THERMOHYDRAULISCHE UNTERSUCHUNGEN ZU DEN VORGAENGEN WAEHREND DER FLUTPHASE NACH EINEM KUEHLMITTELVERLUST BEI EINEM FORTGESCHRITTENEN DRUCKWASSERREAKTOR
The aim of this work is to analyse the behaviour of some different Advanced Pressurized Water Reactor (APWR) rd designs during the reflooding phase following a large break (double ended) loss of coolant accident (LOCA). The FLUT code and its most important physical models and correlations will be shortly discussed. The major changes will be described addressing the reasons for their introduction. Special attention is given to the description of a newly developed droplet-model, which allows a better modelling of the progression of the quench front. In order to assess the updated correlations and models, many forced reflooding experiments were evaluated. The results of these posttest calculations will be shown. The calculations for two APWR designs will then be compared with that for the reference PWR pointing out the most important differences.
Bibliographic Reference: FOR FULL-SIZE VERSION WRITE TO KERNFORSCHUNGSZENTRUM KARLSRUHE GMBH, POSTFACH 3640, 7500 KARLSRUHE 1, MENTIONING KFK 4302; FOR MICROFICHE WRITE TO , EUROFFICE, LUXEMBOURG, POB 1003 MENTIONING EUR 10538DE(1987), 154 P., BFR 300
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Record Number: 1989126027001 / Last updated on: 1989-01-01
Available languages: de