Underground storage tank integrated demonstration: Evaluation of pretreatment options for Hanford tank wastes
Description
Separation science plays a central role inn the pretreatment and disposal of nuclear wastes. The potential benefits of applying chemical separations in the pretreatment of the radioactive wastes stored at the various US Department of Energy sites cover both economic and environmental incentives. This is especially true at the Hanford Site, where the huge volume (>60 Mgal) of radioactive wastes stored in underground tanks could be partitioned into a very small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). The cost associated with vitrifying and disposing of just the HLW fraction in a geologic repository would be much less than those associated with vitrifying and disposing of all the wastes directly. Futhermore, the quality of the LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. In this report, we present the results of an evaluation of the pretreatment options for sludge taken from two different single-shell tanks at the Hanford Site-Tanks 241-B-110 and 241-U-110 (referred to as B-110 and U-110, respectively). The pretreatment options examined for these wastes included (1) leaching of transuranic (TRU) elements from the sludge, and (2) dissolution of the sludge followed by extraction of TRUs and 90Sr. In addition, the TRU leaching approach was examined for a third tank waste type, neutralized cladding removal waste
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE93016830; NTIS; INIS; US Govt. Printing Office Dep.Files
24075660.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 34 p.
- Report number
- PNL--8537
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24075660
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- ALPHA-BEARING WASTES; CARBONATES; CESIUM 137; DISSOLUTION; GROUTING; HANFORD RESERVATION; HIGH-LEVEL RADIOACTIVE WASTES; LEACHING; LOW-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; SLUDGES; STRONTIUM 90; TANKS; TECHNETIUM 99; VITRIFICATION
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON COMPOUNDS; CESIUM ISOTOPES; CONTAINERS; EVEN-EVEN NUCLEI; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MATERIALS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; SEPARATION PROCESSES; STORAGE; STRONTIUM ISOTOPES; TECHNETIUM ISOTOPES; US DOE; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTE STORAGE; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract AC06-76RL01830
- Funding organization
- USDOE, Washington, DC (United States).