锆-铌合金的氢化  

Hydriding of Zirconium-Niobium Alloy

作　　者：徐海生[1] 兰光友[1] 

机构地区：[1]中国核动力研究设计院核燃料及材料研究所,成都610041

出　　处：《核动力工程》2008年第1期73-75,共3页Nuclear Power Engineering

摘　　要：将锆-铌合金在880℃下氢化,然后辅以慢速冷却补充吸氢的工艺,最终可以实现氢化锆的H/Zr原子比达到1.80以上,并且无裂纹。在氢化过程中,原锆-铌合金中的铌以弥散小颗粒状的形式析出,并分散分布在氢化锆基体中;H/Zr原子比由最终停止氢化的温度和系统的氢气压力所决定;氢化时降温速度和氢气流量的控制对防止氢化锆的开裂起重要作用。X-射线衍射分析和金相观察表明,H/Zr原子比达到1.80以上的氢化锆为单一ε相,组织形貌呈平行条带状。The zirconium-niobium alloy is hydrided at 880℃. And when zirconium hydride reaches its hydrogen saturation point at that temperature, hydrogen has been continuously supplied to the hydriding furnace during the process of slowly cooling. This method can progressively increase the hydrogen content of zircloy hydride and effectively prevent hydride from cracking. The results show that the H/Zr atom ratio of zirconium hydrides is above 1.80 and the samples have no cracking. During the hydriding process, the niobium which is rejected from the zirconium hydride is present as a fine, uniform dispersion. The H/Zr atom ratio is depended on the hydriding temperature and the pressure of hydrogen. It is very important to prevent zirconium hydride from cracking by controlling the rate of cooling and the flow of hydrogen. The X-ray diffraction and metallography analysis results show that the hydride phase is a single ε- phase and the morphol- ogy of ZrHx（x〉1.80） appears as a banded, twin structure.

关 键 词：锆-铌合金 氢化 H/Zr原子比 慢化材料 

分 类 号：TG146.414[一般工业技术—材料科学与工程]