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Safety against brittle fracture of the reactor pressure vessel in the nuclear power plant Obrigheim

机译:安全防止核电站Obrigheim的反应堆压力容器发生脆性断裂

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摘要

Obrigheim. the first pressurized light water reactor built i11 Germany, operates with a nominal power of 357 MW. Since the beginning of electricity production in l968 the nuclear power plant Obrigheim (KWO) has proved to be a reliable and safe operation with a high availability. in terms of time, of 81.4/100 over 29 years. The reactor pressure vessel could be qualified for future operation by means of inservice inspections, irradiation programs, fluence calculations. nondestructive testing. investigations of pressurized thermal shock (PTS) conditions and by implementa- tion of technical improvements for operation and maintenance. The main steps of the final licensing procedure, for the qualification of the reactor pressure vessel relative to irradiation embrittlement and safety against brittle fracture under pressurized thermal shock conditions, are presented as a summary of investigations and experiences over more than 20 years.
机译:奥布里格海姆。德国i11建造的第一座加压轻水反应堆的额定功率为357兆瓦。自从1968年开始发电以来,事实证明,核电厂Obrigheim(KWO)具有高可用性,是一种可靠,安全的运行方式。就时间而言,在29年中为81.4 / 100。反应堆压力容器可以通过在役检查,辐照程序,注量计算等方式进行未来运行的认证。非破坏性测试。对加压热冲击(PTS)条件进行调查,并通过实施技术改进来进行操作和维护。最终许可程序的主要步骤是对超过20年的研究和经验进行总结,以对反应堆压力容器进行辐照脆化鉴定和在加压热冲击条件下防止脆性破裂的安全性。

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