| タイトル | Friction coefficient measurementsn and analysis of local stress/strain in Zircaloy-2 cladding |
| その他のタイトル | None |
| DOI | |
| 本文（外部サイト） | http://jolissrch-inter.tokai-sc.jaea.go.jp/pdfdata/PNC-TN841-79-37.pdf |
| 参考URL | http://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?4021811 |
| 著者（日） | 立花 利道; 中江 延男; 金子 洋光; 本田 裕 |
| 発行日 | 1979-06 |
| 発行機関など | JAEA |
| 刊行物名 | PNC-TN841 79-37 |
| 開始ページ | 1 |
| 終了ページ | 21 |
| 刊行年月日 | 1979-06 |
| 言語 | en |
| 内容記述 | In the present study, the friction coefficient between UO2 pellet and Zry-2 cladding was successfully measured by out-of-pile experiments. The friction coefficient under a condition of hard contact was about 0.5 at temperature region of 300-400 circC celsius. Using the results, calculation was performed to obtain the local stress/strain distributions in Zry- 2 cladding when a radially cracked pellet expanded out wardly after contact with the cladding. The calculation was carried out by finite element code in which a system of friction between pellet and cladding was introduced. Local strain concentrations appeared not only at the position just facing pellet's crack but also at the position apart from the cracks when the friction coefficient became larger than 1.0. From the analysis it was concluded that keeping the friction coefficient below 0.5 in fuel rod must be one of measures which prevent PCI-induced SCC failure.
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/619176 |
