首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems-water reactors >DEVELOPMENT AND PERFORMANCE OF Mo FUEL CLADDING UNDER LWR AND SEVERE LOSS OF COOLANT ACCIDENT CONDITIONS
【24h】

DEVELOPMENT AND PERFORMANCE OF Mo FUEL CLADDING UNDER LWR AND SEVERE LOSS OF COOLANT ACCIDENT CONDITIONS

机译:轻水堆下钼燃料熔覆层的发展与性能以及严重事故条件下的严重损失

获取原文

摘要

Molybdenum alloy with an external coating has been proposed as a candidate fuel cladding to provide enhanced tolerance to severe loss of coolant accidents. Mo-alloy has been known to possess good tensile and creep strength at temperatures exceeding 1200°C, and some Mo-alloys also have adequate ductility at room temperature suitable for fabrication of thin-wall tubes. The proposed Mo alloy cladding for accident tolerant fuel (ATF) includes an external coating of either Zr-alloy or Al-containing stainless steel; both are anticipated to provide good corrosion resistance at light water reactor operation temperatures and form an in-situ oxide of ZrO_2 and Al_2O_3 to protect the Mo-alloy in a loss of coolant environments. The corrosion resistance of bare and coated Mo tubes was evaluated in high temperature water, simulating three different LWR water chemistry conditions; (1) BWR normal water chemistry (NWC) containing lppm O_2 at 290°C, (2) BWR hydrogen water chemistry (HWC) containing 0.3ppm H_2 at 290°C, and (3) PWR primary coolant containing 3.57ppm H_2 at 330°C. It is shown that Mo is more stable in high temperature water containing hydrogen, while a high susceptibility of pure Mo to corrosion is observed in the presence of oxygen due to the formation of soluble MO_3. Coated specimens show excellent corrosion resistance. The high temperature oxidation resistance of bare and coated Mo-alloy was also tested in 1000°C steam. Mo specimens coated with Zircaloy or Al-containing stainless steel (FeCrAl) have shown stability in 1000°C steam up to 4 days with the formation of protective ZrO_2 or Al_2O_3.
机译:已经提出了具有外部涂层的钼合金作为候选的燃料包壳,以提供对严重损失冷却剂事故的增强的耐受性。已知钼合金在超过1200°C的温度下具有良好的拉伸强度和蠕变强度,并且某些钼合金在室温下也具有足够的延展性,适用于制造薄壁管。提议的用于耐事故燃料(ATF)的钼合金熔覆层包括Zr合金或含Al的不锈钢的外部涂层。预计两者在轻水反应堆运行温度下均具有良好的耐腐蚀性,并形成ZrO_2和Al_2O_3的原位氧化物,以在冷却剂流失的环境中保护钼合金。模拟了三种不同的轻水堆水化学条件,在高温水中评估了裸露的和涂覆的钼管的耐腐蚀性。 (1)290°C时含有1ppm O_2的BWR常规水化学(NWC),(2)290°C时含有0.3ppm H_2的BWR氢水化学(HWC)和(3)330°C下含有3.57ppm H_2的PWR初级冷却剂℃。结果表明,Mo在含氢的高温水中更稳定,而由于存在可溶的MO_3,在有氧存在下,观察到纯Mo对腐蚀的敏感性较高。涂层样品显示出优异的耐腐蚀性。裸钼合金和涂层钼合金的高温抗氧化性也在1000°C的蒸汽中进行了测试。涂有Zircaloy或含Al不锈钢(FeCrAl)的Mo试样在1000°C的蒸汽中最多显示4天的稳定性,并形成保护性ZrO_2或Al_2O_3。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号