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

基本信息

  • 批准号:
    10680473
  • 负责人:
  • 金额:
    $ 2.11万
  • 依托单位:
  • 依托单位国家:
    日本
  • 项目类别:
    Grant-in-Aid for Scientific Research (C)
  • 财政年份:
    1998
  • 资助国家:
    日本
  • 起止时间:
    1998 至 1999
  • 项目状态:
    已结题

项目摘要

Some zirconium-alloy getters are expected to be used for tritium separation, purification and storage in a fuel cycle of a nuclear fusion reactor. We have been investigated particle beds of Zr, ZrCo, ZrNi and ZrィイD22ィエD2Fe which can recover the tritium concentration in gas streams lower than the maximum permissible level for the radioisotope in Japan. However, once tritium-getters contact with any of the gaseous impurities such as OィイD22ィエD2, HィイD22ィエD2O and CO, they lose most of their hydrogen capacities. Based on our previous experimental studies on mass-transfer processes in alloy beds, new surface pretreatment techniques in order to enhance insensitiveness to impurities were tested with their keeping the high absorption capacity. The three surface pretreatment techniques are (1) alkali pretreatment, (2) pd depositing (3) Cu depositing. In 1998 we comparatively investigated the surface pretreatment to the ZrィイD22ィエD2Fe getter, and its hydrogenating rate after the alkali pretreatment was enhanced about ten times faster than that of the non-treated getter. It was found that pretreated ZrィイD22ィエD2Fe particles under the room temperature can absorb tritium less than the detection limit. In 1999, methane and tritium water vapor cracking by a Zr(MnィイD20.5ィエD2FeィイD20.5ィエD2)ィイD22ィエD2 bed was experimentally investigated. Methane at higher than 650ィイD1゜ィエD1C and water vapor at 350ィイD1゜ィエD1C were successfully cracked by the Zr(MnィイD20.5ィエD2FeィイD20.5ィエD2)ィイD22ィエD2 bed. Results obtained in the present study have been presented at the international symposium of the fusion nuclear technology and that of the hydrogen energy and have been also reported to international journals.
预计将使用一些锆 - 铝制捕获器用于Zr,Zrco,Zrni和Zr II D22 Yi D2FE的颗粒层,该层可以在日本h h h h h h h h h h h h h h h h h h h h h h h h h h h h h h h he h h h h h h h h h h s gas cropt诸如O -I D22 Yi D22 Yi D2O和CO之类的气态杂质,它们基于我们的氢化功能,以增强其氢化功能。 (2)PD沉积(3)CU沉积在1998年,我们比较表面预处理ZR ZR ZR D22 YIE D2FE Getter,其碱性预处理后的氢化速率增强了大约十倍的速度检测极限。 .5 I D20.5 I D2)Lei D22床。

项目成果

期刊论文数量(19)
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. Morimitsu, S. Fukada, et al.: "Experimental Study on Hydrogen-Absorbing Alloy Heat-Pump Working in the High Temperature Region"Proc. of the 5th Korea-Japan Joint Symposium '99 on Hydrogen Energy, Yusong in Korea. 77-82 (1999)
S. Morimitsu,S. Fukada,等:“吸氢合金热泵在高温区工作的实验研究”Proc。
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    0
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S. Fukada et al.: "Hydrogen Isotope Separation with Palladium Particle Bed"Fusion Engineering Design. 39-40. 995-999 (1998)
S. Fukada 等人:“钯粒子床氢同位素分离”聚变工程设计。
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    0
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H. Fujiwara and S. Fukada: "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. 25. 127-132 (2000)
H. Fujiwara 和 S. Fukada:“用于氢同位素分离的交替逆流流动的填充有钯和分子筛的双柱的氢化速率”国际氢能杂志。
  • DOI:
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  • 影响因子:
    0
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S. Fukada et al: "A Study on Particle Beds of LaNi, LaNi_< 2> and LaNi_< 3> for Purification of Hydrogen Isotopes"Proc. of the 4th Inter. Conf on New Energy System and Conversions. 59-64 (1999)
S. Fukada 等:“用于纯化氢同位素的 LaNi、LaNi_<2> 和 LaNi_<3> 颗粒床的研究”Proc.
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    0
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S.Fukada et al.: "Zr_2Fe and Zr(Mn_<0.5>Fe_<0.5>)_2 Particle Beds for High Purification of Tritium and Impurity Removal in a Fuel Cycle"Proc.The fifth International Symposium on Fusion Nuclear Technology. 印刷中. (2000)
S. Fukada 等人:“Zr_2Fe 和 Zr(Mn_<0.5>Fe_<0.5>)_2 粒子床用于燃料循环中氚的高纯化和杂质去除”论文集,第五届国际聚变核技术研讨会正在出版。 (2000)
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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:
    $ 2.11万
  • 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:
    $ 2.11万
  • 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:
    $ 2.11万
  • 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:
    $ 2.11万
  • 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:
    $ 2.11万
  • 项目类别:
    Grant-in-Aid for Scientific Research (C)
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
  • 批准号:
    11558058
  • 财政年份:
    1999
  • 资助金额:
    $ 2.11万
  • 项目类别:
    Grant-in-Aid for Scientific Research (B).
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:
    $ 2.11万
  • 项目类别:
    Grant-in-Aid for Scientific Research (C)

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Coated Zirconium Alloy Fuel Rod Cladding for Accident Tolerance
涂层锆合金燃料棒包壳可耐受事故
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实现氢的 3D 原子级成像以研究裂变反应堆中锆合金燃料包壳的氢脆
  • 批准号:
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锆合金中的相变诱导塑性
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