Material Selection for Accident Tolerant Fuel Cladding

Pint, Bruce A.; Terrani, Kurt A.; Yamamoto, Yukinori; Snead, Lance Lewis

doi:10.1007/s40553-015-0056-7

Cited by 97 publications

(87 citation statements)

References 37 publications

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“…where ρ ox is assumed to be the density of oxygen in chromite, 1.44 g/cm 3 . The flux of Fe across the Crrich spinel layer may now be defined as:…”

Section: Corrosion Kineticsmentioning

confidence: 99%

“…Oxidation resistant FeCrAl alloys have been proposed as an accident tolerant fuel cladding to replace Zrbased alloys in light water reactors (LWRs) [1]. Under highly oxidizing environments characteristic of LWR severe accidents, the FeCrAl class of ferritic alloys offer oxidation rates roughly three orders of magnitude slower than Zr-based alloys [2,3]. The slow oxidation kinetics for these alloys can span over a wide temperature range extending all the way to near their melting point (~1500°C), given that a critical concentration of Cr and Al are present in the bulk [4].…”

Section: Introductionmentioning

confidence: 99%

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Uniform corrosion of FeCrAl alloys in LWR coolant environments

Terrani

Pint

Kim

et al. 2016

Journal of Nuclear Materials

192

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The corrosion behavior of commercial and model FeCrAl alloys and type 310 stainless steel was examined by autoclave tests and compared to Zircaloy-4, the reference cladding materials in light water reactors. The corrosion studies were carried out in three distinct water chemistry environments found in pressurized and boiling water reactor primary coolant loop conditions for up to one year. The structure and morphology of the oxides formed on the surface of these alloys was consistent with thermodynamic predictions. Spinel-type oxides were found to be present after hydrogen water chemistry exposures, while the oxygenated water tests resulted in the formation of very thin and protective hematite-type oxides. Unlike the alloys exposed to oxygenated water tests, the alloys tested in hydrogen water chemistry conditions experienced mass loss as a function of time. This mass loss was the result of net sum of mass gain due to parabolic oxidation and mass loss due to dissolution that also exhibits parabolic kinetics. The maximum thickness loss after one year of LWR water corrosion in the absence of irradiation was ~2μm, which is inconsequential for a ~300-500µm thick cladding.

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“…where ρ ox is assumed to be the density of oxygen in chromite, 1.44 g/cm 3 . The flux of Fe across the Crrich spinel layer may now be defined as:…”

Section: Corrosion Kineticsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Uniform corrosion of FeCrAl alloys in LWR coolant environments

Terrani

Pint

Kim

et al. 2016

Journal of Nuclear Materials

192

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show abstract

“…1 Under such high-temperature accident conditions, Zr alloys exhibit an exothermic oxidation reaction with water/steam that is accompanied by hydrogen gas release. The US Department of Energy's (DOE) industry-led Accident Tolerant Fuel (ATF) program is aimed at the development of alternative cladding and fuel concepts.…”

Section: Introductionmentioning

confidence: 99%

Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors

Maier

Yeom

Johnson

et al. 2017

JOM

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The cold spray coating process has been developed at the University of Wisconsin-Madison for the deposition of oxidation-resistant coatings on zirconium alloy light water reactor fuel cladding with the goal of improving accident tolerance during loss of coolant scenarios. Coatings of metallic (Cr), alloy (FeCrAl), and ceramic (Ti 2 AlC) materials were successfully deposited on zirconium alloy flats and cladding tube sections by optimizing the powder size, gas preheat temperature, pressure and composition, and other process parameters. The coatings were dense and exhibited excellent adhesion to the substrate. Evaluation of the samples after high-temperature oxidation tests at temperatures up to 1300°C showed that the cold spray coatings significantly mitigate oxidation kinetics because of the formation of thin passive oxide layers on the surface. The results of the study indicate that the cold spray coating process is a viable nearterm option for developing accident-tolerant zirconium alloy fuel cladding.

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“…In addition, the examined temperatures were generally low (< 1300°C) considering nuclear application with respect to accident scenarios. A plenty of studies have been dedicated to examining their behavior in high-temperature steam for nuclear application recently [25][26][27][28]. The comprehensive understanding of underlying mechanisms on growth and failure of protective alumina scale, particularly during the initial stage of oxidation, at elevated temperatures is not yet satisfying.…”

Section: Introductionmentioning

confidence: 99%

Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam

Tang

Jianu

Steinbrueck

et al. 2018

Journal of Nuclear Materials

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FeCrAl alloys are proposed and being intensively investigated as alternative accident tolerant fuel (ATF) cladding for nuclear fission application. Herein, the influence of major alloy elements (Cr and Al), reactive element effect and heating schedules on the oxidation behavior of FeCrAl alloys in steam up to 1500°C was examined. In case of transient ramp tests, catastrophic oxidation, i.e. rapid and complete consumption of the alloy, occurred during temperature ramp up to above 1200°C for specific alloys. The maximum compatible temperature of FeCrAl alloys in steam increases with raising Cr and Al content, decreasing heating rates during ramp period and doping of yttrium. Isothermal oxidation resulted in catastrophic oxidation at 1400°C for all examined alloys. However, formation of a protective alumina scale at 1500°C was ascertained despite partial melting. The occurrence of catastrophic oxidation seems to be controlled by dynamic competitive mechanisms between mass transfer of Al from the substrate and transport of oxidizing gas through the scale both toward the metal/oxide scale interface.

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Material Selection for Accident Tolerant Fuel Cladding

Cited by 97 publications

References 37 publications

Uniform corrosion of FeCrAl alloys in LWR coolant environments

Uniform corrosion of FeCrAl alloys in LWR coolant environments

Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors

Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam

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