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The T-containment properties of a Zr-containing Li rod in a high-temperature gas-cooled reactor as a T production device for fusion reactors
https://repo.qst.go.jp/records/84327
https://repo.qst.go.jp/records/843277b017de5-f101-4079-b54d-c0ded3feeec2
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2021-09-29 | |||||
| タイトル | ||||||
| タイトル | The T-containment properties of a Zr-containing Li rod in a high-temperature gas-cooled reactor as a T production device for fusion reactors | |||||
| 言語 | ||||||
| 言語 | eng | |||||
| 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 | journal article | |||||
| アクセス権 | ||||||
| アクセス権 | metadata only access | |||||
| アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
| 著者 |
Matsuura, Hideaki
× Matsuura, Hideaki× Suganuma, Takuro× Koga, Yuki× Naoi, Motomasa× Katayama, Kazunari× Otsuka, Teppei× Goto, Minoru× Nakagawa, Shigeaki× Hamamoto, Shinpei× Ishitsuka, Etsuo× Kenji, Tobita× Satoshi, Konishi× Ryoji, Hiwatari× Yoji, Someya× Yoshiteru, Sakamoto× Matsuura, Hideaki× Katayama, Kazunari× Otsuka, Teppei× Goto, Minoru× Nakagawa, Shigeaki× Hamamoto, Shinpei× Ishitsuka, Etsuo× Kenji, Tobita× Satoshi, Konishi× Ryoji, Hiwatari× Yoji, Someya× Yoshiteru, Sakamoto |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The production of tritium (T) using high-temperature gas-cooled reactors (HTGRs) has been studied for a prior engineering research with T handling and initial T possession in demonstration fusion reactors. Stable containment of T in Li-loading rods during HTGR operation is a critical issue. This study investigates this for an irradiation test to examine T-containment performance in Li-loading rods and develops an analytical model of evaluating the amount of T outflow to a He coolant. The hydrogen absorption characteristics, including the deterioration of the hydrogen absorption speed after Zr has sufficiently absorbed the hydrogen, is experimentally measured assuming an HTGR setting. We present an analytical model of evaluating the T outflow from a Li rod and, on the basis of this model, estimate the total T outflow, assuming the presence of a gas-turbine high-temperature reactor of 300 MWe with a nominal capacity and a high-temperature engineering test reactor. It is demonstrated that, by loading a sufficient amount of Zr into the Li rod, the T outflow can be suppressed to less than a small percent of the total T produced during 360 days of reactor operation. | |||||
| 書誌情報 |
Fusion Engineering and Design 巻 169, p. 112441, 発行日 2021-08 |
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| 出版者 | ||||||
| 出版者 | Elsevier | |||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 0920-3796 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1016/j.fusengdes.2021.112441 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | https://www.sciencedirect.com/science/article/pii/S0920379621002179 | |||||
