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首页> 外文会议>20th International Symposium on Effects of Radiation on Materials, Jun 6-8, 2000, Williamsburg, Virginia >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钢在BN-600反应堆中用作熔覆材料时对中子辐照温度，注量和损伤率的溶胀依赖性

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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℃. 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℃ 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16Cr-15Ni-2Mo-1Mn钢制成的燃料元件包壳样品在反应堆BN -600中使用后最大损伤剂量为73-93 dpa时的辐射溶胀。样品是从堆芯不同位置的区域切出的，因此各种样品的照射温度在390至610℃之间变化。损伤剂量在40-92 dpa / s之间，辐射损伤率从0.9 * 10〜（-6）到2 * 10〜（-6）dpa / s不等。理论上，在固体的统计热力学范围内考虑了发生辐射膨胀的必要条件。获得了将溶胀潜伏期与温度，通量，辐射损伤率和材料微观结构特征联系起来的解析表达式。估计在各种照射温度下的孵育后阶段的溶胀率。从实验数据得到的膨胀对温度，剂量和辐射损伤率的依赖性与理论分析的结果吻合得很好。在390至600℃范围内，引发膨胀的成核损伤剂量随着辐照温度的增加而增加。孵育后阶段的溶胀率也增加了。辐射损伤率的降低将溶胀的能量密度依赖性转移到能量密度和温度较低的区域。

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