间歇式热扩散塔非稳态操作下水-同位素混合物分离中氘的回收

Ho-Ming Yeh
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引用次数: 1

摘要

重水(D2O)是核裂变反应堆中最可行的慢化剂和冷却剂,而氘(D)将在遥远的将来成为热核聚变的核燃料。对热扩散分离水-同位素混合物(H2O-HDO-D2O)中D2O和h2o中氘的回收率进行了估算。首先预测了水-同位素混合物在热扩散柱中各组分的分离度,然后根据分子量估算了各组分中氘的回收率。结果表明,当D2O的进料质量分数为0.22时,氘的回收率最高。
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Recoveries of deuterium from the separation of water–isotope mixture in batch-type thermal diffusion columns under unsteady-state operation

Heavy water (D2O) is the most feasible moderator and coolant in nuclear-fission reactors while deuterium (D) will be the nuclear fuel for thermonuclear fusion in the distant future. The recoveries of deuterium in D2O and HDO from the separation of water–isotope mixture (H2O–HDO–D2O) by thermal diffusion has been estimated. First, the degrees of separation for each component of water–isotope mixture in thermal diffusion columns were predicted, then the recoveries of deuterium in each component were estimated from the molecule weights. It was found that the maximum recovery of deuterium might be obtained when the feed concentration of D2O is 0.22 mass fraction.

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