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Content Provider | The American Society of Mechanical Engineers (ASME) Digital Collection |
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Author | Chopra, O. K. Gruber, E. E. Alexandreanu, B. Chen, Y. Shack, W. J. |
Copyright Year | 2007 |
Abstract | Crack growth rate (CGR) data have been obtained in boiling water reactor environments on several grades of austenitic stainless steels, including weld heat-affected-zone and cast materials, that were irradiated up to 2.0 × 1021 n/cm2 (E > 1 MeV) (≈3 dpa). Crack growth tests were conducted on 1/4-T compact tension specimens subjected to either a sawtooth waveform with load ratios up to 0.7 and rise times up to 1000 s, or a constant load with or without periodic partial unloading. The results indicate significant enhancement of crack growth rates in the irradiated steels. The results are compared with data obtained from other studies. The existing CGR data are also reviewed to evaluate the effects of material composition, irradiation, and water chemistry on the CGRs in austenitic SSs. The significance of specimen size criteria is discussed. |
Sponsorship | Pressure Vessels and Piping Division |
Starting Page | 253 |
Ending Page | 268 |
Page Count | 16 |
File Format | |
ISBN | 0791842797 |
DOI | 10.1115/PVP2007-26659 |
e-ISBN | 0791838048 |
Volume Number | Volume 1: Codes and Standards |
Conference Proceedings | ASME 2007 Pressure Vessels and Piping Conference |
Language | English |
Publisher Date | 2007-07-22 |
Publisher Place | San Antonio, Texas, USA |
Access Restriction | Subscribed |
Subject Keyword | Heat Water chemistry Stainless steel Irradiation (radiation exposure) Tension Fracture (materials) Boiling water reactors Steel Stress |
Content Type | Text |
Resource Type | Article |
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