Densification Behaviors of Zirconium Carbide with Silicon Additive Produced by Spark Plasma Sintering

IF 2.3 2区物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Materials and Energy Pub Date : 2025-06-08 DOI:10.1016/j.nme.2025.101958

Qisen Ren , Lixiang Wu , Yang Liu , Jun Yan , Yehong Liao , Weiming Guo , Weiqiang Liu

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Abstract

Zirconium Carbide (ZrC) is a promising matrix material candidate for Fully Ceramic Microencapsulated (FCM) fuel. Using Spark Plasma Sintering (SPS) and introducing a certain amount of Si as sintering additive can effectively promote the sintering densification process, reduce the sintering temperature, and avoid adverse effects on the microstructure and properties of the matrix and fuel phase during high-temperature sintering process. Adopting SPS process, this article investigates the effects of Si addition, sintering temperature, sintering pressure, and holding time on the density and microstructure of ZrC sample. The results indicate that the sintering temperature and Si addition amount are the key factors affecting the densification of ZrC, while the sintering pressure and holding time have a relatively small impact. The addition of Si could effectively promote the densification procedure during ZrC sintering. Introducing 2.5 wt% of Si increased the maximum densification rate by more than 200 % compared to that of pure ZrC, under sintering condition of 1600 °C/20 MPa/10 min.

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火花等离子烧结硅添加剂对碳化锆致密化行为的影响

碳化锆（ZrC）是一种很有前途的全陶瓷微囊化（FCM）燃料的候选基体材料。采用火花等离子烧结（SPS）技术，引入一定量的Si作为烧结添加剂，可以有效地促进烧结致密化过程，降低烧结温度，避免高温烧结过程中对基体和燃料相的组织和性能产生不利影响。采用SPS工艺，研究了Si添加量、烧结温度、烧结压力和保温时间对ZrC样品密度和显微组织的影响。结果表明，烧结温度和Si添加量是影响ZrC致密化的关键因素，而烧结压力和保温时间的影响相对较小。Si的加入能有效促进ZrC烧结过程中的致密化过程。在1600℃/20 MPa/10 min的烧结条件下，添加2.5 wt%的Si可使ZrC的最大致密化率比纯ZrC提高200%以上。

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来源期刊

Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)

CiteScore

3.70

自引率

15.40%

发文量

175

审稿时长

20 weeks

期刊介绍： The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.