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Radial-hydride Embrittlement of High-burnup Zircaloy-4 Fuel Cladding
Prestorage drying operations of high-burnup fuel may make Zircaloy-4 (Zry-4) fuel cladding more susceptible to failure, especially during fuel handling, transport, and post-storage retrieval. In particular, hydride precipitates may reorient from the circumferential to the radial direction of the cla...
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Published in: | Journal of nuclear science and technology 2006-09, Vol.43 (9), p.1054 |
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Main Authors: | , , , |
Format: | Article |
Language: | English |
Subjects: | |
Citations: | Items that cite this one |
Online Access: | Get full text |
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Summary: | Prestorage drying operations of high-burnup fuel may make Zircaloy-4 (Zry-4) fuel cladding more susceptible to failure, especially during fuel handling, transport, and post-storage retrieval. In particular, hydride precipitates may reorient from the circumferential to the radial direction of the cladding during drying operations if a threshold level of hoop stress at or above a corresponding threshold temperature is exceeded. This study indicates that the threshold stress is approximately 75-80 MPa for both nonirradiated and high-burnup stress-relieved Zry-4 fuel cladding cooled from 400[Degree]C and, under ring compression at both room temperature and 150[Degree]C, that radial-hydride precipitation embrittles Zry-4. Specifically, the plastic tensile hoop strain needed to initiate unstable crack propagation along radial hydrides decreases dramatically from >8% to 600 wppm), like that found in high-burnup Zry-4. |
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ISSN: | 0022-3131 1881-1248 |
DOI: | 10.3327/jnst.43.1054 |