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2007 Fiscal Year Final Research Report Summary

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

Research Project

Project/Area Number 17360443
Research Category

Grant-in-Aid for Scientific Research (B)

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear fusion studies
Research InstitutionKyushu University

Principal Investigator

FUKADA Satoshi  Kyushu University, Interdisciplinary Graduate School of Engineering Sciences, Professor (50117230)

Project Period (FY) 2005 – 2007
Keywordstritium water / distillation column / isotope separation / isotope enrichment / adsorbent / fusion reactor / Height equivalent to theoretical plate (HETP)
Research Abstract

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

  • Research Products

    (42 results)

All 2008 2007 2006 2005

All Journal Article (37 results) (of which Peer Reviewed: 18 results) Presentation (4 results) Book (1 results)

  • [Journal Article] The effect of water on tritium release behavior from solid breeder candidates2008

    • Author(s)
      K.Suematsu, M.Nishikawa, S.Fukada, T.Kinjyo, T.Koyama, N.Yamashita
    • Journal Title

      Fusion Science and Technology

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Concentration profiles of tritium penetrated in concrete2008

    • Author(s)
      H.Takata, K.Furuichi, M.Nishikawa, S.Fukada, K.Katayama, T.Takeishi, K.Kobayashi, T.Hayashi, H.Namba
    • Journal Title

      Fusion Science and Technology

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Tritium recovery system for Li-Pb loop of inertial fusion reactor2008

    • Author(s)
      S., Fukada, Y., Edao, Y., Maeda, T., Norimatsu
    • Journal Title

      Proc. 4th IAEA Technical meeting on physics and technology of IFE targets and chambers (in printing)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] The effect of water on tritium release behavior from solid breeder candidates2008

    • Author(s)
      K., Suematsu, M., Nishikawa, S., Fukada, T., Kinjyo, T., Koyama, N., Yamashita
    • Journal Title

      Fusion Science and Technology (in printing)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Concentration profiles of tritium penetrated in concrete2008

    • Author(s)
      H., Takata, K., Furuichi, M., Nishikawa, S., Fukada, K., Katayama, T., Takeishi, K., Kobayashi, T., Hayashi, H., Namba
    • Journal Title

      Fusion Science and Technology (in printing)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Partial oxidation of methane in a Nipermeable membrane tube for effective hydrogen production2007

    • Author(s)
      S.Fukada, S.Ono
    • Journal Title

      Separation Science and Technology 42

      Pages: 73-87

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Detritiation by using distillation column2007

    • Author(s)
      M.Koga, S.Fukada
    • Journal Title

      Proc.the 9th Cross Straits Symposium on Materials, Energy and Environmental Engineering

      Pages: 177-178

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] レーザー核融合炉トリチウム増殖燃料サイクル系について2007

    • Author(s)
      深田 智
    • Journal Title

      核融合工学部会部会報 14

      Pages: 44-47

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Verification to recover tritium in neutron-irradiated Li by Y plate2007

    • Author(s)
      S.Fukada, M.Kinoshita, Y.Maeda, T.Muroga
    • Journal Title

      Fusion Engineering and Design 82

      Pages: 2152-2157

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Recovery of tritium from Flibe blanket in fusion reactor2007

    • Author(s)
      S.Fukada, K.Katayama, T.Terai, A.Sagara
    • Journal Title

      Fusion Science and Technology 52

      Pages: 677-681

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Overall conductivity and electromotive force of SrZr_<0.9>Yb_<0.1>O_<3-a> cell system supplied with moist CH_42007

    • Author(s)
      S.Fukada, S.Suemori, K.0noda
    • Journal Title

      Journal Nuclear Science and Technology 44

      Pages: 1324-1329

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Adsorption properties of water vapor on sulfonated perfluoropolymer membrane2007

    • Author(s)
      H.Takata, N.Mizuno, M.Nishikawa, S.Fukada, M.Yoshitake
    • Journal Title

      International Journal of Hydrogen Energy 32

      Pages: 371-379

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Tritium recovery system for Li-Pb loop of inerfial fusion reactor2007

    • Author(s)
      S.Fukada, Y.Edao, Y.Maeda, T.Norimatsu
    • Journal Title

      Proc.4th IAEA Technical Meeting on Physics and Technology of IFE Targets and Chambers

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Partial oxidation of methane in a Ni permeable membrane tube for effective hydrogen production2007

    • Author(s)
      S., Fukada, S., Ono
    • Journal Title

      Separation Science and Technology 42

      Pages: 73-87

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Detritiation by using distillation column2007

    • Author(s)
      M., Koga, S., Fukada
    • Journal Title

      Proc. the 9th Cross Straits Symposium on Materials, Energy and Environmental Engineering

      Pages: 177-178

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] レーザー核融合炉トリチウム増殖燃料サイクル系について2007

    • Author(s)
      深田, 智
    • Journal Title

      核融合工学部会部会報 14

      Pages: 44-47

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Verification to recover tritiumin neutron irradiated Li by Y plate2007

    • Author(s)
      S., Fukada, M., Kinoshita, Y., Maeda, T., Muroga
    • Journal Title

      Fusion Engineering and Design 82

      Pages: 2152-2157

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Recovery of tritium from Flibe blanket in fusion reactor2007

    • Author(s)
      S., Fukada, K., Katayama, T., Terai, A., Sagara
    • Journal Title

      Fusion Science and Technology 52

      Pages: 677-681

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Overall conductivity and electromotive force of SrZr_0.9Yb_0.1 O_3-a cell system supplied with moist CH_42007

    • Author(s)
      S., Fukada, S., Suemori, K., Onoda
    • Journal Title

      Journal Nuclear Science and Technology 44

      Pages: 1324-1329

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] water vapor on sulfonated perfluoropolymer membrane2007

    • Author(s)
      H., Takata, N., Mizuno, M., Nishikawa, S., Fukada, M., Yoshitake
    • Journal Title

      International Journal of Hydrogen Energy 32

      Pages: 371-379

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Transient behavior of enrichment of tritium water in adsorption-distillation column2006

    • Author(s)
      S.Fukada
    • Journal Title

      Journa lof Nuclear Science and Technology 43

      Pages: 423-426

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Recovery of tritium from liquid blanket materials2006

    • Author(s)
      S.Fukada
    • Journal Title

      Proceedings of A mini-workshop on ITER Related Tritium Technology in China

      Pages: 51-57

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Transient behavior of enrichment of tritium water in adsorption-distillation column2006

    • Author(s)
      S., Fukada
    • Journal Title

      Journal of Nuclear Science and Technology 43

      Pages: 423-426

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Recovery of tritium from liquid blanket materials2006

    • Author(s)
      S., Fukada
    • Journal Title

      Proceedings of a mini-workshop on ITER related tritium technology in China

      Pages: 51-57

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Tritium isotope separation using adsorption-distillation column2005

    • Author(s)
      S.Fukada
    • Journal Title

      Fusion Science and Technology 48

      Pages: 141-143

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] 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2005

    • Author(s)
      深田 智、林
    • Journal Title

      日本原子力学会誌 47

      Pages: 623-629

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Proton transfer in SrCeO_3-based oxide with internal reformation under supply of CH_4 and H_2O2005

    • Author(s)
      S.Fukada, S.Suemori, K.Onoda
    • Journal Title

      Journal of Nuclear Materials 348

      Pages: 26-32

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] 国際核融合材料照射施設(IFMIF)の設計と開発の現状、3.ターゲット系の開発2005

    • Author(s)
      中村 博雄、堀池 寛、.近藤 浩夫、田中 知、深田 智
    • Journal Title

      プラズマ核融合学会 82

      Pages: 16-20

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Diffusion coefficient of tritium through a molten salt Flibe blanket and evaluation of tritium leak from fusion reactor system2005

    • Author(s)
      S.Fukada, R.A.Anderl, T.Terai, A.Sagara, M.Nishikawa
    • Journal Title

      Fusion Science and Technology 48

      Pages: 666-669

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Study on water uptake of proton exchange membrane by using tritiated water sorption method2005

    • Author(s)
      H.Takata, M.Nishikawa, Y.Arimura, T.Egawa, S.Fukada, M.Yoshitake
    • Journal Title

      International Journal of Hydrogen Energy 30

      Pages: 1017-1025

    • Description
      「研究成果報告書概要(和文)」より
    • Peer Reviewed
  • [Journal Article] Tritium isotope separation using adsorption-distillation column2005

    • Author(s)
      S., Fukada
    • Journal Title

      Fusion Science and Technology 48

      Pages: 141-143

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] 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2005

    • Author(s)
      深田, 智, 林
    • Journal Title

      日本原子力学会誌 47

      Pages: 623-629

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Proton transfer in SrCeO_3 based oxide with internal reformation under supply of CH_4 and H_2O2005

    • Author(s)
      S., Fukada, S., Suemori, K., Onoda
    • Journal Title

      Journal of Nuclear Materials 348

      Pages: 26-32

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Diffusion coefficient of tritium through a molten salt Flibe blanket and evaluation of tritium leak from fusion reactor system2005

    • Author(s)
      S., Fukada, R. A., Anderl, T., Terai, A., Sagara, M., Nishikawa
    • Journal Title

      Fusion Science and Technology 48

      Pages: 666-669

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Experiment and analysis of mass transfer in SrCe_<0.95>Yb_<0.05>O_3-a fuel cell using complex impedance plot2005

    • Author(s)
      S., Fukada, K., Onoda, S., Suemori
    • Journal Title

      Journal of Nuclear S cience and Technology 42

      Pages: 305-311

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Hydrogen diffusion in liquid lithium from 500℃ to 650℃2005

    • Author(s)
      S., Fukada, M., Kinoshita, K., Kuroki, T., Muroga
    • Journal Title

      Journal of Nuclear Materials 346

      Pages: 293-297

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Study on water uptake of proton exchange membrane by using tritiated water sorption method2005

    • Author(s)
      H., Takata, M., Nishikawa, Y., Arimura, T., Egawa, S., Fukada, M., Yoshitake
    • Journal Title

      International Journal of Hydrogen Energy 30

      Pages: 1017-1025

    • Description
      「研究成果報告書概要(欧文)」より
  • [Presentation] LHD排出気体/液体処理系の開発研究-高分子透過膜除湿装置の設計検討2008

    • Author(s)
      朝倉 大和、田中 将裕、奥野 健二、大矢 恭久、深田 智
    • Organizer
      日本原子力学会春の大会
    • Place of Presentation
      大阪大学吹田キャンパス
    • Year and Date
      20080300
    • Description
      「研究成果報告書概要(和文)」より
  • [Presentation] Detritiation by using distillation column2007

    • Author(s)
      M.Koga, S.Fukada
    • Organizer
      the 9th Cross Straits Symposium on Materials, Energy and Environmental Engineering
    • Place of Presentation
      Pohang,Korea
    • Year and Date
      20071121-22
    • Description
      「研究成果報告書概要(和文)」より
  • [Presentation] 吸着剤によるトリチウム水蒸留塔高効率化の研究2007

    • Author(s)
      古賀 雅人、深田 智
    • Organizer
      日本原子力学会九州支部第26回研究発表講演会
    • Place of Presentation
      福岡市
    • Year and Date
      2007-12-07
    • Description
      「研究成果報告書概要(和文)」より
  • [Presentation] 核融合排気ガス処理システムの研究2007

    • Author(s)
      寺下 真史、深田 智
    • Organizer
      日本原子力学会九州支部第26回研究発表講演会
    • Place of Presentation
      福岡市
    • Year and Date
      2007-12-07
    • Description
      「研究成果報告書概要(和文)」より
  • [Book] 水素-将来のエネルギーを目指して2006

    • Author(s)
      西川 正史、深田 智、渡辺 幸信
    • Total Pages
      310
    • Publisher
      養賢堂
    • Description
      「研究成果報告書概要(和文)」より

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Published: 2010-02-04  

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