Disintegration of graphite matrix from the simulative high temperature gas-cooled reactor fuel element by electrochemical method
Disintegration of graphite matrix from the simulative high temperature gas-cooled reactor fuel element by electrochemical method
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电化学法分解模拟高温气冷堆燃料元件石墨基体
DOI：
10.1016/j.electacta.2009.07.056
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发表时间：
2009-12
影响因子：
6.6
通讯作者：
Chen, Jing
中科院分区：
文献类型：
--
作者：
Li, Linyan;Tian, Lifang;Wen, Mingfen;Chen, Jing
研究了以盐为电解质的电化学方法对模拟高温气冷堆燃料元件中的石墨基体进行裂解。实验选择硝酸铵作为合适的电解质。破碎后石墨碎片的体积平均直径约为100μm，最大值小于900μm。石墨在分解后，其重量增加了约20%，而没有释放出大量的CO2，这可能是由于石墨在电化学过程中发生了部分氧化。本工作表明，改进的电化学方法具有减少二次核废物的潜力，是一个有前途的选择，从高温气冷堆乏燃料元件在后处理的头端解体石墨基体。
Electrochemical method with salt as electrolyte has been studied to disintegrate the graphite matrix from the simulative high temperature gas-cooled reactor fuel elements. Ammonium nitrate was experimentally chosen as the appropriate electrolyte. The volume average diameter of disintegrated graphite fragments is about 100μm and the maximal value is less than 900μm. After disintegration, the weight of graphite is found to increase by about 20% without the release of a large amount of CO2probably owing to the partial oxidation to graphite in electrochemical process. The present work indicates that the improved electrochemical method has the potential to reduce the secondary nuclear waste and is a promising option to disintegrate graphite matrix from high temperature gas-cooled reactor spent fuel elements in the head-end of reprocessing.
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