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- HIROHATA Yuko
- Department of Nuclear Engineering, Hokkaido University
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- MOTOJIMA Dai
- Department of Nuclear Engineering, Hokkaido University
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- YAMAUCHI Yuji
- Department of Nuclear Engineering, Hokkaido University
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- HINO Tomoaki
- Department of Nuclear Engineering, Hokkaido University
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- MUROGA Takeo
- National Institute for Fusion Science
書誌事項
- タイトル別名
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- Deuterium Retention of Vanadium Alloy, V-4Cr-4Ti
- ソクホウ Deuterium Retention of Vanadium Alloy V 4Cr 4Ti
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説明
The deuterium retention property of vanadium alloy, V-4Cr-4Ti which is a candidate material for blanket in a fusion reactor was investigated by deuterium ion irradiation and gas desorption measurement after irradiation using thermal desorption spectroscopy (TDS). The deuterium ion irradiation to the vanadium alloy sample was carried out at the temperatures of 380 and 773 K and at ion energy of 1.7 keV. Deuterium retained in the sample desorbed in the forms of D2, HD, HDO and D2O during heating up to 1273 K in a TDS apparatus. The retained amount of deuterium in the sample after deuterium ion irradiation at 380 K linearly increased with the fluence of deuterium ion, and did not saturate to the fluence up to 7×1018 D /cm2, and was 100% of implanted D which was one order or two orders of magnitude larger than those of graphite and tungsten, respectively. At the irradiation temperature of 773 K and the fluence up to 8 × 1018 D/cm2, the retention of deuterium in the sample has small dependence against the ion fluence and was approximately 8% of implanted D.
収録刊行物
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- 真空
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真空 46 (10), 756-759, 2003
一般社団法人 日本真空学会
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詳細情報 詳細情報について
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- CRID
- 1390282679040087296
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- NII論文ID
- 10012426330
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- NII書誌ID
- AN00119871
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- ISSN
- 18809413
- 05598516
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- NDL書誌ID
- 6747801
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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
- NDLサーチ
- Crossref
- CiNii Articles
- OpenAIRE
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- 抄録ライセンスフラグ
- 使用不可