首页> 外文会议>International Congress on Advances in Nuclear Power Plants >DEVELOPMENT OF PROTOTYPE REACTOR MAINTENANCE (2) APPLICATION TO PIPING SUPPORT OF SODIUM-COOLED REACTOR PROTOTYPE
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DEVELOPMENT OF PROTOTYPE REACTOR MAINTENANCE (2) APPLICATION TO PIPING SUPPORT OF SODIUM-COOLED REACTOR PROTOTYPE

机译:原型反应器维护的开发(2)应用于钠冷却反应器原型的管道支撑

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A maintenance program on piping support of prototype fast breeder reactor Monju are studied. Based on degradation mechanism, snubbers in Monju primary cooling system showed lifetime more than the plant lifetime of 30years by experiments conservatively. For the first step during construction, visual inspection on accessible all supports could be available. In that visual inspection, mounting conditions and damages of all accessible supports could be monitored. One of major features of the Monju primary piping system is large thermal expansion due to large temperature difference between maintenance and operation conditions. Thanks to that large thermal expansion, integrity of piping supports could be monitored by measuring piping displacement. When technologies of piping displacement monitoring are matured in Monju, visual inspection on piping support could be shifted to piping displacement monitoring. At that stage, the visual inspection could be limited only on representative supports.
机译:研究了原型快速育种反应堆Monju的管道支撑的维护计划。基于降解机制,蒙居初级冷却系统的缓冲器显示寿命超过植物寿命30年的实验。对于施工期间的第一步,可以使用视觉检查所有支持。在该目视检查,可以监控所有可访问支持的安装条件和损坏。由于维护和操作条件之间的较大温差,Monju主要管道系统的主要特点之一具有大的热膨胀。由于这种大的热膨胀,可以通过测量管道位移来监测管道支撑件的完整性。当管道位移监测的技术在Monju成熟时,可以转移到管道支持上的目视检查到管道位移监测。在那个阶段,目视检查可能仅限于代表性支持。

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