Estimation of tritium accumulation in tungsten and its application for ITER divertor
| Project/Area Number |
24360380
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| Research Category |
Grant-in-Aid for Scientific Research (B)
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| Allocation Type | Partial Multi-year Fund |
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| Section | 一般 |
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| Research Field |
Nuclear fusion studies
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| Research Institution | University of Toyama |
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Principal Investigator |
TORIKAI Yuji 富山大学, 水素同位体科学研究センター, 准教授 (80313592)
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| Co-Investigator(Kenkyū-buntansha) |
KURISHITA Hiroaki 東北大学, 金属材料研究所, 准教授 (50112298)
ISOBE Kanetsugu 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 研究主幹 (00354613)
OYAIZU Makoto 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 任期付研究員 (60516855)
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| Project Period (FY) |
2012-04-01 – 2015-03-31
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| Project Status |
Completed (Fiscal Year 2014)
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| Budget Amount *help |
¥18,590,000 (Direct Cost: ¥14,300,000、Indirect Cost: ¥4,290,000)
Fiscal Year 2014: ¥3,380,000 (Direct Cost: ¥2,600,000、Indirect Cost: ¥780,000)
Fiscal Year 2013: ¥5,460,000 (Direct Cost: ¥4,200,000、Indirect Cost: ¥1,260,000)
Fiscal Year 2012: ¥9,750,000 (Direct Cost: ¥7,500,000、Indirect Cost: ¥2,250,000)
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| Keywords | プラズマ・壁相互作用 / タングステン / トリチウム蓄積 / ITER |
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| Outline of Final Research Achievements |
Tungsten(W) is currently contemplated as plasma facing material because of its advantageous thermo physical properties and rather low solubility of tritium. Tritium solubility of W estimated in this study is 3 order higher than that reported by literature. Traps or oxide films may affect the retention capability of W and lead significantly modified release properties. It became clear that there were capture sites that had different thermal stability and capture intensity in W after polishing, or oxide films that were grown on the surface of W and had barrier effects. Detailed investigation of the impact of possibly rather diverse traps produced either during manufacturing-or via radiation-induced processes and oxide films after annealing on the uptake and retention properties of hydrogen isotopes retained by W used in first wall components of fusion machines is therefore necessary in order to assess correctly and minimize the tritium inventory during various phases of operation.
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Report
(4 results)
Research Products
(20 results)
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[Journal Article] Tritium Trapping on the Plasma Irradiated Tungsten Surface2015
Author(s)
Y. Torikai, V. Kh. Alimov, K. Isobe, M. Oyaidzu, T. Yamanishi, R.-D. Penzhorn, Y. Ueda, H. Kurishita, V. Philipps, A. Kreter, M. Zlobinski, and TEXTOR Team
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Journal Title
Fusion Sci. and Technol.
Volume: 67
Pages: 619-622
Related Report
Peer Reviewed / Acknowledgement Compliant
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[Journal Article] Current Status of Nanostructured Tungsten-Based Materials Development2014
Author(s)
H. Kurishita, S. Matsuo, H. Arakawa, T. Sakamoto, S. Kobayashi, K. Nakai, H. Okano, H. Watanabe, N. Yoshida, Y. Torikai, Y. Hatano, T. Takida, M. Kato, A. Ikegaya, Y. Ueda, M. Hatakeyama, T. Shikama
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Journal Title
Phys. Scr.
Volume: T159
Pages: 14032-14039
Related Report
Peer Reviewed / Acknowledgement Compliant
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[Journal Article] Current status of nanostructured tungsten-based materials development2014
Author(s)
H. Kurishita, S. Matsuo, H. Arakawa, T. Sakamoto, S. Kobayashi, K. Nakai, H. Okano, H. Watanabe, N. Yoshida, Y. Torikai, Y. Hatano, T. Takida, M. Kato, A. Ikegaya, Y. Ueda, M. Hatakeyama and T. Shikama
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Journal Title
Physica Scripta
Volume: T159
Pages: 14032-14032
DOI
Related Report
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[Journal Article] Tritium loading study of tungsten pre-exposed to TEXTOR plasmas
Author(s)
Y. Torikai, A. Taguchi, M. Saito, R. D. Penzhorn, Y. Ueda, H. Kurishita, K. Sugiyama, V. Philipps, A. Kreter, M. Zlobinski, TEXTOR team
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Journal Title
Journal of Nuclear Materials
Volume: (in press)
Related Report
Peer Reviewed
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[Journal Article] Deuteriunm retention in Toughened, Fine-Grained Recrystallized Tungsten
Author(s)
M. Oya, K. Uekita, H.T. Lee, Y. Ohtsuka, Y. Ueda, H. Kurishita, A. Kreter, J.W. Coenen, V. Philipps, S. Brezinsek, A. Litnovsky, K. Sugiyama, Y. Torikai
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Journal Title
Journal of Nuclear Materials
Volume: (in press)
Related Report
Peer Reviewed
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[Presentation] TRITIUM TRAPPING ON THE PLASMA IRRADIATED TUNGSTEN SURFACE2013
Author(s)
Y. Torikai, V.Kh. Alimov, K. Isobe, M. Oyaidzu, T. Yamanishi, R.-D. Penzhorn, Y. Ueda, H. Kurishita, V. Philipps, A. Kreter, M. Zlobinski, and TEXTOR Team
Organizer
10th International Conference on Tritium Science and Technology
Place of Presentation
Nice Acropolis France
Related Report
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[Presentation] Current status of nanostructured tungsten-based materials development2013
Author(s)
H. Kurishita, S. Matsuo, H. Arakawa, T. Sakamoto, S. Kobayashi, K. Nakai, H. Okano, H. Watanabe, N. Yoshida, Y. Torikai, Y. Hatano, T. Takida, M. Kato, A. Ikegaya, Y. Ueda, M. Hatakeyama and T. Shikama
Organizer
14th International Conference on Plasma-Facing Materials and Components for Fusion Applications
Place of Presentation
Forschungszentrum Juelich, Germany
Related Report
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