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Radiation Effects of F82H JLF-1

机译:F82H&JLF-1的辐射效应

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摘要

Irradiation programs of RAF/M in EU, Japan and US are summarized. F82H and JLF-1 are included in Japanese and US irradiation programs. F82H is also adopted in the EU programs. F82H and JLF-1 have been irradiated in HFIR, JMTR, JRR-2, JRR-3, FFTF, EBR-II and ATR. Another domestic reactor, JOYO, is also considered in the future program. Thus accumulated data may suggest the saturation in DBTT shift of 300 C irradiated F82H around 0 C at 1 dpa, but recent data from EU irradiation program show that is not the case. Another topic in recent results is the tensile properties of welded F82H. Irradiation hardening of the weld joint type specimen, measured in 0.2% proof stress, was smaller than those of base metal or weld metal specimens, suggesting less irradiation hardening in the tempered area of HAZ.
机译:综述了欧盟,日本和美国欧盟的RAF / M的辐照计划。 F82H和JLF-1包含在日本和美国辐照方案中。 F82H还采用欧盟计划采用。 F82H和JLF-1已在HFIR,JMTR,JRR-2,JRR-3,FFTF,EBR-II和ATR中进行辐照。另一位国内反应堆乔州也在未来的计划中考虑。因此,累积的数据可以在1dPa下暗示300c照射F82h的DBTT偏移的饱和度,但近期来自欧盟照射程序的数据并非如此。最近结果的另一个主题是焊接F82H的拉伸性能。焊接接头型样品的照射硬化在0.2%的抗粘附应力下测量,小于贱金属或焊接金属样品,表明HAZ的钢化面积较少照射硬化。

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