Published 2023 | Version v1
Book

Determination of U(IV) concentration by ferric sulphate titration

  • 1. Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam-603102 (India)

Description

The uranous nitrate solution is employed as a reducing agent for Pu(IV) in PUREX process for the mutual separation of uranium and plutonium from the loaded organic phase. This reagent is also used for recovery of plutonium from degraded solvent, removal of plutonium from surface of the process equipment and tanks etc. The uranous nitrate of concentration of 5-100g/L is usually employed for the recovery of plutonium in reprocessing plant. As uranium in +4 oxidation state undergoes aerial oxidation and also by the nitrite ion present in nitric acid, it is important to determine the concentration of U(IV) before treatment. In general, concentration of uranous ion in feed sample is determined by redox titration method using potassium dichromate as the titrant and ferroin as indicator. The concentration of uranous in the test samples were also analyzed by redox titration and spectrophotometric methods. The concentration value obtained by the present procedure is in good agreement with the value determined by the conventional method

Part of:
Proceedings of the sixteenth biennial DAE-BRNS symposium on nuclear and radiochemistry: book of abstracts

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the sixteenth biennial DAE-BRNS symposium on nuclear and radiochemistry: book of abstracts
Imprint Pagination
469 p.
Journal Page Range
p. 208

Conference

Title
16. biennial DAE-BRNS symposium on nuclear and radiochemistry
Acronym
NUCAR-2023
Dates
1-5 May 2023
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
54108361
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MATERIALS RECOVERY; PLUTONIUM; PUREX PROCESS; SOLVENT EXTRACTION; URANIUM
Descriptors DEC
ACTINIDES; ELEMENTS; EXTRACTION; MANAGEMENT; METALS; PROCESSING; REPROCESSING; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING

Optional Information