Predictions of critical heat flux using the ASSERT-PV subchannel code for a CANFLEX variant bundle /

Eitemau Tebyg

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• Comparison of dryout power data between canflex MK-V and canflex MK-IV bundle strings in uncrept and crept channels /
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• An experimental study on post-chf heat transfer for low flow of water in a 3x3 rod bundle /
• Assertiveness : practical approach /
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  Cyhoeddwyd: (1990)
• Thermalhydraulic evaluations for a canflex bundle with natural or recycled uranium fuel in the uncrept and crept channels of a candu-6 reactor /
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