反应堆压力容器钢热影响区的中子辐照脆化敏感性

H. Takamizawa, J. Katsuyama, Y. Ha, T. Tobita, Y. Nishiyama, K. Onizawa
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引用次数: 0

摘要

由于对焊接头多道次焊接的热历史导致热影响区(HAZ)的组织不均匀,从而导致反应堆压力容器(RPV)钢的夏比冲击性能存在较大的散射。研究了未辐照材料的热影响区特征与晶粒尺寸、相分数、马氏体-奥氏体成分等微观组织的关系。中子辐照在日本原子能机构运营的日本研究堆-3 (JRR-3)上进行。通过辐照后力学测试和显微结构分析对中子辐照敏感性进行评价。在实验中,制备了典型的RPV钢板及其焊件。基于有限元热史计算,制备了具有代表性的粗晶HAZ (chaz)和细晶HAZ (FGHAZ)等HAZ模拟材料。对于未辐照材料,部分模拟热影响区材料主曲线法的参考温度高于母材(BM)。HAZ材料的辐照硬化与BM几乎相同或更低,参考温度的变化与BM相当。
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Susceptibility to Neutron Irradiation Embrittlement of Heat-Affected Zone of Reactor Pressure Vessel Steels
The heat-affected zone (HAZ) of reactor pressure vessel (RPV) steels is known to show large scatter in Charpy impact properties because it has inhomogeneous microstructure due to thermal histories of multi-pass welding for butt-welded joints. The correlation between mechanical properties and microstructure such as grain size, phase-fraction, martensite-austenite constituent, on the characteristics of HAZ of un-irradiated materials was investigated. Neutron irradiation was conducted at Japanese Research Reactor −3 (JRR-3) operated by JAEA. The neutron irradiation susceptibility was evaluated based on post-irradiation examinations consisting of mechanical testing and microstructural analysis. In the experiments, typical RPV steel plate and their weldment were prepared. Simulated HAZ materials that have representative microstructures such as coarse-grain HAZ (CGHAZ) and fine-grain HAZ (FGHAZ) were also prepared based on the thermal histories calculated by finite element analysis. For un-irradiated materials, a part of simulated HAZ materials showed a higher reference temperature of the master curve method than that of the base metal (BM). The irradiation hardening of HAZ was almost the same or lower than that of the BM, and the shift of reference temperature for HAZ materials was comparable with that of BM.
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