Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide]
Abstract
This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solvent (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste. Assessments were made of the use of two TRUEX solvents: one incorporating the well-studied dihexyl-N,N-diethylcarbamoylmethylphosphonate (DHDECMP) and a second incorporating an extractant with superior properties for a 1M HNO/sub 3/ acid feed, octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (O/sub phi/D(IB)CMPO). In this report, conceptual flowsheets for the removal of soluble TRUs from high-level nuclear wastes using these two TRUEX proces solvents are presented, and flowsheet features are discussed in detail. The conceptual flowsheet for TRU-element removal from a PUREX waste by the O/sub phi/D(IB)CMPO-TRUEX process solvent was tested in a bench-scale countercurrent experiment, and results of that experiment are presented and discussed. The conclusion of this study is that the TRUEX process is able to separate TRUs from high-level wastes so that the major portion of the solid waste (approx. 99%) can be classified as non-TRU. Areas where more experimentation is needed are listed at the endmore »
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- OSTI Identifier:
- 6696097
- Report Number(s):
- ANL-84-45
ON: DE84016019
- DOE Contract Number:
- W-31-109-ENG-38
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; DHDECMP; SOLVENT PROPERTIES; ORGANIC PHOSPHORUS COMPOUNDS; RADIOACTIVE WASTE PROCESSING; HIGH-LEVEL RADIOACTIVE WASTES; SOLVENT EXTRACTION; TRANSURANIUM ELEMENTS; BENCH-SCALE EXPERIMENTS; EXPERIMENTAL DATA; FLOWSHEETS; NITRIC ACID; DATA; DIAGRAMS; ELEMENTS; ESTERS; EXTRACTION; HYDROGEN COMPOUNDS; INFORMATION; INORGANIC ACIDS; MANAGEMENT; MATERIALS; NUMERICAL DATA; ORGANIC COMPOUNDS; PHOSPHONIC ACID ESTERS; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; 052001* - Nuclear Fuels- Waste Processing; 400105 - Separation Procedures
Citation Formats
Vandegrift, G F, Leonard, R A, Steindler, M J, Horwitz, E P, Basile, L J, Diamond, H, Kalina, D G, and Kaplan, L. Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide]. United States: N. p., 1984.
Web. doi:10.2172/6696097.
Vandegrift, G F, Leonard, R A, Steindler, M J, Horwitz, E P, Basile, L J, Diamond, H, Kalina, D G, & Kaplan, L. Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide]. United States. https://doi.org/10.2172/6696097
Vandegrift, G F, Leonard, R A, Steindler, M J, Horwitz, E P, Basile, L J, Diamond, H, Kalina, D G, and Kaplan, L. 1984.
"Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide]". United States. https://doi.org/10.2172/6696097. https://www.osti.gov/servlets/purl/6696097.
@article{osti_6696097,
title = {Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide]},
author = {Vandegrift, G F and Leonard, R A and Steindler, M J and Horwitz, E P and Basile, L J and Diamond, H and Kalina, D G and Kaplan, L},
abstractNote = {This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solvent (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste. Assessments were made of the use of two TRUEX solvents: one incorporating the well-studied dihexyl-N,N-diethylcarbamoylmethylphosphonate (DHDECMP) and a second incorporating an extractant with superior properties for a 1M HNO/sub 3/ acid feed, octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (O/sub phi/D(IB)CMPO). In this report, conceptual flowsheets for the removal of soluble TRUs from high-level nuclear wastes using these two TRUEX proces solvents are presented, and flowsheet features are discussed in detail. The conceptual flowsheet for TRU-element removal from a PUREX waste by the O/sub phi/D(IB)CMPO-TRUEX process solvent was tested in a bench-scale countercurrent experiment, and results of that experiment are presented and discussed. The conclusion of this study is that the TRUEX process is able to separate TRUs from high-level wastes so that the major portion of the solid waste (approx. 99%) can be classified as non-TRU. Areas where more experimentation is needed are listed at the end of the report. 45 references, 17 figures, 56 tables.},
doi = {10.2172/6696097},
url = {https://www.osti.gov/biblio/6696097},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jul 01 00:00:00 EDT 1984},
month = {Sun Jul 01 00:00:00 EDT 1984}
}