblio/114585}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {5}
}