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Radiation Stability of the Referent Reactor Pressure Vessel JRQ Steel at High Neutron Fluence

机译:参考反应堆压力容器JRQ钢在高中子注量下的辐射稳定性

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The mechanical parameters of JRQ reactor pressure vessel steel after irradiation up to high neutron fluence are investigated. The irradiation of specimens is performed by using assembly of new type designed to assure homogeneous neutron field on the specimens. The assembly is installed in core zone restrictor cooling channel in order to achieve high neutron fluence on the specimens. It is established that maximal irradiation temperature in this position is higher than 292 ℃ and lower than 302 ℃. The comparison of the JRQ critical temperature shift obtained in this experiment with the data of other authors shows good agreement. The obtained value of critical temperature shift is used to derive an equation for shift dependency on neutron fluence in the investigated range.
机译:研究了JRQ反应堆压力容器钢在辐照至高中子注量后的力学参数。样品的辐照是通过使用新型组件进行的,该组件设计为确保样品上均匀的中子场。该组件安装在核心区限流器冷却通道中,以实现对样品的高中子注量。确定该位置的最高照射温度高于292℃而低于302℃。在本实验中获得的JRQ临界温度变化与其他作者的数据进行的比较显示出很好的一致性。所获得的临界温度偏移值用于得出研究范围内偏移对中子注量的依赖关系方程。

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    《Journal of materials science and technology》 |2010年第3期|p.143-154|共12页
  • 作者单位

    Institute of Metal Science, Equipment and Technologies 'Akad. A. Balevski' with Hydroaerodynamics Centre, Bulgarian Academy of Sciences, 67, Shipchenski Prohod Street, 1574 Sofia, Bulgaria;

    Institute of Metal Science, Equipment and Technologies 'Akad. A. Balevski' with Hydroaerodynamics Centre, Bulgarian Academy of Sciences, 67, Shipchenski Prohod Street, 1574 Sofia, Bulgaria;

    Institute of Metal Science, Equipment and Technologies 'Akad. A. Balevski' with Hydroaerodynamics Centre, Bulgarian Academy of Sciences, 67, Shipchenski Prohod Street, 1574 Sofia, Bulgaria;

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