The effect of axial fuel rod power profile on fuel temperature and cladding strain
The most limiting design criteria for nuclear reactor normal operating conditions (ANS Condition I) are known to be rod internal pressure and cladding oxidation, while those for nuclear reactor transient operating conditions (ANS Conditon II) to be fuel centerline temperature and transient cladd...
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| Format: | Article |
| Language: | English |
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VINCA Institute of Nuclear Sciences
2010-01-01
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| Series: | Nuclear Technology and Radiation Protection |
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| Online Access: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2010/1451-39941002114K.pdf |