Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations
Description
The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission's ''Technical Position on Waste Form'' (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92017878; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- EGG-M--92090
Conference
- Title
- Waste management '92.
- Dates
- 1-5 Mar 1992.
- Place
- Tucson, AZ (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23083033
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S54: ENVIRONMENTAL SCIENCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRUNSWICK-1 REACTOR; CEMENTS; FITZPATRICK REACTOR; LEACHING; NUCLEAR POWER PLANTS; PH VALUE; RADIOACTIVE EFFLUENTS; RADIONUCLIDE MIGRATION; RESINS; SOLIDIFICATION
- Descriptors DEC
- BUILDING MATERIALS; BWR TYPE REACTORS; DISSOLUTION; ENRICHED URANIUM REACTORS; ENVIRONMENTAL TRANSPORT; MASS TRANSFER; MATERIALS; NUCLEAR FACILITIES; ORGANIC COMPOUNDS; ORGANIC POLYMERS; POLYMERS; POWER PLANTS; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTORS; SEPARATION PROCESSES; THERMAL POWER PLANTS; THERMAL REACTORS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-920307--86.