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Potentiometric determination of uranium in simulated Purex Process solutions by acidiometry

Journal Article:

Abstract

A potentiometric methods for sequential free acidity and uranium determination in simulated Purex Process solutions is described. An oxalate solution or a mixture of fluoride-oxalate pellets were used as complexing agent for free titration. Following this first equivalent point, uranium is determined-by indirect titration of H/sup +/ liberated in the peruanate reaction. Some elements present in the standard fuel elements with a burn-up of 33.000 Mwd/t, neutron flux of 3,2 x 10/sup 13/n.cm/sup -2/.s/sup -1/ and cooling time of two years were considered as interfering elements in uranium analyses. As a substitute of Pu-IV, Th(NO/sub 3/)/sub 4/ solution was used. The method can be applied to aqueous and organic (TBP/diluent) solutions with 2% precision and 2% accuracy. (Autor).
Publication Date:
Jan 01, 1984
Product Type:
Journal Article
Reference Number:
AIX-18-075751; EDB-87-140991
Resource Relation:
Journal Name: An. Assoc. Bras. Quim.; (Brazil); Journal Volume: 34-35:1-4
Subject:
37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; PUREX PROCESS; PROCESS SOLUTIONS; URANIUM; POTENTIOMETRY; CHEMICAL REACTIONS; NEUTRON FLUX; OXALATES; PH VALUE; QUANTITATIVE CHEMICAL ANALYSIS; ACTINIDES; CARBOXYLIC ACID SALTS; CHEMICAL ANALYSIS; DISPERSIONS; ELEMENTS; METALS; MIXTURES; RADIATION FLUX; REPROCESSING; SEPARATION PROCESSES; SOLUTIONS; TITRATION; 400102* - Chemical & Spectral Procedures; 050800 - Nuclear Fuels- Spent Fuels Reprocessing
OSTI ID:
6292250
Research Organizations:
Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, Brazil. Dept. de Engenharia Quimica
Country of Origin:
Brazil
Language:
Portuguese
Other Identifying Numbers:
Journal ID: CODEN: AABQA
Submitting Site:
INIS
Size:
Pages: 55-60
Announcement Date:
Aug 01, 1987

Journal Article:

Citation Formats

Cohen, V H, Matsuda, H T, Araujo, B.F. de, and Araujo, J.A. de. Potentiometric determination of uranium in simulated Purex Process solutions by acidiometry. Brazil: N. p., 1984. Web.
Cohen, V H, Matsuda, H T, Araujo, B.F. de, & Araujo, J.A. de. Potentiometric determination of uranium in simulated Purex Process solutions by acidiometry. Brazil.
Cohen, V H, Matsuda, H T, Araujo, B.F. de, and Araujo, J.A. de. 1984. "Potentiometric determination of uranium in simulated Purex Process solutions by acidiometry." Brazil.
@misc{etde_6292250,
title = {Potentiometric determination of uranium in simulated Purex Process solutions by acidiometry}
author = {Cohen, V H, Matsuda, H T, Araujo, B.F. de, and Araujo, J.A. de}
abstractNote = {A potentiometric methods for sequential free acidity and uranium determination in simulated Purex Process solutions is described. An oxalate solution or a mixture of fluoride-oxalate pellets were used as complexing agent for free titration. Following this first equivalent point, uranium is determined-by indirect titration of H/sup +/ liberated in the peruanate reaction. Some elements present in the standard fuel elements with a burn-up of 33.000 Mwd/t, neutron flux of 3,2 x 10/sup 13/n.cm/sup -2/.s/sup -1/ and cooling time of two years were considered as interfering elements in uranium analyses. As a substitute of Pu-IV, Th(NO/sub 3/)/sub 4/ solution was used. The method can be applied to aqueous and organic (TBP/diluent) solutions with 2% precision and 2% accuracy. (Autor).}
journal = {An. Assoc. Bras. Quim.; (Brazil)}
volume = {34-35:1-4}
journal type = {AC}
place = {Brazil}
year = {1984}
month = {Jan}
}