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Zr-V-Fe合金による実験室規模でのトリチウムガスの供給と回収
https://doi.org/10.15099/00006345
https://doi.org/10.15099/000063459bbe1e56-24b8-4ec8-85c8-a754c1b04596
名前 / ファイル | ライセンス | アクション |
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annual_report6-3.pdf (626.8 kB)
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Item type | 紀要論文 / Departmental Bulletin Paper(1) | |||||
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公開日 | 2007-10-03 | |||||
タイトル | ||||||
タイトル | Zr-V-Fe合金による実験室規模でのトリチウムガスの供給と回収 | |||||
言語 | ||||||
言語 | jpn | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | departmental bulletin paper | |||||
ID登録 | ||||||
ID登録 | 10.15099/00006345 | |||||
ID登録タイプ | JaLC | |||||
著者 |
松山, 政夫
× 松山, 政夫× 三宅, 均× 市村, 憲司× 芦田, 完× 渡辺, 国昭 |
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著者別名 | ||||||
姓名 | Matsuyama, Masao | |||||
著者別名 | ||||||
姓名 | Miyake, Hitoshi | |||||
著者別名 | ||||||
姓名 | Ichimura, Kenji | |||||
著者別名 | ||||||
姓名 | Ashida, Kan | |||||
著者別名 | ||||||
姓名 | Watanabe, Kuniaki | |||||
その他(別言語等)のタイトル | ||||||
その他のタイトル | Supply and Recovery of Tritium Gas by Zr-V-Fe alloy for Laboratory Experiments | |||||
抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | Supply and recovery techniques of tritium gas (T2) on a laboratory scale is important for experimental studies using a large amount of tritium gas. From this view point, we examined the potential of the Zr-V-Fe alloy as material for the supply and recovery of tritium gas. The amount of tritium gas used was 5 Ci in each run, and that of the alloy used was 47mg. It was revealed that the alloy was excellent for purifying tritium gas containing such impurities as 3He, tritiated water and methane: the gas released by heating from the alloy consisted of T2 (85%), HT (15%) and trace amounts of water and hydrocarbons. The pressure (P) of tritium gas released from the alloy obeyed the following equation, Log P=2.7+log q2-6300/T, where q and T denote the amount of absorption and temperature, respectively. This equation agree with that obtained by using ultra-high vacuum systems. It indicates that the alloy is applicable to recover tritium gas from even conventional vacuum systems that not so good. An absorption-desorption cycle of over 40 times confirmed the durability of the alloy against residual gases mainly consisting of water and carbon monoxide. These results indicate that the Zr-V-Fe alloy is excellent for the purification, recovery, storage, and supply of tritium gas in conventional vacuum systems. | |||||
書誌情報 |
富山大学トリチウム科学センター研究報告 = Annual Report of Tritium Research Center, Toyama University 巻 6, p. 39-46, 発行日 1986 |
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ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0287-1408 | |||||
書誌レコードID | ||||||
収録物識別子タイプ | NCID | |||||
収録物識別子 | AN10100133 | |||||
フォーマット | ||||||
内容記述タイプ | Other | |||||
内容記述 | application/pdf | |||||
著者版フラグ | ||||||
出版タイプ | VoR | |||||
出版タイプResource | http://purl.org/coar/version/c_970fb48d4fbd8a85 | |||||
出版者 | ||||||
出版者 | 富山大学トリチウム科学センター | |||||
資源タイプ(DSpace) | ||||||
内容記述タイプ | Other | |||||
内容記述 | Article |