Abstract
Corrosion fatigue crack growth rate of Soviet reactor pressure vessel steel 15X2M∅A and its cladding were studied in simulated PWR-conditions. The crack growth rate was highest in the cladding and lowest near the fusion line. No delamination or crack branching along the fusion line was found. In all cases, the ASME Code Section IX reference curves were conservative for the materials studied.
| Original language | English |
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| Title of host publication | Structural Mechanics in Reactor Technology |
| Subtitle of host publication | transactions of the 10th International Conference |
| Editors | Asadour H. Hadjian |
| Place of Publication | Los Angeles |
| Publisher | American Association for Structural Mechanics in Reactor Technology (AASMiRT) |
| Pages | 135-139 |
| ISBN (Print) | 978-0-9623306-0-5 |
| Publication status | Published - 1989 |
| MoE publication type | A4 Article in a conference publication |
| Event | 10th International Conference on Structural Mechanics in Reactor Technology - Anaheim, United States Duration: 14 Aug 1989 → 18 Aug 1989 |
Conference
| Conference | 10th International Conference on Structural Mechanics in Reactor Technology |
|---|---|
| Country/Territory | United States |
| City | Anaheim |
| Period | 14/08/89 → 18/08/89 |