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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
Presentation Title Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Author(s) David McClintock
On-Site Speaker (Planned) David McClintock
Abstract Scope High-energy radiation changes the microstructure and mechanical properties of structural components operated in high-radiation environments. These changes typically increase the risk of fracture, and the lifetime of these components are typically regulated by administrative lifetimes to limit the risk of failure during operation. Lifetime limits for a particular material and radiation environment are usually based on previous test results from similar materials and radiation environments, which frequently are not available for a particular material and radiation environment of interest. Post irradiation examination (PIE) of components after service is considered the best method for characterizing the radiation-induced changes that occur during operation. A PIE program is maintained at the Spallation Neutron Source (SNS) for targets and proton beam windows, where samples are regularly removed and characterized from these components after service. This presentation will discuss the current PIE program and component lifetime limit philosophies implemented at the SNS.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Mechanical Properties, Characterization

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Cavity Formation Induced by Swift Heavy Ion Irradiation in AlN/GaN
Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Developing a High-Performance Cluster Dynamics Code: Challenges and Lessons Learned
Effect of Applied Stress on Radiation-Induced Loop and Raft Formation in a BCC Metal
Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
In-situ Electron Microscopy Characterization of Deformation Mechanisms of Inconel 718 Irradiated with Simultaneous High Energy Protons and Spallation Neutrons
Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Materials Research for High-Power Accelerator Beam-Intercepting Devices
Modeling Galvanic Drawdown Separations Technique
Phase Field Modeling of Irradiation-Induced Amorphous-to-Crystalline (A-C) Transformations in Structural Ceramics
Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Small Scale Tests, Big Lessons Learned
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C

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