
doi: 10.2172/839519
The repository design includes a drip shield (BSC 2004 [DIRS 168489]) that provides protection for the waste package both as a barrier to seepage water contact and a physical barrier to potential rockfall. The purpose of the process-level models developed in this report is to model dry oxidation, general corrosion, and localized corrosion of the drip shield plate material, which is made of Ti Grade 7. This document is prepared according to ''Technical Work Plan For: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]). The models developed in this report are used by the waste package degradation analyses for TSPA-LA and serve as a basis to determine the performance of the drip shield. The drip shield may suffer from other forms of failure such as the hydrogen induced cracking (HIC) or stress corrosion cracking (SCC), or both. Stress corrosion cracking of the drip shield material is discussed in ''Stress Corrosion Cracking of the Drip Shield, the Waste Package Outer Barrier, and the Stainless Steel Structural Material'' (BSC 2004 [DIRS 169985]). Hydrogen induced cracking of the drip shield material is discussed in ''Hydrogen Induced Cracking of Drip Shield'' (BSC 2004 [DIRS 169847]).
And Non-Radioactive Wastes From Nuclear Facilities, Design, 36 Materials Science, Performance, Shields, Water, 12 Management Of Radioactive Wastes, Waste Forms, Stainless Steels, Corrosion, 08 Hydrogen, Stress Corrosion, Oxidation, Wastes, Plates, Simulation, Hydrogen
And Non-Radioactive Wastes From Nuclear Facilities, Design, 36 Materials Science, Performance, Shields, Water, 12 Management Of Radioactive Wastes, Waste Forms, Stainless Steels, Corrosion, 08 Hydrogen, Stress Corrosion, Oxidation, Wastes, Plates, Simulation, Hydrogen
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