Improved measurement of aluminum in irradiated fuel reprocessed at the Savannah River Site
Description
This paper reports that at the Savannah River Site (SRS), irradiated fuel from research reactor operators or their contract fuel service companies is reprocessed in the H-Canyon Separations Facility. Final processing costs are based on analytical measurements of the amount of total metal dissolved. Shipper estimates for uranium and uranium-235 and measured values at SRS have historically agreed very well. There have occasional been significant differences between shipper estimates for aluminum and the aluminum content determined at SRS. To minimize analytical error that might contribute to poor shipper-receiver agreement for the reprocessing of offsite fuel, and new analytical method to measure aluminum was developed by SRS Analytical Laboratories at the Central Laboratory Facilities. An EDTA (ethylenediaminetetraacetic acid) titration method, subject to dissolver matrix interferences, was previously used at SRS to measure aluminum in H-Canyon dissolver during the reprocessing of offsite fuel
Additional details
Publishing Information
- Journal Title
- Nuclear Materials Management
- Journal Volume
- 20
- Series
- Nucl. Mater. Manage.
- Journal Page Range
- 1025-1027
- ISSN
- 0362-0034
- CODEN
- NUMMB
Conference
- Title
- 32. Institute of Nuclear Materials Management (INMM) annual meeting.
- Dates
- 28-31 Jul 1991.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23057144
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; ANIONS; COST; DISSOLUTION; EDTA; FISSION PRODUCTS; GAMMA RADIATION; ION EXCHANGE; PARTICLE SIZE; REACTOR OPERATORS; REPROCESSING; RESEARCH REACTORS; SAVANNAH RIVER PLANT; SPENT FUELS; TITRATION; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AMINO ACIDS; CARBOXYLIC ACIDS; CHARGED PARTICLES; CHELATING AGENTS; ELECTROMAGNETIC RADIATION; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; FUELS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTO; IONIZING RADIATIONS; IONS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NUCLEAR FUELS; NUCLEI; ORGANIC ACIDS; ORGANIC COMPOUNDS; PERSONNEL; RADIATIONS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES; SIZE; SPONTANEOUS FISSION RADIOISOTO; URANIUM ISOTOPES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-910774--.