Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT)
SUBCHANFLOW is a computer code to analyze thermal-hydraulic phenomena in the core of pressurized water reactors, boiling water reactors, and innovative reactors operated with gas or liquid metal as coolant. As part of the ongoing assessment efforts, the code has been validated by using experimental...
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| Principais autores: | , |
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| Format: | Artigo |
| Sprog: | Inglês |
| Udgivet: |
Wiley
2012-01-01
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| Serier: | Science and Technology of Nuclear Installations |
| Online adgang: | http://dx.doi.org/10.1155/2012/465059 |
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