POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION
The knowledge of heat transfer coefficient in the post critical heat flux region in nuclear reactor safety is very important. Although the nuclear reactors normally operate at conditions where critical heat flux (CHF) is not reached, accidents where dryout occur are possible. Most serious postulated...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
CTU Central Library
2016-12-01
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| Series: | Acta Polytechnica CTU Proceedings |
| Online Access: | https://ojs.cvut.cz/ojs/index.php/APP/article/view/3723 |