2015
DOI: 10.2172/1253237
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Evaluation on the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys

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Cited by 7 publications
(10 citation statements)
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“…Irradiation studies of model FeCrAl alloys, which are candidates for ATF cladding, indicate that the dominant impact of the neutron radiation environment is the accelerated formation of Cr-rich αʹ precipitates [24]. These precipitates form at high temperatures (300°C-400°C) as a result of the aging process, but their formation is accelerated under neutron irradiation.…”
Section: Aged Fecral Modified Burst Tube Testingmentioning
confidence: 99%
“…Irradiation studies of model FeCrAl alloys, which are candidates for ATF cladding, indicate that the dominant impact of the neutron radiation environment is the accelerated formation of Cr-rich αʹ precipitates [24]. These precipitates form at high temperatures (300°C-400°C) as a result of the aging process, but their formation is accelerated under neutron irradiation.…”
Section: Aged Fecral Modified Burst Tube Testingmentioning
confidence: 99%
“…Generation I alloys are ORNL developed model FeCrAl alloys with Y additions used to screen primary composition effects (Cr and Al) on radiation tolerance, as well as other key performance aspects such as welding [21], oxidation [4,9,22], burst behavior [23], and corrosion [24]. Generation I alloys are otherwise referenced as B-series alloys or model alloys in previous reports [3,[5][6][7][8][9][10][11][12][13][14][15][16]. Generation II alloys are ORNL developed FeCrAl alloys with Y additions that also include additional minor alloying elements such as Mo, Nb, Si, and/or C. Minor alloy additions and further refinement in thermomechanical processing for Generation II alloys means generally a higher strength alloy at elevated temperatures compared to Generation I alloys with identical or similar Cr and/or Al contents [3].…”
Section: 1/ Materialsmentioning
confidence: 99%
“…Phase I was based around exploratory studies of the Fe-Cr-Al design space and focused primarily on assessment of how various aspects of alloy performance were affected by major alloying element composition. The alloys utilized for these investigations were simple FeCrAl-Y model alloys and are typically regarded as Generation I FeCrAl alloys within reporting [3,[5][6][7][8][9][10][11][12][13][14][15][16]. These Phase I alloys have demonstrated that higher Cr and Al contents are generally more desirable for maximizing corrosion and/or oxidation resistance but too much of either can limit alloy applications; excessive Cr additions increase the formation of embrittling Cr-rich αʹ precipitates [17][18][19], while high Al content results in failure during the seamless tube extrusion process required for LWR cladding fabrication [20].…”
Section: / Introductionmentioning
confidence: 99%
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“…Under neutron irradiation, the formation of other microstructural features including dislocation loops can increase the hardening and embrittlement response of FeCrAl alloys [3]. Preliminary studies on a commercial FeCrAl alloy have shown that microstructural features, such as grain boundaries and dislocation cell networks can alter the radiation response of alloys [13]. The issue is that such microstructural features which could be beneficial towards the radiation tolerance of a FeCrAl weldment can become lost under fusion-based welding leading to fusion zones in weldments with reduced tolerance to radiation.…”
Section: Introductionmentioning
confidence: 99%