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与我国核电发展相关的堆芯关键材料——锆合金国产化问题
引用本文:李中奎,刘建章,薛祥义.与我国核电发展相关的堆芯关键材料——锆合金国产化问题[J].稀有金属快报,2007,26(1):6-9.
作者姓名:李中奎  刘建章  薛祥义
作者单位:1. 西北有所金属研究院,陕西,西安,710016
2. 西北工业大学,陕西,西安,710072
摘    要:评述了我国“十五”期间在堆芯关键结构材料——锆合金的研发与产业化方面的最新进展。说明我国在改进Zr-4和新一代锆合金研究方面取得了明显的突破,材料研究已达国际先进水平;同时进一步完善了2条包壳管材生产线,为我国核电用包壳管的国产化生产提供了基础保障。结合我国核电发展的实际情况,提出了我国要加快建设海绵锆生产厂,建立格架用条带生产线,完善管、板材开坯设备等建议,并指出锆铪分离技术、条带制造方面的织构控制及在线检测技术是需解决的关键技术。文章强调,高燃耗组件用新一代锆合金的研发仍是科研的主要任务。

关 键 词:锆合金  核反应堆  分离技术  条带
文章编号:1008-5939(2007)01-006-04
修稿时间:2006年8月25日

The Scenario Objectives of Domestic Manufacture for Zirconium Alloys as Structural Materials in the Core of Nuclear Reactor in China
Li Zhongkui,Liu Jianzhang,Xue Xiangyi.The Scenario Objectives of Domestic Manufacture for Zirconium Alloys as Structural Materials in the Core of Nuclear Reactor in China[J].Rare Metals Letters,2007,26(1):6-9.
Authors:Li Zhongkui  Liu Jianzhang  Xue Xiangyi
Abstract:The recent progress of R&D and manufacture Scenario for zirconium alloys as structural materials in the core of nuclear reactor in China is reviewed in this paper.It is pointed out that much breakthrough has been achieved in aspects of R&D for IMP Zircaloy-4 and high performance new zirconium alloys,in aspects of domestic production line for cladding tubes.It is proposed that construction of sponge zirconium plant and setting up plate or strip production line etc.is prominent task in next yeas,improvement of separation Hf from zirconium,and the fabrication technology in industrial scale for plate or strip are key research issues in recent years.
Keywords:zirconium alloys  nuclear reactor  separation  plate/strip
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