Cesium removal from Hanford tank waste
Conference
·
OSTI ID:10146484
Researchers at PNL are developing ion exchange processes to remove cesium from high salt, alkaline tank wastes at the Hanford site. The separated cesium will be concentrated and vitrified for disposal in the High-Level Waste Repository. The low-level waste fraction containing the majority of the waste constituents will be solidified in a grout waste form for disposal in underground concrete vaults. While the treatment and disposal requirements are still being defined, one goal is to remove enough cesium so that the low-level waste will meet the class A limits for Cs-137 (1 Ci/m{sup 3}). An integrated laboratory testing and desip effort is being used to speed the deployment of the ion exchange processes. The three main areas of laboratory investigation are equilibrium behavior, column performance, and material stability in the radioactive and chemical environment encountered during waste processing. Materials being investigated include a phenolic-carboxylic acid based resin, a resorcinol-formaldehyde resin, and the inorganic ion exchangers zeolite and silco-titanates. Concurrent with the laboratory work, a field deployable, modular compact ion-exchange unit is being designed to provide a means for rapid deployment of the technology. This distributed processing concept appears to offer several advantages relative to the traditional centralized fixed canyon facility. These include accelerating the start of tank waste pretreatment, flexibility to incorporate process improvements, flexibility to tailor a process to a particular waste type, and a reduced risk in deploying new processes.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10146484
- Report Number(s):
- PNL-SA--21848; CONF-930364--2; ON: DE93011906
- Country of Publication:
- United States
- Language:
- English
Similar Records
An investigation of the radiolytic stability of a resorcinol-formaldehyde ion exchange resin
REMOVAL OF CESIUM FROM SAVANNAH RIVER SITE WASTE WITH SPHERICAL RESORCINOL FORMALDEHYDE ION EXCHANGE RESIN EXPERIMENTAL TESTS
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Technical Report
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Sun Jan 30 23:00:00 EST 1994
·
OSTI ID:10136677
REMOVAL OF CESIUM FROM SAVANNAH RIVER SITE WASTE WITH SPHERICAL RESORCINOL FORMALDEHYDE ION EXCHANGE RESIN EXPERIMENTAL TESTS
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Wed Mar 31 00:00:00 EDT 2010
· Separation Science and Technology
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OSTI ID:982417
MODELING RESULTS FROM CESIUM ION EXCHANGE PROCESSING WITH SPHERICAL RESINS
Conference
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Sun Jan 02 23:00:00 EST 2011
·
OSTI ID:1001425
Related Subjects
052001
052002
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105
CESIUM 137
HANFORD RESERVATION
HIGH-LEVEL RADIOACTIVE WASTES
ION EXCHANGE
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RESINS
SALTS
SEPARATION PROCEDURES
SEPARATION PROCESSES
TANKS
VITRIFICATION
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052002
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37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
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CESIUM 137
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HIGH-LEVEL RADIOACTIVE WASTES
ION EXCHANGE
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RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RESINS
SALTS
SEPARATION PROCEDURES
SEPARATION PROCESSES
TANKS
VITRIFICATION
WASTE DISPOSAL AND STORAGE
WASTE PROCESSING