首页> 外文会议>Symposium on effects of radiation on materials >The Swelling Dependence of Cold Worked 16Cr-15Ni-2Mo-1Mn Steel on Neutron Irradiation Temperature, Fluence and Damage Rate During Its Use as a Cladding Material in the BN-600 Reactor
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The Swelling Dependence of Cold Worked 16Cr-15Ni-2Mo-1Mn Steel on Neutron Irradiation Temperature, Fluence and Damage Rate During Its Use as a Cladding Material in the BN-600 Reactor

机译:冷加工的16Cr-15ni-2Mo-1mn钢对中子照射温度,注重流量和损伤率的膨胀依赖性在BN-600反应器中用作覆层材料

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The radiation swelling of samples of fuel element cladding made of steel 16Cr-15Ni-2Mo-lMn after its use up to a maximum damage dose 73 - 93 dpa in the reactor BN -600 was studied. The samples were cut out from areas of different location in the core, so the irradiation temperature of various samples varied from 390 to 610°C. The damage dose varied from 40 - 92 dpa and the radiation damage rate varied from 0.9 * 10~(-6) to 2 * 10~(-6) dpa/s. The conditions necessary to have the radiation swelling occurred were considered theoretically within the statistical thermodynamics of solids. An analytical expression connecting the incubation period of swelling with a temperature, fluence, radiation damage rate, and characteristics of material microstructure was obtained. The swelling rate at the post-incubation stage at various irradiation temperatures was estimated. The character of swelling dependencies on temperature, dose, and radiation damage rate obtained from the experimental data agreed well with the results of the theoretical analysis. In the range of 390 to 600°C the nucleation damage dose initiating swelling increased with irradiation temperature. The swelling rate in the post-incubation phase also increased. Decreasing radiation damage rate shifted the fluence dependence of swelling into a region of lower fluences and temperatures.
机译:研究了由钢16Cr-15Ni-2MO-LMN制成的燃料元件包层样品的辐射膨胀,在反应器BN -600中使用过最大损伤剂量73-93dPa之后。将样品从核心的不同位置的区域中切出,因此各种样品的照射温度从390变化到610℃。损伤剂量从40-92dPa变化,辐射损伤率从0.9 * 10〜(-6)变化到2 * 10〜(-6)DPA / s。理论上在固体的统计热力学内理论上考虑了辐射肿胀所需的条件。获得了将溶胀的溶胀期与温度,注重,放射损伤率和材料微观结构特征连接的分析表达。估计各种辐照温度下培养后阶段的溶胀率。从实验数据获得的温度,剂量和辐射损伤率溶胀依赖性的特征与理论分析的结果很好。在390至600°C的范围内,成核损伤剂量引发肿胀随着照射温度而增加。后孵育阶段的溶胀率也增加。降低辐射损伤率将肿胀的流量依赖性移入较低的流量和温度的区域。

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