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Quartz KU-1 optical density measurements after irradiation in the nuclear reactor IR-8

机译:核反应堆IR-8辐照后的石英KU-1光学密度测量

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Optical characteristics of quartz glass KU-1 were investigated after irradiation in a water-pull nuclear reactor IR-8 up to the fluence of 6×10~(190 n/cm~2. Quartz samples - cylinders with diameters 16 mm and heights 8 mm - were placed in two aluminum containers active zone in one of the central channel of the reactor IR-8 where the neutron flux was approximately equals 8×10~(13) n/cm~2 s. Quartz glass KU-1 optical characteristics were investigated after irradiation at the dose rate 4 kGy(Si)/s. Made from one melt, samples (though even this does not guarantee their complete identity) were irradiated up to the neutron fluence for the first group of 6×10~(19) n/cm~2 (gamma dose of 2.5 GGy) and for the second group of 6×10~(18) n/cm~2 (gamma dose of 270 MGy) at the temperature of 55 °C. Transparency spectra of unirradiated and irradiated samples, in the wavelength range from 0.2 to 2.5 m, were measured with the aid of a Hitachi Recording Spectrometer 20 days after irradiation. As it was observed at a lower fluence an essential degradation of the transparency took place in a wavelength region of λ<350 nm. In a region of 450-650 nm transparency decreased by 15%. At longer wavelengths no absorption was induced. The results of measurement have shown that the quartz of KU type may be used behind the shield in periscope channels or for windows behind the straight channel.
机译:在水拉式核反应堆IR-8中辐照至6×10〜(190 n / cm〜2)的通量后,研究了石英玻璃KU-1的光学特性。石英样品-直径16 mm,高度8的圆柱体毫米-放置在反应堆IR-8中央通道之一的两个铝容器活动区中,其中中子通量大约等于8×10〜(13)n / cm〜2 s。石英玻璃KU-1光学特性在以4 kGy(Si)/ s的剂量率辐照后进行了研究。由一个熔体制成的样品(即使不能保证其完全相同)也被辐照至第一组6×10〜( 19)n / cm〜2(伽马剂量为2.5 GGy),第二组6×10〜(18)n / cm〜2(伽马剂量为270 MGy)在55°C的温度下。照射后20天,用日立记录光谱仪测量0.2至2.5 m波长范围内的未辐照和辐照样品。观察到以较低的通量,在λ<350nm的波长范围内发生了透明性的显着降低。在450-650 nm范围内,透明度降低了15%。在更长的波长下,不会引起吸收。测量结果表明,KU型石英可以在潜望镜通道的护罩后面使用,也可以在直通道的窗口中使用。

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