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首页> 外文期刊>Metallurgical and Materials Transactions, E. Materials for Energy Systems >Microstructural Characterization of the U-9.1Mo Fuel/AA6061 Cladding Interface in Friction-Bonded Monolithic Fuel Plates Irradiated in the RERTR-6 Experiment
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Microstructural Characterization of the U-9.1Mo Fuel/AA6061 Cladding Interface in Friction-Bonded Monolithic Fuel Plates Irradiated in the RERTR-6 Experiment

机译：在RERTR-6实验中施加摩擦粘合整体燃料板中U-9.1MO燃料/ AA6061覆层界面的微观结构表征

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Low-enrichment ( U < 20 pct) U-Mo monolithic fuel is being developed for use in research and test reactors. The earliest design for this fuel that was investigated via reactor testing consisted of a nominally U-10Mo fuel foil encased in AA6061 (Al-6061) cladding. For a fuel design to be deemed adequate for final use in a reactor, it must maintain dimensional stability and retain fission products throughout irradiation, which means that there must be good integrity at the fuel foil/cladding interface. To investigate the nature of the fuel/cladding interface for this fuel type after irradiation, fuel plates were fabricated using a friction bonding process, tested in INL's advanced test reactor (ATR), and then subsequently characterized using optical metallography, scanning electron microscopy, and transmission electron microscopy. Results of this characterization showed that the fuel/cladding interaction layers present at the U-Mo fuel/AA6061 cladding interface after fabrication became amorphous during irradiation. Up to two main interaction layers, based on composition, could be found at the fuel/cladding interface, depending on location. After irradiation, an Al-rich layer contained very few fission gas bubbles, but did exhibit Xe enrichment near the AA6061 cladding interface. Another layer, which contained more Si, had more observable fission gas bubbles. In the samples produced using a focused ion beam at the interaction zone/AA6061 cladding interface, possible indications of porosity/debonding were found, which suggested that the interface in this location is relatively weak.
机译：富集（U <20 PCT）U-Mo单片燃料正在开发用于研究和测试反应堆。通过反应器测试研究的这种燃料的最早设计由封装在AA6061（AL-6061）包层中的标称U-10MO燃料箔组成。对于燃料设计被视为反应器中最终用途的充分性，它必须保持尺寸稳定性并在整个辐射过程中保留裂变产物，这意味着在燃料箔/包层界面上必须具有良好的完整性。为了探测照射后燃料/包层界面的性质，使用摩擦粘合过程制造燃料板，在INL的先进试验反应器（ATR）中测试，然后使用光学金相，扫描电子显微镜和扫描电子显微镜和透射电子显微镜。该表征的结果表明，在辐照期间，在制造过程中，在U-Mo燃料/ AA6061包层界面处存在于U-Mo燃料/ AA6061包层的燃料/包覆相互作用层。基于组合物最多可以在燃料/包层接口中找到最多两个主要的相互作用层，具体取决于位置。辐照后，富含铝层的裂变气泡含有非常少量的裂变气泡，但在AA6061熔覆界面附近表现出XE富集。含有更多Si的另一层具有更高可观察的裂变气泡。在使用聚焦离子束在相互作用区/ AA6061包层界面产生的样品中，发现了孔隙度/剥离的可能指示，这表明该位置中的界面相对较弱。

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