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

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
这是建立tri骨安全性限制过程的最重要问题之一,以及融合反应器的燃料处理环。 Handlesese设施的安全规则t具有trip的劣势。建立一个实验设备,该设备可以使水蒸气蒸气降低到大于大于以上以上的速率,而不必使用Adsorben的环境中的调节水平……更多的t.in t.in是为了恢复蒸气蒸汽降低至校长水平是通过在第一个s核中通过沉积的trap trap的trap。在表面上的形成速率和窒息时间的定量估计中,我们在整体上进行了估计,我们进行了两个阶段的t阶段去除系统的实验液体中的氮是在国际科学和技术中提出的。

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)
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:
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    0
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S.Fukada: "Fuel for Future Energy Separation Technology of Hydrogen Isotopes Using Hydrogen-Absorbing Alloys"N.T.S.Corp.. 328 (2000)
S.Fukada:“使用吸氢合金的氢同位素未来能源分离技术的燃料”N.T.S.Corp. 328 (2000)
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    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。
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    0
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  • 通讯作者:
H.Fujiwara,S.Fukada et al.: "Hydrogenating Rates of Twin Columns Packed with Pd and Molecular Sieve with an Alternately Countercurrent Flow for Hydrogen Isotope Separation"International Journal of Hydrogen Energy. Vol.25. 127-132 (2000)
H.Fujiwara、S.Fukada 等人:“用于氢同位素分离的交替逆流流动的填充有 Pd 和分子筛的双柱的氢化速率”国际氢能杂志。
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    0
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  • 通讯作者:
S.Fukada: "Maintenance and Waste Treatment of Tritium Existing in or out of Fusion Reactor 4. Tritium Recovery and Removal from Liquid Blankets (in Japanese)"Journal of Plasma and Fusion Research. Vol.76. 1036-1043 (2000)
S.Fukada:“聚变反应堆内外存在的氚的维护和废物处理4。从液体覆盖层中回收和去除氚(日语)”等离子体与聚变研究杂志。
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    0
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FUKADA Satoshi其他文献

FUKADA Satoshi的其他文献

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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)

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