ProgramMaster Logo
Conference Tools for MS&T23: Materials Science & Technology
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting MS&T23: Materials Science & Technology
Symposium Progressive Solutions to Improve Corrosion Resistance of Nuclear Waste Storage Materials
Presentation Title Evaluating the Sensitivities of an Environmental Cracking LEFM-based Model for Use in Realistic Lifetime Predictions of Nuclear Waste Storage Casks
Author(s) Sarah Blust, James Burns
On-Site Speaker (Planned) Sarah Blust
Abstract Scope Spent nuclear fuel (SNF) is currently stored across the US in passively-cooled stainless steel dry cask storage (DCS) systems. Due to the design of DCS systems, aerosols from the outside environment are able to deposit on the stainless-steel canisters. Over time the deposited aerosols will deliquesce on canisters to form concentrated salt brines resulting in localized corrosion, which when coupled with the high residual stress around welds can lead to stress corrosion cracking (SCC). Work has been done to generate SCC data and investigate sensitivities to environmental factors and microstructure variability. Concurrently, a probabilistic linear elastic fracture mechanics (LEFM) based model has been created to assist with lifetime management of DCS systems across the US. The work presented will look at the impact of individual modeling inputs on DCS lifetime predictions and demonstrate the utilization of this model for real-world SNF applications.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

An Integrated Data-driven and Physics-driven Approach Towards Discovering Optimal Nuclear Waste Immobilization Glass
Chloride-induced Stress Corrosion Crack in Spent Nuclear Fuel Canisters: Understanding and Mitigating
Evaluating the Sensitivities of an Environmental Cracking LEFM-based Model for Use in Realistic Lifetime Predictions of Nuclear Waste Storage Casks
Gel Layer Structures and Properties of Silicate Glasses: Understanding the Corrosion of Glasses for Nuclear Waste Disposal
SiON Protective Coatings for U-shaped Stainless Steel
Structural Descriptors Controlling Sulfur Solubility in Borosilicate Glasses
Topological Model of the Dissolution Kinetics of Borosilicate Glasses

Questions about ProgramMaster? Contact programming@programmaster.org