Improvement of tungsten lifetime by coating with middle melting point materials
| Project/Area Number |
26630473
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| Research Category |
Grant-in-Aid for Challenging Exploratory Research
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| Allocation Type | Multi-year Fund |
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| Research Field |
Nuclear fusion studies
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| Research Institution | Osaka University |
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Principal Investigator |
Ueda Yoshio 大阪大学, 工学(系)研究科(研究院), 教授 (30193816)
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| Project Period (FY) |
2014-04-01 – 2016-03-31
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| Project Status |
Completed (Fiscal Year 2015)
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| Budget Amount *help |
¥3,510,000 (Direct Cost: ¥2,700,000、Indirect Cost: ¥810,000)
Fiscal Year 2015: ¥1,430,000 (Direct Cost: ¥1,100,000、Indirect Cost: ¥330,000)
Fiscal Year 2014: ¥2,080,000 (Direct Cost: ¥1,600,000、Indirect Cost: ¥480,000)
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| Keywords | プラズマ対向材料 / タングステン / 中間融点堆積膜 / 蒸気遮蔽効果 / 保護層 / ディスラプション / 壁材料保護 |
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| Outline of Final Research Achievements |
The following results were obtained. (1)Various W materials (pure W, W-2Ta, W-Re) were melted by a pulsed laser with ELM like heat pulses and their melt layer dynamics were studied. It was found that the least droplet ejection by bumping was observed for pure W. (2)W with thin Al coating layers (1 micrometer) was exposed to laser heat pulses and pulsed plasmas. Significant reduction of heat flux to W by evaporation heat of Al and vapor shielding effects by Al vapor was observed. (3)The vapor shielding effects of Be and W were successfully simulated by a newly developed PIC code. (4)W monoblocks for ITER with surface damage (cracking, melting made by pulsed plasmas and electron beam) were tested by cyclic high heat loading by electron beam. Heat flux of 20 MW/m^2 for 10 s was repeatedly applied for simulating slow transient heat pulsed in ITER. It was found that the W monoblocks with surface damage easily showed longitudinal cracks (self castellation).
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Report
(3 results)
Research Products
(16 results)
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[Journal Article] Surface modifications on toughened, fine-grained, recrystallized tungsten with repetitive ELM-like pulsed plasma irradiation2016
Author(s)
Kikuchi, Y., Sakuma, I., Kitagawa, Y., Asai, Y., Onishi, K., Fukumoto, N., Nagata, M., Ueda, Y., Kurishita, H.
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Journal Title
Journal of Nuclear Materials
Volume: 463
Pages: 206-209
DOI
Related Report
Peer Reviewed
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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
Related Report
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[Journal Article] Deuterium retention in various toughened, fine-grained recrystallized tungsten materials under different irradiation conditions2014
Author(s)
M Oya, H T Lee, Y Ohtsuka, Y Ueda, H Kurishita, M Oyaidzu and T Yamanishi
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Journal Title
M Oya, H T Lee, Y Ohtsuka, Y Ueda, H Kurishita, M Oyaidzu and T Yamanishi
Volume: T159
Related Report
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[Journal Article] Surface erosion and modification of toughened, fine-grained, recrystallized tungsten exposed to TEXTOR edge plasma2014
Author(s)
Y Ueda, M Oya, Y Hamaji, H T Lee, H Kurishita, Y Torikai, N Yoshida, A Kreter, J W Coenen, A Litnovsky and V Philipps
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Journal Title
Physica Scripta
Volume: T159
Related Report
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[Presentation] 日米協力PHENIX計画の概要と初年度の成果2014
Author(s)
上田良夫,波多野雄治,横峯健彦,檜木達也,長谷川晃,大矢恭久,Pete Pappano, Lance Snead, Richard Nygren, 加藤雄大, Brad Merrill,Dean Buchenauer
Organizer
第10回核融合エネルギー連合講演会
Place of Presentation
つくば国際会議場（茨城県）
Year and Date
2014-06-20
Related Report
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