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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Irradiation Testing: Facilities, Capabilities, and Experimental Designs
Presentation Title Neutron Irradiation as a Function of Temperature – Experiment (NIFT-E)
Author(s) Simon M. Pimblott, David Armstrong, Matthew Arrowood, Karina Assis, Chris Grovenor, Abbie Jones, Susan Ortner, Nassia Tzelepi, Stuart Maloy, Janelle Wharry
On-Site Speaker (Planned) Simon M. Pimblott
Abstract Scope As part of the U.S.–U.K. action plan to facilitate cooperation on advanced nuclear energy, the NSUF and NNUF have initiated the Neutron Irradiation as a Function of Temperature – Experiment (NIFT-E). This project is non-fueled drop-in materials experiment that will irradiate nuclear grade graphite, alumina forming austenitic stainless steel, and miscellaneous ferritic/martensitic steels, Grade 91 steel, high entropy alloys, and hetero nano-composite specimens utilizing eight irradiation capsules with passive temperature control. Material samples are being provided by various suppliers in the U.K. and U.S.A. The irradiation capsules have been designed at INL and will be fabricated in the U.K. with assembly scheduled before March 2024. Subsequently, irradiation will occur at the INL ATR with post irradiation examination INL HFEF and other suitable advanced characterization facilities in the U.S. and U.K. This work is supported by the DOE-NE Nuclear Science User Facilities program.
Proceedings Inclusion? Planned:
Keywords High-Entropy Alloys, High-Temperature Materials, Nuclear Materials

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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