Study on clarification of tritium transfer in fusion reactor bIankets and on development of new processes to recover tritium

2011 Fiscal Year Final Research Report

• Project Area: Tritium Science and Technology for Fusion Reactor
• Project/Area Number: 19055006
• Research Category: Grant-in-Aid for Scientific Research on Priority Areas
• Allocation Type: Single-year Grants
• Review Section: Science and Engineering
• Research Institution: Kyushu University
• Principal Investigator: FUKADA Satoshi 九州大学, 大学院・総合理工学研究院, 教授 (50117230)
• Co-Investigator(Kenkyū-buntansha): ENOEDA Mikio 日本原子力研究開発機構, 核融合研究開発部門, 主任研究員 (90354620) ; KAWAMURA Yoshinori 日本原子力研究開発機構, 核融合研究開発部門, 主任研究員 (10354614) ; KATAYAMA Kazunari 九州大学, 大学院・総合理工学研究院, 助教 (90380708) ; NISHIKAWA Masabumi 九州大学, 大学院・総合理工学研究院, 名誉教授 (90026229) ; SAGARA Akio 核融合科学研究所, 核融合システム研究系, 核融合研究プロジェクト総主幹,教授 (20187058)
• Project Period (FY): 2007 – 2011
• Keywords: 核融合 / トリチウム / 安全性 / ブランケット / 増殖率 / 透過漏洩

Research Abstract

Based on material's tritium breeding ratio (TBR) and tritium retentions that have been already determined for solid breeding materials of Li_2TiO_3 and Li_4SiO_4 and liquid breeding materials of Li, Li-Pb eutectic alloy and Flibe molten salt, blanket systems are experimentally investigated to achieve tritium self-sufficient condition and to realize safety to lower level than allowable tritium leak rate. Micro-scale He convection in solid blankets and new tritium recovery systems are experimentally proved for each of the solid and liquid blankets. The present study is heavily contributed to realize fusion reactor systems.

Research Products

• [Journal Article] Transfer of tritium in concrete coated with hydrophobic paints (2012)
  • Author(s): S. Fukada, Y. Edao, K. Sato, T, Takeishi, K. Katayama, K. Kobayashi, T. Hayashi, T. Yamanishi, Y. Hatano, A. Taguchi, S. Akamaru
  • Journal Title: Fusion Engineering and Design Volume: 87 Pages: 54-60
  • Peer Reviewed
• [Journal Article] Effects of preadsorbed H_2O and CH_4 on H_2 and He adsorption of activated carbon at cryogenic temperature (2012)
  • Author(s): S. Fukada, M. Ueda, T. Izumi, G. Wu, K. Katayama
  • Journal Title: Fusion Science and Technology Volume: 61 Pages: 282-289
  • Peer Reviewed
• [Journal Article] Experiments of hydrogen isotope permeation, diffusion and dissolution in Li-Pb (2011)
  • Author(s): Y. Edao, H. Noguchi, S. Fukada
  • Journal Title: Journal of Nuclear Materials Volume: 417 Pages: 723-726
  • Peer Reviewed
• [Journal Article] Unresolved issues on tritium mass transfer in Li-Pb liquid blankets (2011)
  • Author(s): S. Fukada, Y. Edao
  • Journal Title: Journal of Nuclear Materials Volume: 417 Pages: 727-730
  • Peer Reviewed
• [Journal Article] Effect of surface water on tritium release behavior from Li_2TiO_3 (2011)
  • Author(s): T. Hanada, M. Nishikawa, T. Kanazawa, H. Yamasaki, N. Yamashita, S. Fukada
  • Journal Title: Journal of Nuclear Materials Volume: 417 Pages: 735-738
  • Peer Reviewed
• [Journal Article] Experimental clarification of the desorption of H_2, D_2 and He mixtures from cryosorption pump (2011)
  • Author(s): M. Terashita, S. Fukada
  • Journal Title: Journal of Nuclear Materials Volume: 417 Pages: 1179-1182
  • Peer Reviewed
• [Journal Article] Target system of IFMIF/EVEDA in Japanese activities (2011)
  • Author(s): M. Ida, S. Fukada, T. Furukawa, Y. Hirakawa, H. Horiike, T. Kanemura, H. Kondo, M. Miyashita, H. Nakamura, H. Sigiura, A. Suzuki, T. Terai, Y. Tsuji, H. Ushimaru, K. Watanabe, J. Yagi
  • Journal Title: Journal of Nuclear Materials Volume: 417 Pages: 1294-1298
  • Peer Reviewed
• [Journal Article] Leakage control of tritium through heat cycles of conceptual-design, laser-fusion reactor Koyo-F (2011)
  • Author(s): T. Norimatsu, H. Saika, H. Homma, M. Nakai, S. Fukada
  • Journal Title: Fusion Science and Technology Volume: 60 Pages: 893-896
  • Peer Reviewed
• [Journal Article] Stability of NaI (T1) detector for tritium monitor of BIXS use to hot environment (2011)
  • Author(s): Y. Kawamura, W. Shu, M. Matsuyama, T. Yamanishi
  • Journal Title: Fusion Science and Technology Volume: 60 Pages: 986-989
  • Peer Reviewed
• [Journal Article] Tritium monitoring using magnetically-levitated-electrode ionization chambers (2011)
  • Author(s): K. Ichiki, T. Kawaguchi, K. Ishibashi, N. Ikeda, S. Fukada, G. Wakabayashi, Y. Kawabata
  • Journal Title: Fusion Science and Technology Volume: 60 Pages: 994-997
  • Peer Reviewed
• [Journal Article] Demonstration of tritium extraction from tritiated methane in helium by utilizing plasma decomposition (2011)
  • Author(s): K. Katayama, S. Fukada, M. Nishikawa
  • Journal Title: Fusion Science and Technology Volume: 60 Pages: 1151-1154
  • Peer Reviewed
• [Journal Article] Permeation of two-component hydrogen isotopes in lithium-lead eutectic alloy (2011)
  • Author(s): Y. Edao, H. Okitsu, H. Noguchi, and S. Fukada
  • Journal Title: Fusion Science and Technology Volume: 60 Pages: 1163-1166
  • Peer Reviewed
• [Journal Article] Study on tritium release behavior from Li_2ZrO_3 (2011)
  • Author(s): T. Kanazawa, M. Nishikawa, H. Yamasaki, K. Katayama, H. Kashimura, T. Hanada, S. Fukada
  • Journal Title: Fusion Science and Technology Volume: 60 Pages: 1167-1170
  • Peer Reviewed
• [Journal Article] IFMIF/EVEDA lithium test loop: design and fabrication technology of target assembly as ａ key component (2011)
  • Author(s): H. Kondo, T. Furukawa, Y. Hirakawa, K Nakamura, M. Ida, K. Watanabe, T. Kaneraura, E. Wakai, H. Horiike, N. Yamaoka, H. Sugiura, T. Terai, A. Suzuki, J. Yagi, S. Fukada, H. Nakamura, I. Matsushita, F. Groeschel, K. Fujishiro, P. Garin, H. Kimura
  • Journal Title: Nuclear Fusion Volume: 51 Pages: 1-12
  • Peer Reviewed
• [Journal Article] Hydrogen incorporation in tungsten deposits growing by deuterium plasma sputtering (2011)
  • Author(s): K. Katayama, S. Kasahara, S. Ishikawa, S. Fukada, M. Nishikawa
  • Journal Title: Fusion Engineering and Design Volume: 86 Pages: 1702-1705
  • Peer Reviewed
• [Journal Article] Tritium recovery from blanket sweep gas via ceramic proton conductor membrane (2011)
  • Author(s): Y. Kawamura, T. Yamanishi
  • Journal Title: Fusion Engineering and Design Volume: 86 Pages: 2160-2163
  • Peer Reviewed
• [Journal Article] Recent status of fabrication technology development of water cooled ceramic breeder test blanket module in Japan (2011)
  • Author(s): T. Hirose, H. Tanigawa, A. Yoshikawa, Y. Seki, D. Tsuru, K. Yokoyama, K. Ezato, S. Suzuki, M. Enoeda, M. Akiba
  • Journal Title: Fusion Engineering and Design Volume: 86 Pages: 2265-2268
  • Peer Reviewed
• [Journal Article] Mixed desorption of He, H_2, and CH_4 adsorbed on charcoal maximally cooled at 10 K (2010)
  • Author(s): S. Fukada, M. Terashita
  • Journal Title: Journal of Nuclear Science and Technology Volume: 47 Pages: 1219-1226
  • Peer Reviewed
• [Journal Article] Effects of simultaneous transfer of heat and tritium through Li-Pb or Flibe blanket (2010)
  • Author(s): S. Fukada, Y. Edao, A. Sagara
  • Journal Title: Fusion Engineering and Design Volume: 85 Pages: 1314-1319
  • Peer Reviewed
• [Presentation] カルシウム交換型モルデナイトの水素同位体吸着速度 (2012)
  • Author(s): 河村繕範, 山西敏彦
  • Organizer: 日本原子力学会2012年春の年会
  • Place of Presentation: 福井
  • Year and Date: 20120319-21
• [Presentation] Fabrication of hydrogen recovery unit in the molten salt loop Oroshi-1 (2011)
  • Author(s): T. Nagasaka, T. Tanaka, A. Sagara, T. Muroga, M. Kondo, T. Watanabe, S. Fukada, H. Yukawa, T. Namba, T. Iikubo
  • Organizer: 21^<st> International Toki Conference on Integration of Fusion Science and Technology for steady-state operation
  • Place of Presentation: Toki, Japan
  • Year and Date: 20111128-30
• [Presentation] Hydrogen recovery from liquid Li with Y hot trap (2011)
  • Author(s): S. Shigeharu, Y. Hatachi, T. Hiromoto, Y. Edao, S. Fukada
  • Organizer: 21^<st> International Toki Conference on Integration of Fusion Science and Technology for steady-state operation
  • Place of Presentation: Toki, Japan
  • Year and Date: 20111128-30
• [Presentation] Hydrogen permeation of stainless steel with surface modification of nitride by electrochemical technique (2011)
  • Author(s): T. Watanabe, Y. Edao, T. Tanaka, A. Sagara, S. Fukada
  • Organizer: 21^<st> International Toki Conference on Integration of Fusion Science and Technology for steady-state operation
  • Place of Presentation: Toki, Japan
  • Year and Date: 20111128-30
• [Presentation] Analysis of simultaneous H and D permeation through lithium-lead (2011)
  • Author(s): M. Okada, H. Okitsu, Y. Edao, S. Fukada
  • Organizer: 21^<st> International Toki Conference on Integration of Fusion Science and Technology for steady-state operation
  • Place of Presentation: Toki, Japan
  • Year and Date: 20111128-30
• [Presentation] Progress of ITER Test Blanket Module Development in Japan (2011)
  • Author(s): M. Enoeda, H. Tanigawa, T. Hirose, S. Suzuki, K. Ochiai, C. Konno, Y. Kawamura, T. Yamanishi, T. Hoshino, M. Nakamichi, H. Tanigawa, K. Ezato, Y. Seki, A. Yoshikawa, D. Tsuru
  • Organizer: 21st International Toki Conference (ITC-21) on Integration of Fusion Science and Technology for Steady State Operation
  • Place of Presentation: Toki, Japan
  • Year and Date: 20111128-30
• [Presentation] R&D of prediction system for tritium transport in pebble bed breeder blanket (2011)
  • Author(s): Y. Seki, T. Hirose, H. Tanigawa, M. Enoeda
  • Organizer: Plasma Conference 2011
  • Place of Presentation: Kanazawa, Japan
  • Year and Date: 20111122-25
• [Presentation] Effect of Cation Exchange on Hydrogen Adsorption Property of Mordenite for Isotope Separation (2011)
  • Author(s): Y. Kawamura, Y. Iwai, K. Munakata, T. Yamanishi
  • Organizer: 15th International Conference on Fusion Reactor Materials (ICFRM-15)
  • Place of Presentation: Charleston, USA.
  • Year and Date: 20111016-22
• [Presentation] ブランケットからのトリチウム回収(3)固体増殖材の水分生成反応がトリチウム放出に与える影響 (2011)
  • Author(s): 柏村英明, 片山一成, 山崎英樹, 深田智, 酉川正史, 松田将平
  • Organizer: 日本原子力学会2011年秋の大会
  • Place of Presentation: 北九州
  • Year and Date: 20110919-22
• [Presentation] Analysis of diffusion and dissolution of two-component hydrogen (H+D) in lead lithium (2011)
  • Author(s): H. Okitsu, Y. Edao, M. Okada, S. Fukada
  • Organizer: ISFNT-10
  • Place of Presentation: Portland, USA.
  • Year and Date: 20110912-16
• [Presentation] Release behavior of water vapor and mass loss from lithium titariate (2011)
  • Author(s): K. Katayama, H. Kashimura, T. Hoshino, M. Nishikawa, H. Yamasaki, S. Ishikawa, Y. Ohnishi, S. Fukada
  • Organizer: ISFNT-10
  • Place of Presentation: Portland, USA.
  • Year and Date: 20110912-16
• [Presentation] Desorption behavior of hydrogen isotopes from tungsten deposit caused by plasma exposure (2011)
  • Author(s): S. Ishikawa, K. Katayama, Y. Ohnishi, S. Fukada, M. Nishikawa
  • Organizer: ISFNT-10
  • Place of Presentation: Portland, USA.
  • Year and Date: 20110912-16
• [Presentation] Effect of hydrophobic paints coating for tritium reduction in concrete materials (2011)
  • Author(s): Y. Edao, S. Fukada, Y. Nishimura, T. Takeishi, K. Katayama, Y. Hatano, A. Taguchi
  • Organizer: ISFNT-10
  • Place of Presentation: Portland, USA.
  • Year and Date: 20110912-16
• [Presentation] Effect of water vapor on tritium permeation behavior (2011)
  • Author(s): H. Yamasaki, H. Kashimura, S. Matsuda, T. Kanazawa, T. Hanada, K. Katayama, S. Fukada, M. Nshikawa
  • Organizer: ISFNT-10
  • Place of Presentation: Portland, USA.
  • Year and Date: 20110912-16
• [Presentation] Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan (2011)
  • Author(s): M. Enoeda, H. Tanigawa, T. Hirose, S. Suzuki, K. Ezato, Y. Seki, A. Yoshikawa, D. Tsuru, K. Ochiai, C. Konno, Y. Kawamura, T. Yamanishi, T. Hoshino, M. Nakamichi, H. Tanigawa, M. Akiba
  • Organizer: 10th International Symposium on Fusion Nuclear Technology (ISFNT-10)
  • Place of Presentation: Portland, USA.
  • Year and Date: 20110912-16
• [Presentation] Analysis of hydrogen isotopes absorption between liquid lithium and yttrium under dynamic conditions (2011)
  • Author(s): Y. Hatachi, S. Shigeharu, K. Katekari, Y. Edao, S. Fukada
  • Organizer: ISFNT-10
  • Place of Presentation: Portland, USA.
  • Year and Date: 20110912-16
• [Presentation] Tritium recovery online experiment for Li_2TiO_3 pebble blanket under DT neutron irradiation (2011)
  • Author(s): K. Ochiai, Y. Kawamura, T. Hoshino, Y. Iwai, K. Kobayashi, K. Kondo, M. Nakamichi, C. Konno
  • Organizer: 16th International Workshop on Ceramic Breeder Blanket Interactions
  • Place of Presentation: Portland
  • Year and Date: 20110908-10
• [Presentation] Experimental study of helium purge flow in pebble bed for solid breeder (2011)
  • Author(s): Y. Seki, S. Suzuki, M. Enoeda
  • Organizer: 16th International Workshop on Ceramic Breeder Blanket Interactions
  • Place of Presentation: Portland
  • Year and Date: 20110908-10
• [Presentation] Tritium recovery from liquid blanket systems of fusion reactor (2011)
  • Author(s): S. Fukada, Y. Edao, K. Katekari, H. Okitsu, Y. Hatachi, M Okada, K. Tamari, K. Katayama
  • Organizer: 15th International Conference on Emerging Nuclear Energy Systems
  • Place of Presentation: San Francisco, USA(招待講演)
  • Year and Date: 20110515-19
• [Remarks]
  • URL: http://tritium.nifs.ac.jp/
• [Remarks]
  • URL: http://hyoka.ofc.kyushu-u.ac.jp/search/d
• [Remarks]
  • URL: etails/K001210/index.html