基本信息:
- 专利标题： 우수한 내식성과 기계적 특성을 갖는 지르코늄 합금핵연료 피복관 및 그 제조 방법
- 专利标题（英）：Nuclear fuel cladding tube of zirconium alloys having excellent corrosion resistance and mechanical properties and process for manufacturing thereof
- 专利标题（中）：具有优异耐腐蚀性和机械特性的锆合金核燃料涂层管及其制造方法
- 申请号：KR1020010024582 申请日：2001-05-07
- 公开(公告)号：KR1020020085198A 公开(公告)日：2002-11-16
- 发明人： 정용환 , 백종혁 , 최병권 , 이명호 , 박상윤 , 남철 , 정연호
- 申请人： 한국원자력연구원 , 한국수력원자력 주식회사
- 申请人地址： 대전광역시 유성구 대덕대로***번길 ***(덕진동)
- 专利权人： 한국원자력연구원,한국수력원자력 주식회사
- 当前专利权人： 한국원자력연구원,한국수력원자력 주식회사
- 当前专利权人地址： 대전광역시 유성구 대덕대로***번길 ***(덕진동)
- 代理人： 한인열; 이원희
- 主分类号： G21C3/07
- IPC分类号： G21C3/07
摘要：
PURPOSE: A zirconium alloy nuclear fuel coating tube having excellent corrosion resistance and a mechanical characteristic and a fabricating method thereof are provided to improve corrosion resistance and the mechanical characteristic by forming a zirconium alloy including components such as Nb, Sn, Fe, Cu, and Cr. CONSTITUTION: A zirconium alloy is formed with Nb of 0.05 to 0.4 weight percent, Sn of 0.3 to 0.7 weight percent, Fe of 0.1 to 0.4 weight percent, Cu of 0.01 to 0.2 weight percent, Si of 80 to 120 ppm, O of 600 to 1400 ppm, and Zr. The amount of Nb+Sn is 0.35 to 1.0 weight percent. In a fabricating process of the zirconium alloy, an ingot is formed by melting the mixture. The ingot is forged in a beta region. A beta-quenching process is performed under temperature of 1015 to 1075 degrees centigrade. A hot-extrusion process is performed under the temperature of 600 to 650 degrees centigrade. A pilgering process is repeatedly performed and an intermediate vacuum annealing process is performed under the temperature of 550 to 640 degrees centigrade. A final annealing process is performed under the temperature of 460 to 540 degrees centigrade.
摘要（中）：
目的：提供具有优异的耐腐蚀性和机械特性的锆合金核燃料涂层管及其制造方法，以通过形成包含Nb，Sn，Fe，Cu等成分的锆合金和提高其耐磨性和机械特性， 铬。 构成：以Nb为0.05〜0.4重量％，Sn为0.3〜0.7重量％，Fe为0.1〜0.4重量％，Cu为0.01〜0.2重量％，Si为80〜120ppm，O为600的Nb形成锆合金 至1400ppm，和Zr。 Nb + Sn的量为0.35〜1.0重量％。 在锆合金的制造工艺中，通过熔化混合物形成锭。 铸锭在β区域锻造。 在1015至1075摄氏度的温度下进行β-淬火过程。 在600至650摄氏度的温度下进行热挤压工艺。 重复进行喷涂处理，在550〜640摄氏度的温度下进行中间真空退火处理。 在460至540摄氏度的温度下进行最终退火工艺。
公开/授权文献:
- KR100441562B1 우수한 내식성과 기계적 특성을 갖는 지르코늄 합금핵연료 피복관 및 그 제조 방법 公开/授权日：2004-07-23