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Meeting 2027 TMS Annual Meeting & Exhibition
Symposium Enabling Nuclear Materials Innovation via the Nuclear Science User Facility Capabilities
Presentation Title Implementing best practices in conducting focused-ion beam tomography for optimizing experimentally-informed three-dimensional mesoscale prediction of surface resilience in nuclear structural materials
Author(s) Trishelle Copeland-Johnson, Devin Hall, Jeremy Lopez, Jason Uwaeze, Rahul Kancharla, Stacey Whitmore, Rajiv Khadka, Chaitanya Bhave, Mario Matos, Matthew W. Anderson, Fei Xu, Christopher Bearcroft, Tanner Mauseth, Nicholas Nelson
On-Site Speaker (Planned) Trishelle Copeland-Johnson
Abstract Scope Three-dimensional (3D) focused-ion beam (FIB) tomography generates sub-micron resolution volumes capturing complex surface phenomena like corrosion; critical validation data for predictive 3D mesoscale models to design nuclear structural materials. Prior work applying FIB tomography to study Cr dissolution in Ni-Cr-Mo alloys after molten salt corrosion revealed technical challenges involving standard operating procedures, computational cost, and data export. These challenges were addressed via a case study using Idaho National Laboratory's ThermoFisher G4 UX dual beam FIB microscope through: 1) standard operating procedures for 3D data acquisition; 2) export/release procedures via the Nuclear Research Data System (NRDS), supported by the Nuclear Science User Facility (NSUF) program; and 3) Computational Ultraspatial Tomography Toolkit for High-Resolution Object Analysis Tools (CUT/THROAT), an open-source visualization tool deployed on NRDS for preliminary dataset inspection before intensive downstream processing. These contributions lower barriers to generating 3D mesoscale validation data, expanding accessibility to NSUF users designing resilient nuclear materials.
Proceedings Inclusion? Planned:
Keywords Characterization, Computational Materials Science & Engineering, Nuclear Materials

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

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