ENOEDA Mikio 榎枝幹男

Researcher Number	90354620
Affiliation (based on the past Project Information) *help	2011: 日本原子力研究開発機構, 核融合工学部, 主任研究員 2011: 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 2010: 原子力研究開発機構, 核融合工学部, 主任研究員 2009: 日本原子力研究開発機構, 核融合工学部, 主任研究員 2008: 日木原子力研究開発機構, 核融合工学部, 主任研究員 2007: 原子力研究開発機構, 核融合工学部, 主任研究員
Review Section/Research Field	Except Principal Investigator Science and Engineering
Keywords	Except Principal Investigator ノリチウム / 同位体交換 / 吸着 / リチウム酸化物 / 核融合炉 / 原子力エネルギー / プラズマ・核融合 / 透過 / 回収 / リチウム … More / プラズマ核融合 / 透過漏洩 / 増殖率 / ブランケット / 安全性 / トリチウム / 核融合 Less

Study on clarification of tritium transfer in fusion reactor bIankets and on development of new processes to recover tritium
- Principal Investigator
  
  FUKADA Satoshi
- Project Period (FY)
  2007 – 2011
- Research Category
  
  Grant-in-Aid for Scientific Research on Priority Areas
- Review Section
  
  Science and Engineering
- Research Institution
  Kyushu University

All 2011 2010 2009 2008 2007

All Journal Article Presentation

[Journal Article] Recent status of fabrication technology development of water cooled ceramic breeder test blanket module in Japan2011
- 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
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] Overview of the ITER TBM R&D activities in Japan2010
- Author(s)
  M.Akiba, M.Enoeda, S.Tanaka
- Journal Title
  
  Fusion Engineering and Design
  
  Volume: 85 Pages: 1766-1771
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] Status of the development of Water Cooled Ceramic Breeder (WCCB) Test Blanket Module2009
- Author(s)
  M.Enoeda, S.Suzulci, D.Tsuru, T.Hirose, Hisashi Tanigawa, Y.Seki, K.Ezato, K.Yokoyama, H.Nishi, S.Mori, M.Dairaku, T.Hoshino, M.Nakamichi, Y.Kawamura, Hiroyasu Tanigawa
- Journal Title
  
  Proceedings of 15th CBBI -Sapporo, 3-4, September, 2009-JAEA-Conf 2009-006 JAEA-Conf2009-006
  
  Pages: 29-42
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] 小特集核融合炉の除熱技術-実用から先進技術まで-2. 2ブランケットの伝熱流動2009
- Author(s)
  関洋治, 江里幸一郎, 榎枝幹男
- Journal Title
  
  プラズマ・核融合学会誌 85
  
  Pages: 543-547
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA2009
- Author(s)
  H. Tanigawa, T. Hoshino, Y. Kawamura, M. Nakamichi, K. Ochiai, M. Akiba, M.,o, M. Enoeda, K. Ezato, K. Hayashi, T. Hirose, C. Konno, H. Nakamura, T. Nozawa, H. Ogiwara, Y. Seki, H. Tanigawa, K. Tsuchiya, D. Tsuru, T. Yamanishi
- Journal Title
  
  Nuclear Fusion 49
  
  Pages: 55021-55021
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] 小特集核融合炉の除熱技術-実用から先進技術まで-2.2ブラシゲットの伝熱流動2009
- Author(s)
  関洋治、江里幸一郎、榎枝幹男
- Journal Title
  
  プラズマ・核融合学会誌 85
  
  Pages: 543-547
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] R&D of a Li_2TiO_3 pebble bed for a test blanket module in JAEA2009
- Author(s)
  H.Tanigawa, T.Hoshino, Y.Kawamura, M.Nakamichi, K.Ochiai, M.Akiba, M.Ando, M.Enoeda, K.Ezato, K.Hayashi, T.Hirose, C.Konno, H.Nakamura, T.Nozawa, H.Ogiwara, Y.Seki, H.Tanigawa, K.Tsuchiya, D.Tsuru, T.Yamanishi
- Journal Title
  
  Nuclear Fusion 49
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] Characteristics of tritium release behavior from solid breeder materials2008
- Author(s)
  T. Kinjyo, M. Nishikawa, N. Yamashita, T. Koyama, K. Suernatsu. S. Fukada, M. Enoeda
- Journal Title
  
  Fusion Science and Technology 54
  
  Pages: 557-13560
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] Tritium diffusivity in crystal grain of L_i2TiO_3 and tritium release behavior under several purge gas condition2008
- Author(s)
  T. Kinjo, M. Nishikawa, M. Enoeda, S. Fukada
- Journal Title
  
  Fusion Engineering and Design 83
  
  Pages: 583-587
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] Tritium diffusivity in crystal grain of Li2TiO3 and tritium release behavior under several purge gas condition2008
- Author(s)
  T. Kinjo, M. Nishikawa, M. Enoeda, S. Fukada
- Journal Title
  
  Fusion Engineering and Design 83
  
  Pages: 580-587
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] Characteristics of tritium release behavior from solid breeder materials2008
- Author(s)
  T. Kinjyo, M. Nishikawa, N. Yamashita, T. Koyama, K. Suematsu. S. Fukada, M. Enoeda
- Journal Title
  
  Fusion Science and Technology 54
  
  Pages: 557-560
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] 核熱解析による固体増殖水冷却方式テストブランケットモジュールのトリチウム増殖比に関する検討2007
- Author(s)
  関洋治, 谷川尚, 鶴大悟, 榎枝幹男, 秋場真人, 江里幸一郎, 丹澤貞光, 西宏, 廣瀬貴規, 本間隆, 毛利憲介, 横山堅二
- Journal Title
  
  JAEA-Technology
  
  Pages: 67-74
- Data Source
  KAKENHI-PLANNED-19055006
[Journal Article] Estimation of tritium release behavior from solid breeder materials under the condition of ITER test blanket module2007
- Author(s)
  T. Kinjyo, M. Nishikawa, M. Enoeda
- Journal Title
  
  Journal of Nuclear Materials 367-370
  
  Pages: 1361-1365
- Peer Reviewed
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Experimental study of helium purge flow in pebble bed for solid breeder2011
- Author(s)
  Y. Seki, S. Suzuki, M. Enoeda
- Organizer
  16th International Workshop on Ceramic Breeder Blanket Interactions
- Place of Presentation
  Portland
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] R&D of prediction system for tritium transport in pebble bed breeder blanket2011
- Author(s)
  Y. Seki, T. Hirose, H. Tanigawa, M. Enoeda
- Organizer
  Plasma Conference 2011
- Place of Presentation
  Kanazawa, Japan
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan2011
- 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.
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Progress of ITER Test Blanket Module Development in Japan2011
- 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
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Recent Status of R&D of Solid Breeder TBM and ITER Procurement in JAEA2009
- Author(s)
  M. Enoeda, D. Tsuru, H. Tanigawa, T. Hirose, S. Suzuki, K. Ezato, Y. Scki. K. Mobil. H. Nishi. M Akiba
- Organizer
  Korea-Japan Blanket Workshop
- Place of Presentation
  Seoul, Korea
- Year and Date
  2009-02-26
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Fabrication routes of sub-components for water cooled ceramic breeder blanket module2009
- Author(s)
  T.Hirose, H.Tanigawa, M.Enoeda, H.Serizawa, Y.Kawahito, S.Katayama
- Organizer
  固体増殖ブランケット相互作用国際ワークショップ(CBBI-15)
- Place of Presentation
  Sapporo, Japan
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Packing experiment of breeder pebbles into water cooled solid breeder test blanket module for ITER2009
- Author(s)
  T.Hirose, Y.Seki, D.Tsuru, H.Tanigawa, H.Tanigawa, M.Enoeda, H.Yamaoka (IHI)
- Organizer
  9th International Symposium on Fusion Nuclear Technology
- Place of Presentation
  Sapporo, Japan
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] ITER-TBM増殖機能部の研究開発の成果 ; (2)テストブランケットモジュールにおける増殖材充填体内ヘリウムパージガス流動の圧力損失評価2009
- Author(s)
  関洋治, 吉河朗, 廣瀬貴規, 谷川尚, 鶴大悟, 江里幸一郎, 横山堅二, 鈴木哲, 榎枝幹男
- Organizer
  日本原子力学会2009年秋の大会
- Place of Presentation
  仙台市
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] R&Ds on Li_2TiO_3 Pebble Bed for Test Blanket Module in JAEA2008
- Author(s)
  H. Tanigawa, T. Hoshino, Y. Kawamura, M. Nakamichi, K. Ochiai, M. Akiba, M. Ando, M. Enoeda, K. Ezato, K. Hayashi, T. Hirose, C. Konno, H. Nakamura, T. Nozawa, H. Ogiwara, Y. Seki, H. Tanigawa, K. Tsuchiya, D. Tsuru. T. Yamanishi
- Organizer
  22nd IAEA Fusion Energy Conference
- Place of Presentation
  Geneva, Switzerland
- Year and Date
  2008-10-15
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Preparation of Water Cooled Solid Breeder TBM for ITER Day-1 operation2008
- Author(s)
  M. Akiba, M. Enoeda, D. Tsuru, et.al.
- Organizer
  18Th Topical meeting on the technology of fusion energy
- Place of Presentation
  San Francisco, USA
- Year and Date
  2008-09-29
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Development of water-cooled solid breeder test blanket module in JAEA2008
- Author(s)
  M. Akiba, M. Enoeda, K. Ezato, et.al.
- Organizer
  25th Symposium on Fusion Technology
- Place of Presentation
  Rostock, Germany
- Year and Date
  2008-09-18
- Data Source
  KAKENHI-PLANNED-19055006
[Presentation] Research and development on Water-Cooled Solid Breeder Test Blanket Module in JAEA2007
- Author(s)
  Enoeda, M・Tanigawa, H・Tsuru, D・Ezato, K・Yokoyama, K・Dairaku, M・Seki, Y・Suzuki, S・Mohri, K・Nishi, H・Hirose, T・Tanigawa, H・Akiba, M
- Organizer
  The 16th Pacific Basin Nuclear Conference
- Place of Presentation
  Aomori
- Year and Date
  2007-10-15
- Data Source
  KAKENHI-PLANNED-19055006

1. FUKADA Satoshi (50117230)

# of Collaborated Projects: 1 results

# of Collaborated Products: 4 results
2. KAWAMURA Yoshinori (10354614)

# of Collaborated Projects: 1 results

# of Collaborated Products: 6 results
3. KATAYAMA Kazunari (90380708)

# of Collaborated Projects: 1 results

# of Collaborated Products: 1 results
4. NISHIKAWA Masabumi (90026229)

# of Collaborated Projects: 1 results

# of Collaborated Products: 5 results
5. SAGARA Akio (20187058)

# of Collaborated Projects: 1 results

# of Collaborated Products: 0 results
6. 宗像健三 (70264067)

# of Collaborated Projects: 1 results

# of Collaborated Products: 0 results

ENOEDA Mikio 榎枝 幹男

Research Projects

Research Products

Co-Researchers

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

Principal Investigator

Project Period (FY)

Research Category

Review Section

Research Institution

[Journal Article] Recent status of fabrication technology development of water cooled ceramic breeder test blanket module in Japan2011

Author(s)

Journal Title

Data Source

[Journal Article] Overview of the ITER TBM R&D activities in Japan2010

Author(s)

Journal Title

Data Source

[Journal Article] Status of the development of Water Cooled Ceramic Breeder (WCCB) Test Blanket Module2009

Author(s)

Journal Title

Data Source

[Journal Article] 小特集核融合炉の除熱技術-実用から先進技術まで-2. 2ブランケットの伝熱流動2009

Author(s)

Journal Title

Data Source

[Journal Article] R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA2009

Author(s)

Journal Title

Data Source

[Journal Article] 小特集核融合炉の除熱技術-実用から先進技術まで-2.2ブラシゲットの伝熱流動2009

Author(s)

Journal Title

Data Source

[Journal Article] R&D of a Li_2TiO_3 pebble bed for a test blanket module in JAEA2009

Author(s)

Journal Title

Data Source

[Journal Article] Characteristics of tritium release behavior from solid breeder materials2008

Author(s)

Journal Title

Data Source

[Journal Article] Tritium diffusivity in crystal grain of L_i2TiO_3 and tritium release behavior under several purge gas condition2008

Author(s)

Journal Title

Data Source

[Journal Article] Tritium diffusivity in crystal grain of Li2TiO3 and tritium release behavior under several purge gas condition2008

Author(s)

Journal Title

Data Source

[Journal Article] Characteristics of tritium release behavior from solid breeder materials2008

Author(s)

Journal Title

Data Source

[Journal Article] 核熱解析による固体増殖水冷却方式テストブランケットモジュールのトリチウム増殖比に関する検討2007

Author(s)

Journal Title

Data Source

[Journal Article] Estimation of tritium release behavior from solid breeder materials under the condition of ITER test blanket module2007

Author(s)

Journal Title

Data Source

[Presentation] Experimental study of helium purge flow in pebble bed for solid breeder2011

Author(s)

Organizer

Place of Presentation

Data Source

[Presentation] R&D of prediction system for tritium transport in pebble bed breeder blanket2011

Author(s)

Organizer

Place of Presentation

Data Source

[Presentation] Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan2011

Author(s)

Organizer

Place of Presentation

Data Source

[Presentation] Progress of ITER Test Blanket Module Development in Japan2011

Author(s)

Organizer

ENOEDA Mikio 榎枝幹男