首页> 外文期刊>Radiochimica Acta: International Journal for Chemical Aspects of Nuclear Science and Technology >Actinides draw down process for pyrochemical reprocessing of spent metal fuel
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Actinides draw down process for pyrochemical reprocessing of spent metal fuel

机译:in系元素提取工艺用于乏金属燃料的热化学后处理

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摘要

An experimental system has been setup inside an argon atmosphere glove box to carry out studies on the actinide draw down process, an important step of the pyroprocess flow sheet. Studies have been carried out at 723 K on the extraction of uranium from LiCl-KCl eutectic salt containing 0.5% UCl3 using lithium-0.03% cadmium alloy. In these experiments, 5 L of the molten salt and 5 L of the molten alloy are fed to a single stage extractor where 250 mL of the salt and 250 mL of the alloy come into contact. A three stage stirrer having straight as well as pitched blade turbine impellers was used to mix the molten alloy and salt phases having high interfacial tension of 450 dyne/cm. The results of the studies indicate that a U extraction efficiency of 99% could be achieved.
机译:在氩气氛手套箱内设置了一个实验系统,以进行the系元素提取工艺的研究,该工艺是高温工艺流程图的重要步骤。已经在723 K上进行了使用0.03%锂镉合金从含0.5%UCl3的LiCl-KCl共晶盐中萃取铀的研究。在这些实验中,将5 L的熔融盐和5 L的熔融合金送入单级萃取器,在其中使250 mL的盐和250 mL的合金接触。具有直叶片和斜叶片涡轮的三级搅拌器用于混合熔融合金和具有450达因/厘米的高界面张力的盐相。研究结果表明,可以实现99%的U提取效率。

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