| タイトル | Tritium permeation evaluation through vertical target of divertor based on recent tritium transport properties |
| その他のタイトル | トリチウム輸送物性値の新知見に基づくダイバータ垂直ターゲットからのトリチウム透過評価 |
| DOI | 10.11484/jaeri-research-2003-024 |
| 本文（外部サイト） | http://jolissrch-inter.tokai-sc.jaea.go.jp/pdfdata/JAERI-Research-2003-024.pdf |
| 参考URL | http://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?25188 |
| 著者（日） | 中村 博文; 西 正孝 |
| 発行日 | 2003-11 |
| 発行機関など | JAEA |
| 刊行物名 | JAERI-Research 2003-024 |
| 開始ページ | 1 |
| 終了ページ | 24 |
| 刊行年月日 | 2003-11 |
| 言語 | en |
| 内容記述 | Re-evaluation of tritium permeation through vertical target of divertor under the ITER operation condition was carried out using tritium transport properties in the candidate materials such as the diffusion coefficient and the trapping factors in tungsten for armor, and the surface recombination coefficient on copper for the heat sink obtained by authors' recent investigation (authors' data), which simulated the plasma-facing conditions of ITER. Evaluation with the data set of previous evaluation was also carried out for comparison (previous data). The permeation analysis was carried out individually by classifying into the armor region (Carbon Fiber Composites and tungsten) and the slit region without armor (3% of armor surface area) assuming the incident flux and temperature for each region. As the results of the permeation analysis, estimated permeation amount with the authors' data was one order less than that with the previous data at the end of lifetime of the divertor due to authors' small diffusion coefficient of tritium in tungsten. It also indicated the possibility that permeation through the slit region of the armor tiles could dominate total permeation through the vertical target, since tritium permeation amount through tungsten armor with the authors' data was estimated to be reduced drastically smaller than that with the previous evaluation data. The result of a little tritium permeation amount through the vertical target with the authors' data ensured the conservatism of the current evaluation of tritium concentration in the primary cooling water in ITER divertor, as it indicated the possibility of direct drainage of the divertor primary cooling water.
著者所属: 日本原子力研究開発機構(JAEA) |
| 資料種別 | Technical Report |
| URI | https://repository.exst.jaxa.jp/dspace/handle/a-is/617311 |
