Study of multi-column cold trap with highly effective recovery rate of tritium water vapor
高效氚水蒸气回收率的多柱冷阱研究
基本信息
- 批准号:11558058
- 负责人:
- 金额:$ 2.62万
- 依托单位:
- 依托单位国家:日本
- 项目类别:Grant-in-Aid for Scientific Research (B).
- 财政年份:1999
- 资助国家:日本
- 起止时间:1999 至 2000
- 项目状态:已结题
- 来源:
- 关键词:
项目摘要
It is one of the most important issues to establish processes for tritium safety confinement and a fuel processing loop of a fusion reactor. In conventional processes for the emergency tritium confinement, catalytic oxidation and zeolite adsorption was the main process. Although the process can satisfy the safety rule for handling radioisotopes in Japanese facilities, the removal of tritium in interstitial sites of adsorbent was very difficult, and so it had a disadvantage of an increasae in tritium inventry. Therefore, it is necessary to improve the conventional catalytic oxidation and water adsorption process for the higher safety confinement of tritium gas and tritium compounds.The polyimede gas separation membrane can make gas volume processed decrease greatly and so make the process simple. In the present study we set up an experimental apparatus which can remove water vapor down to lower than the regulation level of tritium compounds in the environment without any use of adsorben … More t.In order to recover tritium water vapor down to the regulation level it was necessary to solve the problems of the tritium breakthrough of the cold trap and duct choking by deposition on the surfaces. In the first year of the present research, we found out that the tritium breakthrough was caused by mist generation under homogeneous nucleation. With the setup of a two-stages cooling system, we succeeded in operating it without mist formation, in quantitative estimation of frost formation rate on surfaces and so the time of choking, and finally in overall estimation of tritium removal rate. In the second year, we carried out experiments of the two stages tritium removal system comprising an open-column trap cooled by dry ice and glass-packed cold trap cooled by liquid nitrogen in series. The experimental results were presented in international journals such as Separation Science and Technology. We succeeded in the optimal design of the tritium removal system for an ITER-scale fusion reactor. Less
建立核聚变反应堆的氚安全约束过程和燃料处理回路是核聚变反应堆的重要问题之一。在常规的应急氚约束工艺中,催化氧化和沸石吸附是主要工艺。虽然该工艺可以满足日本设施放射性同位素处理的安全规则,但在吸附剂间隙位置去除氚非常困难,因此具有增加氚库存的缺点。因此,有必要对传统的催化氧化和水吸附工艺进行改进,以获得更高的安全约束氚气和氚化合物。聚酰亚胺气体分离膜可以使处理的气体体积大大减少,使工艺简单。在本研究中,我们建立了一个实验装置,可以在不使用吸附剂的情况下,将环境中氚化合物的水蒸气去除到低于调节水平,并且为了将氚水蒸气恢复到调节水平,必须解决冷阱中氚的突破和表面沉积导致管道窒息的问题。在本研究的第一年,我们发现氚的突破是由均匀成核下的雾生成引起的。通过建立两级冷却系统,我们成功地在没有雾形成的情况下运行,定量估计了表面上的结霜率和窒息时间,最后全面估计了氚的去除率。在第二年,我们进行了两级除氚系统的实验,包括干冰冷却的开柱式疏水阀和液氮冷却的玻璃填充冷疏水阀串联。实验结果发表在《分离科学与技术》等国际期刊上。我们成功地对iter规模核聚变反应堆的氚去除系统进行了优化设计。少
项目成果
期刊论文数量(36)
专著数量(0)
科研奖励数量(0)
会议论文数量(0)
专利数量(0)
深田智: "核融合炉内外におけるトリチウムメインテナンスと廃棄物処理 4.気体、液体からのトリチウム回収と除去"プラズマ・核融合学会誌. Vol.76. 1036-1043 (2000)
Satoshi Fukada:“聚变反应堆内部和外部的氚维护和废物处理4。从气体和液体中回收和去除氚”日本等离子体与聚变科学学会杂志第76卷1036-1043(2000年)。
- DOI:
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- 影响因子:0
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- 通讯作者:
S. Fukada and K. Inoue: "Internal Mass through Frost"AIChE Journal. 45. 2646-2652 (1999)
S. Fukada 和 K. Inoue:“通过霜的内部质量”AIChE 杂志。
- DOI:
- 发表时间:
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- 影响因子:0
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S.Fukada and K.Inoue.: "Internal Mass Flux through Frost"AIChE J.. Vol.45. 2646-2652 (1999)
S.Fukada 和 K.Inoue.:“通过霜的内部质量通量”AIChE J.. Vol.45。
- DOI:
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- 影响因子:0
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H.FUJIWARA,S.FUKADA, et al.: "Hydrogen Isotope Separation by Self-displacement Chromatography Using Palladium Particles"Journal of Nuclear Science and Technology. Vol.37. 724-726
H.FUJIWARA,S.FUKADA,等人:“使用钯颗粒的自置换色谱法分离氢同位素”核科学与技术杂志。
- DOI:
- 发表时间:
- 期刊:
- 影响因子:0
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- 通讯作者:
S. Fukada et al: "Mist formation in a Water Vapor Cold Trap and Evaluation of Its Removal Rate"Journal Nuclear Science and Technology. 35. 198-204 (1998)
S. Fukada 等人:“水蒸气冷阱中的雾气形成及其去除率的评估”核科学与技术杂志。
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- 影响因子:0
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{{ truncateString('FUKADA Satoshi', 18)}}的其他基金
Study on hydrogen production system assisted with heat pumps andhigh-temperature gas-cooled reactor
热泵辅助高温气冷堆制氢系统研究
- 批准号:
22656212 - 财政年份:2010
- 资助金额:
$ 2.62万 - 项目类别:
Grant-in-Aid for Challenging Exploratory Research
Clarification of tritium transfer inside concrete bui! di ng of fusion reactor and development of technology to decrease tritium permeation through concrete walIs
混凝土建筑内氚转移的澄清!
- 批准号:
21360451 - 财政年份:2009
- 资助金额:
$ 2.62万 - 项目类别:
Grant-in-Aid for Scientific Research (B)
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 - 财政年份:2005
- 资助金额:
$ 2.62万 - 项目类别:
Grant-in-Aid for Scientific Research (B)
Advanced study of tritium recovery from molten salt Flibe blanket in fusion reactor
聚变反应堆熔盐Flibe包层回收氚的最新研究
- 批准号:
14380220 - 财政年份:2002
- 资助金额:
$ 2.62万 - 项目类别:
Grant-in-Aid for Scientific Research (B)
A study on enrichment and volume reduction of tritiated water in a fusion reactor using photocatalysis
聚变反应堆中氚化水光催化富集减容研究
- 批准号:
12680493 - 财政年份:2000
- 资助金额:
$ 2.62万 - 项目类别:
Grant-in-Aid for Scientific Research (C)
A study of surface pretreatment of tritium-getter alloy for enhancement of insensitiveness to impurities
氚吸气合金表面预处理增强杂质不敏感性的研究
- 批准号:
10680473 - 财政年份:1998
- 资助金额:
$ 2.62万 - 项目类别:
Grant-in-Aid for Scientific Research (C)
Gas separation by a Pd-plated alumina membrane for a small-scale emergency atmospheric detritiation system
小型应急大气除氚系统的镀钯氧化铝膜气体分离
- 批准号:
07808056 - 财政年份:1995
- 资助金额:
$ 2.62万 - 项目类别:
Grant-in-Aid for Scientific Research (C)
相似海外基金
Concentrator, cold trap and pump
浓缩器、冷阱和泵
- 批准号:
218387-1999 - 财政年份:1998
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Research Tools and Instruments - Category 1 (<$150,000)
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研究启动--低温冷阱内的压力分布
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