Preliminary assessment of the controlled release of radionuclides from waste packages containing borosilicate waste glass

DM Strachan, BP McGrail, MJ Apted, DW Engle… - 1990 - osti.gov
DM Strachan, BP McGrail, MJ Apted, DW Engle, PW Eslinger
1990osti.gov
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 NRCs release-
rate criterion is also evaluated. Calculations are reported for three hierarchical levels: EBS …
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.
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