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首页> 外文期刊>Journal of Materials Science >Powder metallurgical fabrication of zirconium matrix cermet nuclear fuels
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Powder metallurgical fabrication of zirconium matrix cermet nuclear fuels

机译：锆基金属陶瓷核燃料的粉末冶金制造

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摘要

Two powder metallurgical fabrication methods for a zirconium-based cermet nuclear dispersion fuel with oxide microspheres have been demonstrated. A multi-pass, cold-drawing process is shown to have excellent capability to control the final matrix density, though it requires several high-temperature anneals during fabrication to relieve strain hardening and increase matrix-particle bonding. Severe oxide particle damage was observed in the cold-drawn fuel pin and was likely a result of high matrix deformation resistance at room temperature. A single-pass, hot-extrusion process has been demonstrated and was shown to be capable of providing a dense matrix phase with less particle damage. Both processes were shown to be effective fabrication methods for a zirconium-based cermet, and the process variables may be controlled to create the desired fuel properties.
机译：已经证明了两种具有氧化物微球的锆基金属陶瓷核分散燃料的粉末冶金制造方法。尽管在制造过程中需要多次高温退火以减轻应变硬化并增加基体与颗粒之间的结合，但多道次冷拔工艺具有出色的控制最终基体密度的能力。在冷拔燃料销中观察到严重的氧化物颗粒损坏，这很可能是室温下较高的基体抗变形性的结果。已经证明了单程热挤压工艺，并证明该工艺能够提供致密的基体相，而颗粒损坏更少。两种工艺均被证明是基于锆的金属陶瓷的有效制造方法，并且可以控制工艺变量以产生所需的燃料性能。

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