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- SASAKI Kenta
- Department of Quantum Science and Energy Engineering, Tohoku University
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- NOGAMI Shuhei
- Department of Quantum Science and Energy Engineering, Tohoku University
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- FUKUDA Makoto
- Department of Quantum Science and Energy Engineering, Tohoku University
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- YABUUCHI Kiyohiro
- Department of Quantum Science and Energy Engineering, Tohoku University
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- HASEGAWA Akira
- Department of Quantum Science and Energy Engineering, Tohoku University
抄録
Tungsten is one of the candidate materials being considered for fabricating the plasma facing components (PFCs) of fusion reactors. When used in fusion reactors, PFCs are exposed to high heat loads from the fusion plasma, resulting in the PFCs being subjected to induced thermal stresses. This study focused on the creep deformation of pure tungsten under such a deformation-controlled thermal stress. Bend stress relaxation (BSR) tests were performed on specimens of as-received pure tungsten at temperatures of 600 - 1000◦C for 0.1 - 1 h in vacuum. The BSR ratio decreased with an increase in the temperature, decreasing sharply in a short period of 0.1 h and then decreasing gradually. Most of the stress was relieved during the BSR test performed at 1000◦C for 1 h. The activation energy of stress relaxation, calculated using the cross-cut method, was similar to that of the Peierls mechanism. This suggested that the mobility of the dislocations controls the stress relaxation mechanism. Most of the stress was relieved quickly because the activation energy of stress relaxation was relatively small.
収録刊行物
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- Plasma and Fusion Research
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Plasma and Fusion Research 8 (0), 1405006-1405006, 2013
一般社団法人 プラズマ・核融合学会
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詳細情報 詳細情報について
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- CRID
- 1390282680232645760
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- NII論文ID
- 130003366301
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- ISSN
- 18806821
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
- KAKEN
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- 抄録ライセンスフラグ
- 使用不可