Compression and immersion tests and leaching of radionuclides, stable metals, and chelating agents from cement-solidified decontamination waste collected from nuclear power stations
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
A study was performed for the Nuclear Regulatory Commission (NRC) to evaluate structural stability and leachability of radionuclides, stable metals, and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from seven commercial boiling water reactors and one pressurized water reactor. The decontamination methods used at the reactors were the Can-Decon, AP/Citrox, Dow NS-1, and LOMI processes. Samples of untreated resin waste and solidified waste forms were subjected to immersion and compressive strength testing. Some waste-form samples were leach-tested using simulated groundwaters and simulated seawater for comparison with the deionized water tests that are normally performed to assess waste-form leachability. This report presents the results of these tests and assesses the effects of the various decontamination methods, waste form formulations, leachant chemical compositions, and pH of the leachant on the structural stability and leachability of the waste forms. Results indicate that releases from intact and degraded waste forms are similar and that the behavior of some radionuclides such as {sup 55}Fe, {sup 60}Co, and {sup 99}Tc were similar. In addition, the leachability indexes are greater than 6.0, which meets the requirement in the NRC`s ``Technical Position on Waste Form,`` Revision 1.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Regulatory Applications; EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 10163389
- Report Number(s):
- NUREG/CR-6201; EGG-2736; ON: TI94014576; TRN: 94:015431
- Resource Relation:
- Other Information: PBD: Jun 1994
- Country of Publication:
- United States
- Language:
- English
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The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants
Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
RADIOACTIVE EFFLUENTS
PWR TYPE REACTORS
RADIOACTIVE WASTES
LEACHING
RESINS
CHELATING AGENTS
RADIONUCLIDE MIGRATION
WASTE FORMS
STABILITY
DECONTAMINATION
SOLIDIFICATION
540230
220502
RADIOACTIVE MATERIALS MONITORING AND TRANSPORT