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ALLOY MATERIAL FOR STRUCTURAL MATERIAL OF VERY HIGH TEMPERATURE FURNACE AND METHOD FOR MANUFACTURING IT

机译:高温炉用结构用合金材料及其制造方法

摘要

PROBLEM TO BE SOLVED: To make it possible to withstand a severe condition by adding Y2O3, titanium and tungsten of a specific ratio respectively to a material of ferritic steel and then alloying and powdering it through a mechanical alloying treatment and conducting a sintering and molding treatment of it. ;SOLUTION: Y2O3 of 0.07 to 0.10%, Ti of 0.09 to 0.10% and W of 3 to 4.5% in the form of powder are added respectively to powdery ferritic steel and are mixed with it. A mechanical alloying treatment is conducted for the mixture to alloy and powder it. Then, the obtained powdery alloy is made to have a size of about 1 μm in particle diameter by a plasma electric discharge sintering method, an HIP method, or a hot extrusion method. Consequently, an alloy material can be obtained which is useful as a structural material for a nuclear fusion reactor that has excellent high-temperature strength properties making it possible to withstand a working condition at a high temperature under the irradiation with high-energy neutron flux, mechanical characteristics under high temperature conditions and low activation properties against neutron irradiation.;COPYRIGHT: (C)2000,JPO
机译:解决的问题:通过在铁素体钢材料中分别添加特定比例的Y2O3,钛和钨,然后通过机械合金化处理将其合金化和粉末化,然后进行烧结和成型处理,可以承受严酷的条件它的。 ;解决方案:以粉末形式分别向粉末状铁素体钢中添加0.07至0.10%的Y2O3、0.09至0.10%的Ti和3至4.5%的W,并将其混合。对混合物进行机械合金化处理以使其合金化和粉末化。然后,通过等离子放电烧结法,HIP法或热挤压法使所得粉末合金的粒径为约1μm。因此,可以得到用作核聚变反应堆的结构材料的合金材料,该合金材料具有优异的高温强度特性,使得可以在高能中子通量的照射下承受高温下的工作条件,高温条件下的机械特性和对中子辐照的低活化特性。;版权所有:(C)2000,日本特许厅

著录项

  • 公开/公告号JP2000214282A

    专利类型

  • 公开/公告日2000-08-04

    原文格式PDF

  • 申请/专利权人 JAPAN ATOM ENERGY RES INST;

    申请/专利号JP19990016435

  • 发明设计人 ISHIYAMA TAKASHI;

    申请日1999-01-26

  • 分类号G21B1/00;B22F1/00;B22F3/14;C22C33/02;C22C38/00;

  • 国家 JP

  • 入库时间 2022-08-22 01:59:37

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