重水研究堆热柱石墨潜能释放分析研究

Release of Graphite Stored Energy in Thermal Column of Heavy Water Research Reactor

  • 摘要: 重水研究堆堆内石墨构件在长期中子辐照下将会累积潜能,为确保重水研究堆堆内石墨构件安全退役及处理处置,本文采用差示扫描量热仪对重水研究堆3个不同位置所取热柱石墨样品进行了潜能测量,扫描温度范围为10~550 ℃、升温速率为10 ℃/min。结果表明:3个位置的样品在80~500 ℃温度积分区间内潜能释放量分别为70.690、42.167、18.158 J/g;潜能释放率曲线峰值温度均大于300 ℃,未辐照石墨样品的比热容较热柱石墨样品释放率dS/dTS为潜能释放量(J/g),T为温度(℃))高,表明本实验所取石墨样品不会发生潜能释放导致石墨自身温度上升的情况;3个位置样品的快中子注量分别为6.75×1016、6.10×1014、1.89×107 cm-2;获得了潜能释放分数曲线与潜能释放速率曲线,1#和2#位置样品的潜能释放速率曲线具有至少2个释放峰,表明潜能释放过程中具有至少2个动力学过程。

     

    Abstract: The stored energy will be accumulated in the graphite structure materials of the Heavy Water Research Reactor under long-term neutron irradiation. To ensure the safe decommissioning and disposal of the graphite components in the Heavy Water Research Reactor, the stored energy of graphite in three different positions of the thermal column of the Heavy Water Research Reactor was measured by differential scanning calorimeter. The scanning temperature range is 10-550 ℃, and the heating rate is 10 ℃/min. The results show that in the integral temperature range of 80-500 ℃, the stored energy release of the three kinds of samples is 70.690, 42.167, 18.158 J/g, respectively. The peak temperature of the stored energy release rate curve is higher than 300 ℃, and the specific heat capacity of the non-irradiated graphite sample is much higher than that of the thermal column graphite sample, which indicates that the stored energy release of the graphite sample in this experiment will not cause the temperature rise itself. According to the empirical formula, the fast neutron flux of the three kinds of samples is 6.75×1016, 6.10×1014, 1.89×107 cm-2, respectively. The stored energy release fraction curve and stored energy release rate curve were obtained, and the stored energy release rate constant curves of 1# and 2# position samples have at least two release peaks, indicating that there are at least two kinetic processes in the stored energy release process.

     

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