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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Irradiation Testing: Facilities, Capabilities, and Experimental Designs
Presentation Title Increasing Ion Irradiation Sample Throughput with Gas Implantation Gradients
Author(s) Aaron Gabriel S. Penders, Charles A. Hirst, Alexander Flick, Fabian Naab, Logan Nicholas Clowers, Valentin Pauly, Lauren M. Garrison, Cody A. Dennett, Michael Philip Short, Gary S. Was
On-Site Speaker (Planned) Aaron Gabriel S. Penders
Abstract Scope Contemporary methods to investigate the role of radiation damage and transmutation gas production (H, He) by ion irradiation are to conduct individual experiments, performed at fixed doses (dpa) and gas implantation values (appm). In utilizing controlled beam-line shutters, broad scopes of the appm/dpa parameter space for each shuttered ion beam-line can be explored within a single irradiation experiment. This approach significantly increases the sample throughput by several orders of magnitude, thus accessing numerous combinations of gas implantation and dpa values. Lithography and atomic layer deposition enable precisely discretized sample geometries, facilitating subsequent microscopical investigations of the irradiated microstructure at known implantation doses and damage rates. The application of this gas-gradient technique to predict fast reactor irradiation of alloy T91 using a He-gradient, and fusion blanket conditions using both H- and Hegradients will be presented, along with (S)TEM results of irradiated microstructures. This research was supported by Commonwealth Fusion Systems.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization, Other

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Accelerated Irradiation Creep Testing of Structural Materials for Advanced Reactors
Accelerating the Pace of Radiation Damage Experiments through Novel Sample Geometries, Beam Line Architecture, and Machine Learning Analysis
Advancing Post-irradiation Examination of Structural Materials in INL Facilities
Advancing Thermo-physical Property Characterization Techniques and Methods for Irradiated Nuclear Fuels
Atom Probe Tomography Examinations of Bulk Zircaloy Irradiated at Nominally 410°C
Atom Probe Tomography (APT) Characterization of Annular U-Zr Metallic Fuel Cladded with HT-9
Challenges and Solutions for Fast Neutron Irradiation of Bulk Material Specimens
Comparison between Ion and Neutron Irradiated Tungsten to Simulate Damage in Commercial Nuclear Fusion Reactors
Deployment and Testing of a Fiber-based Instrument for In-reactor Thermal Property Measurements at MIT Research Reactor
Developing Irradiation Experiments to Enable Characterization and Qualification of Advanced Nuclear Materials
E-21: High-Throughput Study of Temperature Effects on Void Swelling in Ion Irradiated SS304
Electron Energy Loss Spectroscopy (EELS) Characterization of Fuel Cladding Chemical Interaction (FCCI) Region in U-Zr Metallic Fuel Cladded with HT-9
Harnessing HFIR Neutron Irradiations: Innovative Experiments and Standardized Capabilities
Increasing Ion Irradiation Sample Throughput with Gas Implantation Gradients
INL’s Holistic Approach to Post-irradiation Examination of Nuclear Fuel Systems
INL’s Mission Incorporating Neutrons in Post-irradiation Examination of Nuclear Materials
Investigating Water Ice Under Ion Irradiation for Future Exploration of Europa
Irradiation Testing of 316H Stainless Steel at Oak Ridge National Laboratory
Irradiation Vehicles for Materials Separate Effects Experiments Supporting the Tritium Modernization Program
Measurement of Hydrogen Vapor Pressure Over Two-phase Zirconium/Zirconium Hydride Material between 275°C and 400°C Under the Effects of Neutron Irradiation
Neutron Irradiation as a Function of Temperature – Experiment (NIFT-E)
Nuclear Fuel Salt Irradiation and Post-irradiation Processing Capabilities at The Ohio State University Research Reactor
Post-irradiation Examination of AGR-5/6/7 TRISO Fuel with Micro X-ray Computed Tomography
The Role of Nuclear Science User Facilities in Nuclear Energy Materials Research and Development
Ultrafast-Electron-diffraction Studies of Radiation-damaged Materials: An Example on the Melting Behavior of He-implanted W
Westinghouse Hot Cell Facility and Laboratories

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