首页> 外文会议>International Conference on Environmental degradation of Materials in Nuclear Power Systems-Water Reactors >EFFECT OF DH CONCENTRATION ON CRUD DEPOSITION ON HEATED ZIRCALOY-4 IN SIMULATED PWR PRIMARY WATER
【24h】

EFFECT OF DH CONCENTRATION ON CRUD DEPOSITION ON HEATED ZIRCALOY-4 IN SIMULATED PWR PRIMARY WATER

机译:DH浓度对模拟PWL初级水中加热锆型-4的CRUD沉积的影响

获取原文

摘要

In order to mitigate PWSCC initiation and propagation in Ni base alloys, Japanese PWR utilities desire to employ optimized dissolved hydrogen (DH) control operation in the near future. Prior to the application of the optimized DH control operation to PWR, the effect of DH concentration on the fuel crud deposition should be clarified.Crud deposition tests were carried out in boric acid (1200ppm) + lithium hydroxide (2.2ppm) + hydrogen (7 to 25cm~3-STP/kg-H_2O) solutions at 325°C under sub-cooled boiling and non-irradiated conditions. The corrosion resistance of zircaloy-4 was also investigated.From the test results, it was revealed that a crud layer composed of NiFe_2O_4 and NiO was formed on zircaloy-4 fuel cladding. NiO was easy to form in the crud layer under the 7cm~3-STP/kg-H_2O condition. The amounts of deposited crud layer, boron incorporated into the crud layer and the corrosion resistance of the zircaloy-4 cladding were not affected by DH concentration.
机译:为了缓解Ni基合金中的PWSCC启动和繁殖,日本PWR公用事业公司在不久的将来采用优化的溶解氢(DH)控制操作。在将优化的DH控制操作施加到PWR之前,应澄清DH浓度对燃料CRUD沉积的影响。在硼酸(1200ppm)+氢氧化锂(2.2ppm)+氢气中进行克劳沉积试验(7在325℃下溶液在325℃下溶液在亚冷沸腾和非照射条件下。还研究了锆瓦洛-4的耐腐蚀性。从测试结果中,揭示了由NiFe_2O_4和NiO组成的粗晶层在锆洛伊-4燃料包层上形成。在7cm〜3-stp / kg-h_2o条件下,NIO易于在CRUD层中形成。沉积的粗晶层,掺入粗晶层的硼的量和锆洛伊-4包层的耐腐蚀性不受DH浓度的影响。

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