Radionuclide separations for the reduction of high-level waste volume
Creators
- 1. Pacific Northwest Lab., Richland, WA (United States)
Description
Applying solvent extraction and chromatographic methods in the separation of Pu, Am, U, 90Sr, and 137Cs from radioactive US defense wastes is described. These wastes consist of large amounts of non-radioactive material (e.g., NaOH, NaNO3, NaNO2, Fe(OH)3, Zr(OH)4, etc.) contaminated with various radionuclides. Separating these radionuclides from the bulk components of the wastes will greatly reduce the volume of high-level wastes (HLW) to be disposed. The TRUEX solvent extraction process or an analogous extraction chromatographic process can be used to separate Pu, Am, and U from acid-dissolved sludge wastes. The SREX solvent extraction process can be used to separate 90Sr from acid-dissolved sludge wastes. Alternatively, extraction chromatographic techniques can be used to separate 90Sr. Ion exchange methods can be used to separate 137Cs, 90Sr, and Pu from alkaline tank supernates, sludge wash solutions, and dissolved salt cakes
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0691-X
- Imprint Title
- Proceedings of the 1993 international conference on nuclear waste management and environmental remediation. Volume 1: Low and intermediate level radioactive waste management
- Imprint Pagination
- 776 p.
- Journal Page Range
- p. 367-373.
Conference
- Title
- '93 international conference on nuclear waste management and environmental remediation.
- Dates
- 5-11 Sep 1993.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27008900
- 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, Numerical Data
- Descriptors DEI
- AMERICIUM; CESIUM 137; EXPERIMENTAL DATA; EXTRACTION CHROMATOGRAPHY; FLOWSHEETS; HIGH-LEVEL RADIOACTIVE WASTES; ION EXCHANGE; PLUTONIUM; RADIOACTIVE WASTE PROCESSING; SOLVENT EXTRACTION; STRONTIUM 90; TRUEX PROCESS; URANIUM
- Descriptors DEC
- ACTINIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CHROMATOGRAPHY; DATA; DIAGRAMS; ELEMENTS; EVEN-EVEN NUCLEI; EXTRACTION; INFORMATION; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; METALS; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; SEPARATION PROCESSES; STRONTIUM ISOTOPES; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-930906--.