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Title: Method for improving the extraction properties of a tributyl phosphate solution

Abstract

A method for improving the extraction properties of a tributyl phosphate extractant used for reprocessing irradiated nuclear reactor fuel (Purex Process) containing degradation products of tributyl phosphate by contacting the extractant with diazomethane in a suitable solvent whereby the degradation products are esterified to triester phosphates which have extraction properties similar to those of tributyl phosphate.

Inventors:
 [1];  [2]
  1. Richland, WA
  2. Kennewick, WA
Publication Date:
Research Org.:
Battelle Pacific Northwest Labs., Richland, WA (United States)
OSTI Identifier:
862477
Patent Number(s):
US 3943204
Assignee:
United States of America as represented by United States Energy (Washington, DC)
DOE Contract Number:  
AT(45-1)-1830
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
method; improving; extraction; properties; tributyl; phosphate; solution; extractant; reprocessing; irradiated; nuclear; reactor; fuel; purex; process; containing; degradation; products; contacting; diazomethane; suitable; solvent; whereby; esterified; triester; phosphates; similar; purex process; tributyl phosphate; irradiated nuclear; suitable solvent; nuclear reactor; reactor fuel; degradation products; properties similar; extraction properties; phosphate extractant; phosphate solution; /999/423/976/987/

Citation Formats

Martin, Earl C, and Bruns, Lester E. Method for improving the extraction properties of a tributyl phosphate solution. United States: N. p., 1976. Web.
Martin, Earl C, & Bruns, Lester E. Method for improving the extraction properties of a tributyl phosphate solution. United States.
Martin, Earl C, and Bruns, Lester E. 1976. "Method for improving the extraction properties of a tributyl phosphate solution". United States. https://www.osti.gov/servlets/purl/862477.
@article{osti_862477,
title = {Method for improving the extraction properties of a tributyl phosphate solution},
author = {Martin, Earl C and Bruns, Lester E},
abstractNote = {A method for improving the extraction properties of a tributyl phosphate extractant used for reprocessing irradiated nuclear reactor fuel (Purex Process) containing degradation products of tributyl phosphate by contacting the extractant with diazomethane in a suitable solvent whereby the degradation products are esterified to triester phosphates which have extraction properties similar to those of tributyl phosphate.},
doi = {},
url = {https://www.osti.gov/biblio/862477}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1976},
month = {Thu Jan 01 00:00:00 EST 1976}
}