Sorption procedure for recovery of {sup 90}Sr from nuclear fuel reprocessing solutions and its purification. I. Recovery of {sup 90}Sr

Journal Article · Fri Sep 01 04:00:00 EDT 1995 · Radiochemistry

OSTI ID:175708

Maslova, G B; Kudryavtseva, S P; Gelis, V M ^[1]

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1. Institute of Physical Chemistry, Moscow (Russian Federation); and others

A possibility was studied of sorption recovery of {sup 90}Sr from raffinates resulted from the reprocessing of nuclear fuel. A method was suggested for selective recovery of strontium with vinylpyridine ampholyte VPK in the presence of masking additives of complexing agents [citric and chromotropic acids (CTA and CHA, respectively)]. Optimal conditions of the process are as follows: in the presence of CTA-CTA: {Sigma}Me = 0.5 : 1 at pH 8, and in the presence of CHA-CHA: {Sigma}Me = 1:1 at pH 7-9; the resin in the Na form. Under these conditions the main part of inpurities is transferred into the filtrate. The process was tested with a highly radioactive solution. Thea authors have obtained the following factors of purification of {sup 90}Sr: with respect to {gamma}-emitting radionuclides 47, {beta}-emitting radionuclides 5, Fe 7, Ni 5, Cr 17, Al 48, Mn 5, and rare-earth metals 3. Approximately 98% of strontium was recovered.

• OSTI ID: 175708
• Journal Information: Radiochemistry, Journal Name: Radiochemistry Journal Issue: 5 Vol. 37; ISSN RDIOEO; ISSN 1066-3622
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
40 CHEMISTRY
CHROMOTROPIC ACID
CITRIC ACID
ION EXCHANGE MATERIALS
NUCLEAR FUELS
PURIFICATION
REPROCESSING
SORPTION
SORPTIVE PROPERTIES
STRONTIUM 90