Advanced Course in Heat Transfer in Nuclear Reactor Safety
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
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.