Blowdown heat transfer phenomena in the scaled BWR test system
Giovanna Sozzi, R. J. MUZZY, G.W. Burnette
Abstract
Giovanna Sozzi, R. J. MUZZY, G.W. Burnette
Abstract
Experimental results from the Boiling Water Reactor (BWR) blowdown heat transfer program (BDHT), obtained in the BWR scaled-test apparatus, are used to provide a basis for evaluating BDHT phenomena. BWR loss-of-coolant accident (LOCA) analysis using the current BWR LOCA evaluation method, when applied to the test apparatus, shows a substantial margin in the prediction of peak cladding temperature. Observed thermal-hydraulic and heat transfer phenomena are evaluated and compared with the current method. Specific phenomenologically based model refinements are recommended for break flow, void distribution, and heat transfer.
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Experimental results from the Boiling Water Reactor (BWR) blowdown heat transfer program (BDHT), obtained in the BWR scaled-test apparatus, are used to provide a basis for evaluating BDHT phenomena. BWR loss-of-coolant accident (LOCA) analysis using the current BWR LOCA evaluation method, when applied to the test apparatus, shows a substantial margin in the prediction of peak cladding temperature. Observed thermal-hydraulic and heat transfer phenomena are evaluated and compared with the current method. Specific phenomenologically based model refinements are recommended for break flow, void distribution, and heat transfer.
Key concepts: Boiler blowdown, Boiling water reactor, Nuclear engineering, Heat transfer, Cladding (metalworking), Thermal hydraulics, Boiling, Scram