Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
Data are presented on the physical stability and leachability of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small-scale waste--form specimens collected during solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station were leach-tested and subjected to compressive strength testing in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1). Samples of untreated resin waste collected from each solidification vessel before the solidification process were analyzed for concentrations of radionuclides, selected transition metals, and chelating agents to determine the quantities of these chemicals in the waste-form specimens. The chelating agents included oxalic, citric, and picolinic acids. In order to determine the effect of leachant chemical composition and pH on the stability and leachability of the waste forms, waste-form specimens were leached in various leachants. Results of this study indicate that differences in pH do not affect releases from cement-solidified decontamination ion-exchange resin waste forms, but that differences in leachant chemistry and the presence of chelating agents may affect the releases of radionuclides and chelating agents. Also, this study indicates that the cumulative releases of radionuclides and chelating agents are similar for waste- form specimens that decomposed and those that retained their general physical form. 36 refs., 60 figs., 28 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5585086
- Report Number(s):
- NUREG/CR-5601; EGG-2605; ON: TI91015168
- Country of Publication:
- United States
- Language:
- English
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Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations
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Related Subjects
CHELATING AGENTS
LEACHING
ION EXCHANGE MATERIALS
SOLIDIFICATION
LOW-LEVEL RADIOACTIVE WASTES
METALS
RADIOISOTOPES
WASTE FORMS
BRUNSWICK-1 REACTOR
CEMENTS
DECONTAMINATION
GROUND DISPOSAL
GROUND WATER
PH VALUE
RESINS
STABILITY
BUILDING MATERIALS
BWR TYPE REACTORS
CLEANING
DISSOLUTION
ELEMENTS
HYDROGEN COMPOUNDS
ISOTOPES
MANAGEMENT
MATERIALS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHASE TRANSFORMATIONS
POLYMERS
POWER REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTORS
SEPARATION PROCESSES
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
052001* - Nuclear Fuels- Waste Processing