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作 者:刘云明[1] 陈建刚[1] 刘超红[1] 孙长龙[1] 庞晓轩[2] 王录全[1] 尹昌耕[1]
机构地区:[1]中国核动力研究设计院反应堆燃料及材料重点实验室,成都610213 [2]中国工程物理研究院,四川江油621700
出 处:《核动力工程》2015年第4期90-94,共5页Nuclear Power Engineering
摘 要:采用扩散偶方法研究U-Mo合金与Zr的相容性。扩散偶采用包覆热轧法制备,热处理温度为750℃和800℃,热处理时间为10 h和50 h。结果表明:U-Mo合金与Zr合金间的扩散层有分层现象,在U-Mo/Zr界面扩散反应成分复杂界面处存在类似Mo2Zr的析出物。经X射线衍射(XRD)检测表明U-Mo/Zr扩散层由M2Zr、UZr2和U等组成。U-Mo/Zr的扩散过程是U和Mo原子向Zr扩散,Mo优先与Zr反应生成Mo2Zr、U通过Mo2Zr扩散形成γ-(U,Zr)固溶体的过程。U-Mo合金与Zr具有良好的相容性。The compatibility of U-Mo alloy and Zirconium alloy was studied in this paper. The diffusion-couple was prepared by coated hot rolling and annealed at 750℃ and 850℃ for 10 and 50 hours. The result shows that the diffusion-layer has delaminated between U-Mo alloy and Zirconium alloy, and the diffusion-layer has a complicated composition with the Mo2Zr second precipitate. XRD result shows that the composition of diffusion-layer is the Mo2Zr, UZr2 and U. The diffused mechanism of U-Mo and Zirconium is that the atom of U and Mo diffuse into Zirconium alloy, then Mo and Zr form Mo2Zr firstly and the U continuously through out Mo2Zr to form y-(U,Zr) solid-solution. The U-Mo alloy has good compatibility with Zirconium alloy.
分 类 号:TL341[核科学技术—核技术及应用]
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