AM堆乏燃料水下处理过程中可燃气体生成与放射性核素释放研究

Artyom Z. Gayazov, A. Leshchenko, V. P. Smirnov, P. A. Ilyin, V. G. Teplov
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引用次数: 1

摘要

介绍。本文对AM反应堆泄漏乏燃料水下处理模拟过程中可燃气体的积累进行了研究。研究了分散在镁中的铀钼和分散在钙中的碳化铀两种燃料组成。方法。在铀钼燃料的水下储存过程中,测量了137Cs的释放速率。得到了燃料氢释放动力学和碳化物SNF甲烷释放动力学。动力学近似于指数依赖,形式上对应于一级化学反应。对实验过程中产生的气体中放射性氢的贡献进行了估计。结果表明,这些气体的决定性来源是乏燃料与水之间的化学相互作用。铀钼燃料的实验表明,由于不溶性腐蚀产物,化学过程对燃料表面有明显的钝化作用。对于碳化物SNF,观察到大约20小时的潜伏期,然后是氢气和甲烷的密集释放。结果。所得到的结果是与有关燃料成分在水中的行为的出版物进行比较分析的结果。结论。研究结果可用于证明使用所考虑的燃料成分(AM、AMB、EGP-6等反应堆的乏燃料)处理受损乏核燃料的水下处理技术的火灾和爆炸安全性,例如,证明AMB乏燃料用于后处理的水下准备。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Study on combustible gas generation and radionuclide release during underwater handling of the AM reactor spent fuel
Introduction. The paper addresses studies on the accumulation of combustible gases during underwater handling simulations for the leaky spent nuclear fuel from the AM reactor. Two fuel compositions were studied- uranium-molybdenum dispersed in magnesium and uranium carbide dispersed in calcium. Methods. The 137Cs release rate was measured during underwater storage of the uranium-molybdenum fuel. The kinetics of hydrogen release for both fuels and methane release for the carbide SNF were obtained. The kinetics approximate most with exponential dependences that formally correspond to first-order chemical reactions. A contribution of radiolytic hydrogen to the gases generated during the experiments was estimated. It was demonstrated that the determining source of the gases is the chemical interaction between the spent fuel and the water. The experiment with the uranium-molybdenum fuel demonstrated a pronounced passivation effect of the chemical processes on the fuel surface due to insoluble corrosion products. For the carbide SNF, an incubation period of about 20 hours was observed followed by an intensive release of hydrogen and methane. Results. The obtained results were subject to a comparative analysis against publications on the behavior of the fuel components in water. Conclusion. The findings can be applied to justify fire and explosion safety of underwater handling techniques for the damaged spent nuclear fuel with the considered fuel compositions (the spent fuel from reactors AM, AMB, EGP-6, etc.), e.g., to justify underwater preparations of the AMB spent fuel for reprocessing.
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