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水冷反应堆燃料元件的在役检测和处理
引用本文:邓浚献,邓峰.水冷反应堆燃料元件的在役检测和处理[J].核安全,2009(4):47-57.
作者姓名:邓浚献  邓峰
作者单位:核工业第二研究设计院,北京100840
摘    要:水冷反应堆包括轻水堆和重水堆,轻水堆分为压水堆和沸水堆;重水堆分为加压重水堆和加拿大的氘铀堆。国际上把它们归为一类进行研究。本文涉及的破损燃料元件的在役检测和处理包括:反应堆运行时的检测;换料时或换料后的检测;在燃料组件内鉴别破损的燃料棒;燃料组件的监测、拆卸和修复;破损燃料棒拆出后的检测,破损定位与修补。

关 键 词:水堆  燃料元件  在役检测

In Service Inspection and Treatment of Water Cooled Reactor Fuel Element
DENG Junxian,DENG Feng.In Service Inspection and Treatment of Water Cooled Reactor Fuel Element[J].Nuclear Safety,2009(4):47-57.
Authors:DENG Junxian  DENG Feng
Affiliation:( Beijing Institute of Nuclear Engineering, Beijing 100840, China)
Abstract:There are Light water reactor and Heavy water reactor in water cooled reactor, Pressure water reactor and Boiling water reactor in Light water reactor; Pressurized heavy water reactor and Canadian deuterium reactor in heavy water reactor. All of these reactors are belong to one research subject in the world. In service inspection and treatment of the defective fuel include the monitoring during reactor operation, the inspection during and after refueling, the identification of defective rods in fuel assembly, the inspection, repair and reconstitution of the fuel assembly, the detection of failed rod, locating the defect and repairing the defect after withdrawal the defective rod.
Keywords:water cooled reactor  fuel element  in service inspection
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