Palladium corrosion of the SiC layer in TRISO particle fuels: A separate effects study to assess mechanisms for palladium attack

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Progress in Nuclear Energy Pub Date : 2026-04-01 Epub Date: 2026-02-07 DOI:10.1016/j.pnucene.2026.106290
Steven J. Cavazos , Julian Valdez , Jordan Stone , Carlos Hernandez , Da Teng , Gisele George , Brian D. Wirth , Elizabeth Sooby
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引用次数: 0

Abstract

Palladium (Pd) is a fission product of particular interest for TRISO fuel performance due to its propensity to chemically corrode the SiC layer. Post irradiation examination experiments on irradiated TRISO particles confirm the formation of several palladium silicide intermetallics, such as PdSi and Pd2Si, in the SiC layer. A corroded SiC layer can lead to TRISO particle failure, resulting in higher fission product release. However, the specific transport mechanisms driving Pd corrosion remain difficult to isolate during irradiation tests. Therefore, this study aims to quantify the thermal diffusion kinetics of Pd through the OPyC layer and its subsequent interaction with the SiC layer under separate effects conditions. The research presented uses surrogate TRISO particles, with Pd-rich coatings on the OPyC layer, and high temperature separate effects testing to examine the behavior of Pd diffusion and chemical interactions on the TRISO particle layers. Physical vapor deposition techniques were used to deposit 200 nm of Pd on surrogate TRISO particles, which were then annealed at various high temperatures. SEM/EDS characterization was used to evaluate the annealed microstructures and revealed a distinct thermal activation threshold. While no Pd diffusion was observed at 850 °C after 10 h, annealing at 1150 °C resulted in complete diffusion through the OPyC layer and Pd-SiC interaction along the OPyC-SiC interface. Pd diffusion was accompanied by OPyC degradation, including OPyC cracking and Si migration to the particle surface. These findings establish 850–1150 °C as a critical transition regime for Pd chemical attack, providing experimentally derived reaction limits necessary for validating fuel performance models and defining safety margins for high-temperature transients. This research characterizes thermally driven Pd diffusion in TRISO fuel layers under non-irradiated conditions, contributing to improved predictive capability for fuel integrity in advanced nuclear energy systems.
TRISO颗粒燃料中碳化硅层的钯腐蚀:评估钯攻击机制的单独影响研究
钯(Pd)是一种对三iso燃料性能特别感兴趣的裂变产物,因为它倾向于化学腐蚀SiC层。对辐照后的TRISO颗粒进行辐照后检测实验,证实在SiC层中形成了PdSi和Pd2Si等几种硅化钯金属间化合物。腐蚀的SiC层会导致TRISO颗粒失效,导致更高的裂变产物释放。然而,在辐照试验中,驱动Pd腐蚀的特定传输机制仍然难以分离。因此,本研究旨在量化Pd在不同作用条件下通过OPyC层及其随后与SiC层相互作用的热扩散动力学。本研究采用替代TRISO颗粒,在OPyC层上涂覆富Pd涂层,并通过高温分离效应测试来研究Pd在TRISO颗粒层上的扩散行为和化学相互作用。采用物理气相沉积技术将200 nm的Pd沉积在替代的TRISO颗粒上,然后在不同的高温下退火。利用SEM/EDS表征对退火后的微观结构进行了评价,发现了明显的热活化阈值。850℃退火10 h后未观察到Pd的扩散,而1150℃退火使OPyC层完全扩散,Pd- sic沿OPyC- sic界面相互作用。Pd扩散伴随着OPyC的降解,包括OPyC的开裂和Si向颗粒表面的迁移。这些发现确定850-1150°C是Pd化学攻击的临界过渡区,为验证燃料性能模型和定义高温瞬态的安全裕度提供了实验推导的反应极限。本研究表征了非辐照条件下三iso燃料层中热驱动Pd扩散,有助于提高先进核能系统中燃料完整性的预测能力。
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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