Database on Performance of Neutron Irradiated FeCrAl Alloys

Status of FeCrAl ODS Irradiations in the High Flux Isotope Reactor

“…The test matrix has been developed to provide cross compatibility with irradiation conditions of the FCAY and FCAT irradiation programs [10] while also providing the high dose radiation response of these alloys. High dose responses are of interest as FeCrAl ODS alloys could have potential applications in other nuclear reactor designs such as fast reactors being developed by TerraPower, LLC.…”

Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR

“…The AMOW irradiation campaign targets neutron irradiations in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) due to the HFIR's ability to generate high damage doses (~8-12 dpa per calendar year in pure Fe), allowing for rapid screening of radiation tolerance. The AMOW campaign also leverages previous irradiation campaigns and irradiation vehicle design concepts including the FCAY [9] and FCAT campaigns [10]. The AMOW campaign is structured to capture at least three irradiations doses (nominally 8, 16, and 50 dpa) at three separate temperatures: 300°C, 385°C, and 525°C.…”

Status of Wrought FeCrAl-UO₂ Capsules Irradiated in the Advanced Test Reactor

“…One Generation I, two Generation II, and one commercial alloy were selected as candidate cladding. Details on the delineation between Generation I and Generation II FeCrAl alloys can be found in previous reports of the same program [16,17]. The Generation I alloy, B125Y3 was thermo-mechanically processed using two different techniques to produce a large grain (LG) variant and small grain (SG) variant with identical compositions.…”