Experimentally Known Properties of U-10Zr Alloys: A Critical Review

Janney, Dawn E.; Hayes, S. L.

doi:10.1080/00295450.2018.1435137

Cited by 38 publications

(11 citation statements)

References 58 publications

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“…The DSC results show the presence of two phase transitions upon heating while only one phase transition is detected upon cooling. The reversible phase transition (with an onset temperature of 606°C upon heating) is consistent with the available U-Zr phase diagrams [25] and corresponds to a δ → γ transition. The additional phase transition (which occurs above 400°C upon heating, however, is not detected upon cooling) is consistent with the presence of non-equilibrium phases in the as-cast microstructure.…”

Section: Thermophysical Property Characterizationsupporting

confidence: 82%

“…Since the fuel was rolled and annealed, the yield stress was expected higher than the yield stress of the arcmelted U-50Zr due to work-hardening effects. The fuel used in this study was an as-fabricated condition where large grains (with sub-grains) were present, and the yield stress was also expected to be significantly lower than that of the rolled and annealed material reported by Rough [25]. Thus, our expectation is the yield stress is close to the ECM value rather than CF value.…”

Section: Nanoindentation Testsmentioning

confidence: 78%

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U-50Zr Microstructure and Property Assessment for LWR Applications

Beausoleil

Cinbiz

Yao

et al. 2021

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Section: Thermophysical Property Characterizationsupporting

confidence: 82%

Section: Nanoindentation Testsmentioning

confidence: 78%

U-50Zr Microstructure and Property Assessment for LWR Applications

Beausoleil

Cinbiz

Yao

et al. 2021

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“…Tellurium is considered a metalloid and has a relatively low melting temperature of 723 K (450 °C) and boiling point of 1263 K (990 °C), which leads to a narrow temperature range where the element can remain in a liquid state. Loss of Te primarily occurred during its addition to the U-10Zr (wt.%) button, which requires an increased amount of energy to fully liquefy having a solidus temperature of approximately 1521 K (1248 °C) and liquidus temperature between 1628 K–1633 K (1355 °C–1360 °C) 18 . Once Te was homogenized into the U-10Zr (wt.%) alloy, it became stabilized by the formation of Zr-Te precipitates (further discussed in later sections).…”

Section: Resultsmentioning

confidence: 99%

“…It should be noted that the matrix, a combination of a primary light phase with a dispersed light-grey phase, is the expected phase formation of the U-Zr system in the as-cast condition. Extensive work has been done on U-Zr alloys, and in particular the U-10Zr (wt.%) 18–24 . Furthermore, the phase formations between U and Zr in the as-cast condition, specifically the co-formation of the α-U and δ-UZr 2 phases, have been discussed elsewhere 19,23 .…”

Section: Resultsmentioning

confidence: 99%

Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel

Jerred

Khanal

Benson

et al. 2019

Sci Rep

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Phase-stability in a U-Zr-Te-Nd multi-component metallic fuel for advanced nuclear reactors is systematically investigated by taking into account binary, ternary and quaternary interactions between elements involved. Historically, the onset of fuel-cladding chemical interactions (FCCI) greatly limits the burnup potential of U-Zr fuels primarily due to interactions between lanthanide fission products and cladding constituents. Tellurium (Te) is evaluated as a potential additive for U-Zr fuels to bind with lanthanide fission products, e.g. neodymium (Nd), negating or mitigating the FCCI effect. Potential fresh fuel alloy compositions with the Te additive, U-Zr-Te, are characterized. Te is found to completely bind with Zr within the U-Zr matrix. Alloys simulating the formation of the lanthanide element Nd within U-Zr-Te are also evaluated, where the Te-Nd binary interaction dominates and NdTe is found to form as a high temperature stable compound. The experimental observations agree well with the trends obtained from density functional theory calculations. According to the calculated enthalpy of mixing, Zr-Te compound formation is favored in the U-Zr-Te alloy whereas NdTe compound formation is favored in the U-Zr-Te-Nd alloy. Further, the calculated charge density distribution and density of states provide sound understanding of the mutual chemical interactions between elements and phase-stability within the multi-component fuel.

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“…), are very expensive and time-costly, because number of out-of-file tests, in-reactor (irradiation) tests, and post-irradiation examination (PIE) are required to understand and be able to predict the material performance and degradation. 4 The goal of this present study is to use machine-learning to aid/bridge the mechanistic understanding of U-10wt.% Zr (U-10Zr) based metallic fuel, a primary candidate for next generation sodium cooled fast reactors (SFRs), 5 and eventually accelerate fuel qualification and licensing for commercial use.…”

Section: Introductionmentioning

confidence: 99%

Advanced Characterization-Informed Framework and Quantitative Insight to Irradiated Annular U-10Zr Metallic Fuels

Cai

Salvato

et al. 2022

Preprint

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U-10Zr-based metallic nuclear fuel is a promising fuel candidate for next-generation sodium-cooled fast reactors. Idaho National Laboratory’s research experience for this type of fuel dates back to the 1960s. Idaho National Laboratory researchers have accumulated a considerable amount of experience and knowledge regarding fuel performance at the engineering scale. The limitation of advanced characterization and lack of proper data analysis tools prevented a mechanistic understanding of fuel microstructure evolution and properties degradation during irradiation. This paper proposed a new workflow, coupled with domain knowledge obtained by advanced post-irradiation examination methods, to provide unprecedented and quantified insights into the fission gas bubbles and pores, and lanthanide distribution in an annular fuel irradiated in the Advanced Test Reactor. In the study, researchers identify and confirm that the Zr-bearing secondary phases exist and generate the quantitative ratios of seven microstructures along the thermal gradient. Moreover, the distributions of fission gas bubbles on two samples of U-10Zr advanced fuels were quantitatively compared. Conclusive findings were obtained and allowed for evaluation of the lanthanide transportation through connected bubbles based on approximately 67,000 fission gas bubbles of the two advanced samples.

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Experimentally Known Properties of U-10Zr Alloys: A Critical Review

Cited by 38 publications

References 58 publications

U-50Zr Microstructure and Property Assessment for LWR Applications

U-50Zr Microstructure and Property Assessment for LWR Applications

Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel

Advanced Characterization-Informed Framework and Quantitative Insight to Irradiated Annular U-10Zr Metallic Fuels

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