Study on highly-efficient enrichment of tritium water by use of distillation column packed with hydrophilic adsorbent

亲水吸附剂精馏塔高效富集氚水的研究

• 批准号: 17360443
• 负责人: FUKADA Satoshi
• 金额: $ 5.47万
• 依托单位: Kyushu University
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for Scientific Research (B)
• 财政年份: 2005
• 资助国家: 日本
• 起止时间: 2005 至 2007
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-17360443/
• 关键词: tritium water; distillation column; isotope separation; isotope enrichment; adsorbent; fusion reactor; Height equivalent to theoretical plate (HETP); トリチワム水; ITER

Tritium-waste water will be drained from facilities for a tritium fuel cycle of a future fusion reactor or is presently exhausted from uranium fuel reprocessing plant for a fission reactor. When its concentration is lower than the legally regulated one (60Bq/cm^3), it can be drained from the facilities as it is. When it is higher than the legal value, the drain water has to be diluted by a large amount of fresh water or has to be enriched/separated in the facilities. There is less difficulty in the dilution process. However, when its tritium concentration is much higher than the regulated level, we need to develop a new isotope separation system to decontaminate the tritium-waste water drain at a lower level than the regulated level and to separate a small amount of high-level tritium water. Although the H_2H_2O isotopic exchange method that was used for a heavy water separation of CANDU reactor can be applied to the tritium enrichment, the facilities for the deuterium separation are h … More uge, and they need a special and expensive Pt catalyst. In addition, the Pt catalyst performance is deteriorated by CO that will be included in the exhaust gas of fusion facilities. Therefore, the process needs pretreatment to reduce some pollutants. In the present study, a new isotope separation method to enhance the performance of a classical distillation column with use of hydrophilic adsorbents. As candidates for the hydrophilic adsorbent, silica-gel and zeolite adsorbents were comparatively experimented in the present study. The original isotope separation factor based on the difference in vapor pressure between H_2O and HTO is 1.028. It was found that the isotope separation factor was enhanced to 1.1 to 1.2 with the use of the hydrophilic adsorbent, and therefore it can downsize the scale of the tritium enrichment and separation. The silica-gel column attained the comparatively large separation performance in the various ranges of vapor flow rate. On the other hand, the zeolite column (commercial name Linde molecular sieve 13X) attained the largest isotope separation performance at very small vapor flow rate, but the separation factor decreased at higher flow rate. This is because the exchange reaction between HTO in the vapor phase and H_2O on the adsorbent is comparatively slow. Therefore, the number of transfer unit (NTP) of the zeolite column was much smaller than that of the silica-gel column. The zeolite column is considered to be effective especially for the very small vapor flow rate. The transient tritium enrichment performance was experimentally determined, and it was found that the numerical calculation based on the plate model that uses the number of transfer unit fitted the experimental ones. The experimental and numerical results were presented in the research papers listed in the next page. The abstract of the present scientific research is summarized in a report. Less

将trium的水从设施中排出，以使未来的融合反应堆的trium燃料循环或从铀燃料重新加工植物中耗尽的裂变反应器。当其浓度低于法律调节的一个（60BQ/cm^3）时，它可以从设施中排出。当它高于法律价值时，排水水必须被大量淡水稀释，或者必须在设施中富集/分离。稀释过程的难度较小。但是，当它的tri浓浓度远高于调节水平时，我们需要开发一种新的同位素分离系统，以低于调节水平的水平降低tri虫水的排水口，并分离少量的高级tri含水。尽管用于将candu反应器进行重水分离的H_2H_2O同位素交换方法可以应用于tri富富集，但氘间隔的设施是H…更uge，并且需要一种特殊且昂贵的PT催化剂。此外，PT催化剂性能由CO确定，该CO将包括在融合设施的废气中。因此，该过程需要预处理以减少一些污染物。在本研究中，通过使用亲水性吸附剂来增强经典蒸馏柱的性能，一种新的同位素分离方法。在本研究中，对亲水吸附剂，硅胶和沸石吸附剂的候选者进行了相对实验。基于H_2O和HTO之间蒸气压的差异的原始同位素分离因子为1.028。发现使用亲水性吸附剂将同位素分离因子提高到1.1至1.2，因此可以缩小tri酶和分离的尺寸。在蒸气流量的各种范围内，硅胶柱达到了相对较大的分离性能。另一方面，沸石柱（商业名称Linde Molecular Siee 13倍）在非常小的蒸气流速下达到了最大的同位素分离性能，但分离因子在较高的流速下降低。这是因为蒸气相和吸附剂上H_2O之间的交换反应相对较慢。因此，沸石柱的转移单元（NTP）的数量远小于硅胶柱的传递单位（NTP）。沸石柱被认为是有效的，特别是对于非常小的蒸气流速。实验确定了瞬态tri富富度性能，发现基于使用传输单元数量的板模型的数值计算拟合了实验。实验和数值结果在下一页列出的研究论文中介绍。报告中总结了本科学研究的摘要。较少的

项目成果

Tritium recovery system for Li-Pb loop of inerfial fusion reactor

惯性聚变反应堆Li-Pb回路氚回收系统

• 发表时间: 2007
• 期刊: Proc.4th IAEA Technical Meeting on Physics and Technology of IFE Targets and Chambers
• 作者: S.Fukada;Y.Edao;Y.Maeda;T.Norimatsu
• 通讯作者: T.Norimatsu

Tritium recovery system for Li-Pb loop of inertial fusion reactor

惯性聚变反应堆Li-Pb回路氚回收系统

• 发表时间: 2008
• 期刊: Proc. 4th IAEA Technical meeting on physics and technology of IFE targets and chambers (in printing)
• 作者: S.;Fukada;Y.;Edao;Y.;Maeda;T.;Norimatsu
• 通讯作者: Norimatsu

Study on water uptake of proton exchange membrane by using tritiated water sorption method

• DOI: 10.1016/j.ijhydene.2005.02.006
• 发表时间: 2005-08
• 期刊: International Journal of Hydrogen Energy
• 影响因子: 7.2
• 作者: H. Takata;M. Nishikawa;Yusaku Arimura;T. Egawa;S. Fukada;M. Yoshitake

よく分かる核融合炉のしくみ 第8回トリチウムを扱う燃料循環システム

易于理解的核聚变反应堆机制第8部分：处理氚的燃料循环系统

• 发表时间: 2005
• 期刊: 日本原子力学会誌 47
• 作者: 深田 智;林
• 通讯作者: 林

Concentration profiles of tritium penetrated in concrete

渗入混凝土中的氚浓度分布

• 发表时间: 2008
• 期刊: Fusion Science and Technology
• 影响因子: 0.9
• 作者: H.Takata;K.Furuichi;M.Nishikawa;S.Fukada;K.Katayama;T.Takeishi;K.Kobayashi;T.Hayashi;H.Namba
• 通讯作者: H.Namba