A Critical Experimental Study of Bubble Effect in the Process of Spent Fuel Dissolving

Z. Xiaoping, Liang Shuhong, Xia Zhaodong
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Abstract

The influence of gas introduction on the critical safety of the nuclear fuel system under the condition of cold condition, given reactor material and geometry structure is studied. Refer to bubble effect test experiment on nuclear critical safety test device (YSR) and considering solid-liquid two-phase nuclear fuel system with uranyl nitrate solution - uranium dioxide fuel element as the experimental platform, the dynamic process of the real behavior of bubbles in uranyl nitrate solution has been simulated in the quasi-static way by replacing bubble generator with aluminous bubble simulation elements. Bubble effect is the reactivity change caused by the change of volume of solution, neutron leakage and absorption property in the nuclear fuel system due to the bubbles generated in the solution. In the dissolving process of spent fuel, oxygen or nitrogen are usually added to accelerate the dissolution of fuel element shear section, and some other bubble production are also caused by the heat released during the dissolution process. Here, the bubble production caused by the heat is omitted and only artificial gas introduction is considered in my study. When there are enough bubbles in the uranium solution system, the volume of the solution will increase, which will inevitably influence the absorption and leakage property of the neutrons, and further influence the reactivity of the nuclear fuel system. The corresponding relationship between the bubble-intake rate and the bubble equivalent diameter, arising velocity and bubble share is determined through fluid dynamics modeling to manufacture the aluminous bubble simulation elements. The theoretical calculation by MONK9A and the critical experimental measurements are also compared and analyzed in this paper. The results showed that the reactivity caused by bubbles was negative, and the greater the intake rate, the greater the negative effect. Meanwhile the theoretical calculated value was in good agreement with the experimental value and the maximum deviation was 63.4 pcm.
乏燃料溶解过程中气泡效应的关键实验研究
研究了在给定反应堆材料和几何结构条件下,冷态下气体引入对核燃料系统临界安全性的影响。参考核临界安全试验装置(YSR)上的气泡效应试验,以硝酸铀酰溶液-二氧化铀燃料元件为实验平台的固液两相核燃料系统,用铝泡模拟元件代替气泡发生器,以准静态方式模拟了硝酸铀酰溶液中气泡真实行为的动态过程。气泡效应是由于溶液中产生气泡而引起的溶液体积、中子泄漏和核燃料系统吸收性能的变化所引起的反应性变化。在乏燃料的溶解过程中,通常加入氧气或氮气来加速燃料元件剪切段的溶解,溶解过程中释放的热量也会引起其他一些气泡的产生。这里省略了热量产生的气泡,我的研究只考虑人工气体的引入。当铀溶液体系中有足够的气泡时,溶液的体积会增大,这必然会影响中子的吸收和泄漏特性,进而影响核燃料系统的反应性。通过流体动力学建模,确定气泡进气量与气泡当量直径、上升速度和气泡占比的对应关系,制作铝质气泡仿真元件。本文还对MONK9A的理论计算和关键的实验测量进行了比较和分析。结果表明,气泡引起的反应性为负,且进气速率越大,负影响越大。理论计算值与实验值吻合较好,最大偏差为63.4 pcm。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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