Published January 1997 | Version v1
Journal article Metadata-only

Evaluation of the SREX solvent extraction process for the removal of 90Sr and hazardous metals from acidic nuclear waste solutions containing high concentrations of interfering alkali metal ions

Creators

  • 1. Idaho National Engineering Lab., Idaho Falls, ID (United States)

Description

The SREX process, which was developed at Argonne National Laboratories, has been evaluated for its effectiveness for the decontamination of radioactive liquid waste at the Idaho Chemical Processing Plant located at the Idaho National Engineering Laboratory. The extraction solvent consists of 0.15 M 4',4',(5')-di-(t-butyl-dicyclohexo)-18-crown-6 in either 1.2 M TBP/isopar L reg-sign. Suppressed extraction due to matrix interferences limits DSr values to the range of 3-4 in batch extraction experiments. The SREX solvent has been shown to be effective in the removal of non-radioactive Pb from liquid wastes, in addition to the extraction of 90Sr. The information from this study has been used to develop a proposed flowsheet for the treatment of liquid waste in centrifugal contactors

Additional details

Publishing Information

Journal Title
Separation Science and Technology
Journal Volume
32
Journal Issue
1-4
Journal Page Range
p. 241-253.
ISSN
0149-6395
CODEN
SSTEDS

Conference

Title
9. symposium on separation science and technology for energy applications.
Dates
22-26 Oct 1995.
Place
Gatlinburg, TN (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28050513
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CENTRIFUGATION; CROWN ETHERS; INTERFERING ELEMENTS; MATHEMATICAL MODELS; RADIOACTIVE WASTE PROCESSING; SOLVENT EXTRACTION; STRONTIUM 90
Descriptors DEC
BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; ETHERS; EVEN-EVEN NUCLEI; EXTRACTION; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; NUCLEI; ORGANIC COMPOUNDS; ORGANIC OXYGEN COMPOUNDS; RADIOISOTOPES; SEPARATION PROCESSES; STRONTIUM ISOTOPES; WASTE MANAGEMENT; WASTE PROCESSING; YEARS LIVING RADIOISOTOPES

Optional Information

Secondary number(s)
CONF-951057--.