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Advanced Course in Heat Transfer in Nuclear Reactor Safety
September, 1-5, 1980, Dubrovnik, Yugoslavia

DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf


ISBN Print: 978-0-89116-223-0

3.3 Transient Critical Heat Flux Investigations

pages 511-522
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.290
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RESUMO

An experimental investigation is presented for power and flow transients and test results are extensively compared to transient computer code predictions. For dryout prediction, the instantaneous local-condition approximation was used and a good agreement can be observed between measured and calculated data, at the nominal operating parameters of a WWER-type reactor.

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