Published June 1989
| Version v1
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Evaluation of forced reflooding experiments in APWR-geometry (NEPTUN-III facility) using the advanced computer code FLUT-FDWR
Description
A new version of the GRS computer code FLUT, named FLUT-FDWR, was recently developed in KfK in order to provide an adequate computational means for analysing the behaviour of the most important APWR designs during the reflooding phase after a LOCA. The Code was checked by means of post-test calculations of experiments in PWR as well as in a very tight APWR geometry. The present work shows the results of calculations for a wider APWR geometry (NEPTUN-III facility) and can be seen as a further step in the code validation for APWR applications. (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Eine neue Version des GRS-Rechenprogrammes FLUT, genannt FLUT-FDWR, wurde neuerdings in KfK entwickelt, um eine geeignete Rechenmethode zur Analyse der Flutphase nach einem Kuehlmittelverluststoerfall bei den wichtigsten FDWR-Entwuerfen verfuegbar zu machen. Das Programm wurde durch die Nachrechnung von Experimenten in DWR- und in einer sehr engen FDWR-Geometrie ueberprueft. Die Arbeit zeigt die Ergebnisse von Rechnungen, die fuer eine weitere FDWR-Geometrie (NEPTUN-III Anlage) durchgefuehrt wurden, und stellt einen weiteren Schritt der Validierung des Programms fuer FDWR-Anwendungen dar. (orig.)
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Additional details
Publishing Information
- Imprint Pagination
- 35 p.
- Report number
- KFK--4585
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 20085837
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ATWS; COMPUTER CALCULATIONS; CORE FLOODING SYSTEMS; HCLWR TYPE REACTORS; HYDRAULICS; LOSS OF COOLANT; POWER DISTRIBUTION; PWR TYPE REACTORS; THERMODYNAMICS; VERIFICATION
- Descriptors DEC
- ACCIDENTS; DESIGN BASIS ACCIDENTS; DISTRIBUTION; ECCS; ENRICHED URANIUM REACTORS; PLUTONIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS