Palladium interaction with silicon carbide

Gentile, M.; Xiao, Ping; Abram, T.J.

doi:10.1016/j.jnucmat.2015.03.013

Cited by 23 publications

(14 citation statements)

References 21 publications

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“…Furthermore, SiC begins to gradually lose mechanical integrity especially above 1700 C, by transformation of -SiC to -SiC and later thermal decomposition [26][27][28]. It is also widely noted that the SiC layer is subject to attack from palladium and rare earth elements [21,[29][30][31][32][33][34], although some studies led to contradictory results, showing significant Pd corrosion of SiC has not been identified [16,35].…”

Section: Triso-coated Particle Fuelmentioning

confidence: 99%

The measurement of silver diffusivity in zirconium carbide to study the release behavior of 110mAg in the ZrC TRISO-coated nuclear fuel particle

Yang

Allen

2016

Journal of Nuclear Materials

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The tri-structural isotropic (TRISO) coated particle fuel has been developed and used for high temperature gas-cooled reactors (HTGRs). It provides a unique robustness of the first barrier for the fission products. The TRISO fuel particle has typically consisted of a UO 2 or UCO kernel, surrounded by successive layers of porous carbon, dense inner pyrocarbon, silicon carbide, and dense outer pyrocarbon. During operation, however, the SiC layer has been known to release radioactive silver 110m Ag which makes maintenance more difficult and thus costly.Zirconium carbide has been considered as a promising alternative to the SiC fission product barrier. ZrC exhibits high temperature stability and possibly possesses superior Pd resistance, while the retention properties especially for silver have not been adequately studied.To help elucidate the diffusive behavior of silver in the ZrC coating of the TRISO-coated particle, a new diffusion experimental technique, called the encapsulating source method, has been developed by constructing a constant source diffusion couple between ZrC and Ag gas originated from Zr-Ag solid solution. SEM, WDS, EBSD Scanning electron microscopy (SEM), wavelength-dispersive X-ray spectroscopy (WDS), electron backscatter diffraction (EBSD) and optical methods were used to analyze the diffusion couple annealed at 1500 C. The resultant diffusion coefficient of Ag in single-crystalline ZrC 0.84 at 1500 C was experimentally determined to be about 2.8 (± 1.2) × 10 -17 m 2 /s.

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Section: Triso-coated Particle Fuelmentioning

confidence: 99%

The measurement of silver diffusivity in zirconium carbide to study the release behavior of 110mAg in the ZrC TRISO-coated nuclear fuel particle

Yang

Allen

2016

Journal of Nuclear Materials

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“…Ф Bo appears to be strongly influenced by the metal work function with a higher work function producing a higher Schottky barrier [12]. The highest increase for Pd devices is observed above 620 K. It has been reported that an exothermic reaction occurs between SiC and Pd in the 673 K-873 K range [31]. n generally decreases from 1.6 at 300 K to about 1.0 at 800 K for Ni, Co and Pd as shown in Figure 3.…”

Section: Resultsmentioning

confidence: 87%

Comparison of nickel, cobalt, palladium, and tungsten Schottky contacts on n-4 H -silicon carbide

Gora

Chawanda

Nyamhere

et al. 2018

Physica B: Condensed Matter

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We have investigated the current-voltage (I-V) characteristics of nickel (Ni), cobalt (Co), tungsten (W) and palladium (Pd) Schottky contacts on n-type 4H-SiC in the 300-800 K temperature range. Results extracted from I-V measurements of Schottky barrier diodes showed that barrier height (Ф Bo ) and ideality factor (n) were strongly dependent on temperature. Schottky barrier heights for contacts of all the metals showed an increase with temperature between 300 K and 800 K. This was attributed to barrier inhomogeneities at the interface between the metal and the semiconductor, which resulted in a distribution of barrier heights at the interface. Ideality factors of Ni, Co and Pd decreased from 1.6 to 1.0 and for W the ideality factor decreased from 1.1 to 1.0 when the temperature was increased from 300 K to 800 K respectively. The device parameters were compared to assess advantages and disadvantages of the metals for envisaged applications.

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“…Other initiatives aimed at increasing tolerance to fault conditions, so-called 'accident tolerant fuels' (ATFs) are also being progressed, e.g. SiC-SiC composite cladding [13,14].…”

Section: Developments In Fuel Technologymentioning

confidence: 99%

Challenges to deployment of twenty-first century nuclear reactor systems

Ion¹

2017

Proc. R. Soc. A.

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The science and engineering of materials have always been fundamental to the success of nuclear power to date. They are also the key to the successful deployment and operation of a new generation of nuclear reactor systems and their associated fuel cycles. This article reflects on some of the historical issues, the challenges still prevalent today and the requirement for significant ongoing materials R&D and discusses the potential role of small modular reactors.

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Palladium interaction with silicon carbide

Cited by 23 publications

References 21 publications

The measurement of silver diffusivity in zirconium carbide to study the release behavior of 110mAg in the ZrC TRISO-coated nuclear fuel particle

The measurement of silver diffusivity in zirconium carbide to study the release behavior of 110mAg in the ZrC TRISO-coated nuclear fuel particle

Comparison of nickel, cobalt, palladium, and tungsten Schottky contacts on n-4 H -silicon carbide

Challenges to deployment of twenty-first century nuclear reactor systems

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