Conference Logo ProgramMaster Logo
Conference Tools for 2027 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools

About this Abstract

Meeting 2027 TMS Annual Meeting & Exhibition
Symposium Enabling Nuclear Materials Innovation via the Nuclear Science User Facility Capabilities
Presentation Title Development of the in-situ annealing capability integrated with in-situ mechanical testing with SEM EBSD for irradiated materials.
Author(s) Soyoung Kang, Maxim Gussev
On-Site Speaker (Planned) Soyoung Kang
Abstract Scope An in-situ annealing capability is being developed for integration with an existing in-situ mechanical testing system coupled with scanning electron microscopy and electron backscatter diffraction (SEM-EBSD) for the characterization of irradiated materials. The system will enable controlled-temperature annealing experiments with or without simultaneous mechanical loading, allowing direct observation of microstructural evolution during thermal treatment. Two sample holder configurations are being developed: one dedicated to annealing experiments and another supporting combined annealing and mechanical testing. The development required overcoming several technical challenges, including achieving uniform specimen heating, maintaining reliable thermal contact between the heater and specimen, and obtaining high-quality EBSD pattern at elevated temperatures. Pilot experiments using non-irradiated materials have been conducted to validate the heating design, temperature control, and EBSD performance before application to irradiated specimens. This capability will provide opportunities to investigate the temperature dependent evolution of radiation-induced defects and their influence on the mechanical behavior of irradiated materials.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization, Mechanical Properties

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization of Irradiated UO2 Fuels
Advanced Test Reactor Pilot Project: A Foundation for NSUFs
AI-Assisted Development of Agent-Ready, Compact Heaters for High-Temperature Nuclear Materials Research at NSLS-II
Compact Helium Ion Gun for Dual Beam Capabilities at the University of Wisconsin-Madison Ion Beam Laboratory.
Deformation mode map of 316 stainless steel from 12 MeV proton irradiation
Development of the in-situ annealing capability integrated with in-situ mechanical testing with SEM EBSD for irradiated materials.
Effects of High Dose Neutron Irradiation at Light Water Reactor-Relevant Temperatures on the Mechanical Properties of SiC Composites
Enabling the Understanding of Irradiation Effects and Performance in Fe-Cr Ferritic Alloys
Evaluation of Microstructural Integrity of ATR-Irradiated Yttrium Hydride (YHₓ)
High-Throughput Characterization of Microstructure-Mechanical Property Relationships of Implantation-Gradient Triple-Ion Irradiated Nickel
Hydrothermal Ageing of CVD (Chemical Vapour Deposited) SiC under Proton Irradiation
Implementing best practices in conducting focused-ion beam tomography for optimizing experimentally-informed three-dimensional mesoscale prediction of surface resilience in nuclear structural materials
In-Situ Real-Time Measurement of Transmissivity of Optical Materials under Irradiation and Concurrent Heating
Investigations on the Electrical and Thermal Properties of Chemical Vapor Deposited Nitrogen and Neutron Transmutation Doped (NTD) Phosphorus in β-SiC.
Lessons Learned in Irradiating Steel and Graphite Specimens in Flibe at the MIT Reactor
Linking Irradiated Microstructures to Mechanical Performance: NSUF Studies of Advanced Reactor Materials
Mechanical and Microstructural Study of Neutron Irradiated Refractory High Entropy Alloys
Microstructural Evolution of Beryllium Carbide Under In Situ Dual-Ion Irradiation
Microstructure Evolution of Mn containing FeCrNi based Multi Principal Element Alloys processed via SPS under in-situ ion Irradiation in a TEM
NSUF Campaigns as Drivers of Scientific Innovation in the Age of AI/ML
ROADRUNNER: Accelerated Burnup Testing to Advance Uranium Nitride Fuel Qualification
Solute Behavior in Thermally Aged vs Neutron-Irradiated Commercial Pressure Vessel Steel Heat Affected Zone Using Atom Probe Tomography
Synchrotron XRD and atomistic modeling of solute effects on ordering in Ni-Cr-based alloys
The beginnings of the NSUF
The Neutron Radiography and Tomography Beamline at the MIT Reactor
The Nuclear Materials Performance Division and the Structural Properties Laboratory at Idaho National Laboratory
X-ray Vision for Nuclear Science: NSUF-Enabled XCT for the Nuclear Community

Questions about ProgramMaster? Contact programming@programmaster.org | TMS Privacy Policy | Accessibility Statement