Preliminary assessment of the controlled release of radionuclides from waste packages containing borosilicate waste glass
Description
The purpose of this report is to provide a preliminary assessment of the release-rate for an engineered barriers subsystem (EBS) containing waste packages of defense high-level waste borosilicate glass at geochemical and hydrological conditions similar to the those at Yucca Mountain. The relationship between the proposed Waste Acceptance Preliminary Specifications (WAPS) test of glass- dissolution rate and compliance with the NRC's release-rate criterion is also evaluated. Calculations are reported for three hierarchical levels: EBS analysis, waste-package analysis, and waste-glass analysis. The following conclusions identify those factors that most acutely affect the magnitude of, or uncertainty in, release-rate performance
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92006743; NTIS; INIS; US Govt. Printing Office Dep.
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Additional details
Publishing Information
- Imprint Pagination
- 95 p.
- Report number
- PNL--7591
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23040465
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- BOROSILICATE GLASS; CONTAINMENT SYSTEMS; CORROSION; DIFFUSION; DISSOLUTION; FAILURES; FISSION PRODUCTS; HIGH-LEVEL RADIOACTIVE WASTES; MASS TRANSFER; MATHEMATICAL MODELS; PACKAGING; PERFORMANCE; RADIOISOTOPES; RADIONUCLIDE MIGRATION; SOLUBILITY; WASTE FORMS
- Descriptors DEC
- CHEMICAL REACTIONS; CONTAINMENT; ENVIRONMENTAL TRANSPORT; GLASS; ISOTOPES; MATERIALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTES
Optional Information
- Contract/Grant/Project number
- Contract AC06-76RL01830
- Funding organization
- USDOE, Washington, DC (United States).