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机构地区:[1]清华大学核能技术设计研究院
出 处:《核动力工程》1998年第3期250-254,共5页Nuclear Power Engineering
摘 要:控制棒水力驱动系统是一种新型的控制棒驱动机构,它可整体封装入压力壳内与堆芯构成一体化结构设计。本文介绍了由压力筒、水力步进缸、加热器、泵及其他设备组成的实验回路和测量系统在高温、高压条件下压力筒失压时控制棒的棒位测量实验。实验结果表明,控制棒水力驱动系统在压力壳失压工况下不产生弹棒事故,系统具有固有安全特性。he hydraulic driving system of control rod is a new controllingequipment in nuclear reactor.Its drive assembly is hydraulic step cylinder.The cylinder can be installed in the pressure vessel and its inner tube is fixed on the bottom block of core.By the experiment for experimental loop(including pressure vessel,hydraulic step cylinder,heater,pump and another devices)and measuring system,the rod position is measured and observed when the pressure vessel loses pressure under high temperature and high pressure.A lot of experimental data and observed results are obtained.The results indicate:The hydraulic driving system of control rod can't engender rod ejection accident when the pressure vessel loses pressure.So,this system has inherent safety feature of not engendering rod ejection.
分 类 号:TL362.6[核科学技术—核技术及应用]
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