A condensed review of nuclear reactor thermal-hydraulic computer codes for two-phase flow analysis
A review is made of the computer codes developed in the U.S. for thermal-hydraulic analysis of nuclear reactors. The intention of this review is to compare these codes on the basis of their numerical method and physical models with particular attention to the two-phase flow and heat transfer...
| Main Authors: | , |
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| Format: | Technical Report |
| Language: | en_US |
| Published: |
MIT Energy Laboratory
2006
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| Subjects: | |
| Online Access: | http://hdl.handle.net/1721.1/35164 |