Abstract:The Nevada Nuclear Waste Storage Investigations Project is investigating the suitability of the tuffaceous rocks at Yucca Mountain Nevada for potential use as a high level nuclear waste repository. The horizon under investigation lies above the water table, and therefore offers a setting that differs substantially from other potential repository sites. The unsaturated zone environment allows a simple, but effective, waste package design. The source term for radionuclide release from the waste package will be b… Show more
“…A value of 0.2 um/yr would appear to be adequate to describe conservatively the rate data so far acquired (Oversby and McCright, 1984). Extrapolation of these rates…”
Section: Summary and Analysis Of General Corrosion And Oxidation Testingmentioning
confidence: 96%
“…It appears that the molybdenum and nitrogen additions impede the diffusion of carbon atoms in austenitic stainless steels; therefore, the growth rates of carbide nuclei are slowed, and materials containing these alloy additions are considerably more resistant to sensitization both above and below 500°C. Figure 5 shows an extrapolation of the LTS data from the BWR work and superposition of this on a typical time-temperature (plotted as log time vs. 1/T) profile for a spent fuel waste package in the thermal environment of a tuff repository (Oversby and McCright, 1984). The prediction from the superposition is that even the heavily cold-worked AISI304L would not develop a sensitized microstructure {from the Briant et al, 1982 work cited above).…”
“…A value of 0.2 um/yr would appear to be adequate to describe conservatively the rate data so far acquired (Oversby and McCright, 1984). Extrapolation of these rates…”
Section: Summary and Analysis Of General Corrosion And Oxidation Testingmentioning
confidence: 96%
“…It appears that the molybdenum and nitrogen additions impede the diffusion of carbon atoms in austenitic stainless steels; therefore, the growth rates of carbide nuclei are slowed, and materials containing these alloy additions are considerably more resistant to sensitization both above and below 500°C. Figure 5 shows an extrapolation of the LTS data from the BWR work and superposition of this on a typical time-temperature (plotted as log time vs. 1/T) profile for a spent fuel waste package in the thermal environment of a tuff repository (Oversby and McCright, 1984). The prediction from the superposition is that even the heavily cold-worked AISI304L would not develop a sensitized microstructure {from the Briant et al, 1982 work cited above).…”
“…For 14C, 0.3 percent of the radionuclide inventory in a stored canister of spent fuel is released as a gas (Section 3.6) (Van Koynenburg et al 1984). For l291[, the radionuclide inventory in spent fuel may be concentrated in the pellet-cladding gap and/or on the grain boundaries of the fuel (Oversby and McCright 1985). The percentage of the total inventory is assumed to be 0.5 percent (Oversby and Wilson 1985).…”
Section: Performance Scenarios and Assumptionsmentioning
“…For 14C, 0.3 percent of the radionuclide inventory in a stored canister of spent fuel is released as a gas (Section 3.6) (Van Koynenburg et al 1984). For 12()1, the radionuclide inventory in spent fuel may be concentrated in the pellet-cladding gap and/or on the grain boundaries of the fuel (Oversby and McCright 1985). The percentage of the total inventory is assumed to be 0.5 percent (Oversby and Wilson 1985).…”
Section: Performance Scenarios and Assumptionsmentioning
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