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Field, Kevin G.
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Publications (5/5 displayed)
- 2018Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR
- 2017Radiation Induced Segregation at Low Angle Grain Boundaries in Steels: NSUF 2017 Milestone Report
- 2017Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor
- 2016Database on Performance of Neutron Irradiated FeCrAl Alloys
- 2015Evaluation on the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys
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report
Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR
Abstract
This report provides a summary of the irradiation vehicle design and thermal analysis of sub-sized tensile specimens generated through traditional processing routes (e.g. wrought alloys), powder metallurgy techniques (e.g. oxide dispersion strengthened alloys), and through additive manufacturing techniques. The neutron irradiations are planned for placement in the flux trap of the High Flux Isotope Reactor (HFIR). The irradiation vehicles are designed to have nominal target temperatures of 300°C, 385°C or 525°C with each test train accommodating 32 sub-sized tensile specimens.