Published November 1983 | Version v1
Journal article Metadata-only

GERDA test facility for pressurized water reactors with straight tube steam generators

Creators

  • 1. Brown Boveri Reaktor G.m.b.H., Mannheim (Germany, F.R.)
  • 2. Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.)

Description

A number of large-scale experimental facilities have been constructed and operate in order to experiment on the thermodynamic and thermohydraulic behaviour of nuclear facilities in case of LOCA. Most of them were designed for ''large leak'' accidents, but as ''small leak'' accidents became the focus of interest, such experiments were also carried out. Experiments carried out with this arrangement for PWR-type reactors with straight-tube steam generators are only partially evaluable. BBR and B and W therefore cooperated in the construction of the test facility GERDA, designed for testing reactors of BBR design. It supplied relevant experimental results for the nuclear power plant at Muelheim-Kaerlich. (orig.)

Abstract (German)

Eine Reihe grosser Versuchsanlagen wurden fuer Experimente zum thermodynamischen und thermohydraulischen Verhalten von Reaktoranlagen bei Kuehlmittelverluststoerfaellen errichtet und betrieben. Sie waren ueberwiegend fuer den Stoerfall ''Grosses Leck'' konzipiert worden dienten jedoch spaeter, als sich das Interesse staerker dem Stoerfall ''Kleines Leck'' zuwandte, auch Versuchen zu diesem Fragenkreis. Fuer Durckwasserreaktoren mit Geradrohrdampferzeugern waren Versuche mit diesen Anlagen allerdings nur bedingt aussagefaehig. Daher errichteten BBR und B und W gemeinsam die Versuchsanlage GERDA, die den Anforderungen des BBR-Typs entspricht und z.B. fuer das Kernkraftwerk Muelheim-Kaerlich relevante Versuchsergebnisse liefern konnte. (orig.)

Additional details

Additional titles

Original title (German)
Versuchsanlage GERDA fuer DWR mit Geradrohrdampferzeuger

Publishing Information

Journal Title
Atomwirtsch., Atomtech.
Journal Volume
28
Journal Issue
11
Series
CODEN: AWAKA.;Atomwirtsch., Atomtech.
Journal Page Range
564-568
ISSN
0365-8414

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
15034037
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
DATA PROCESSING; FLOW RATE; INFORMATION; LEAKS; LOSS OF COOLANT; MEASURING METHODS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RESEARCH PROGRAMS; SIMULATION; STEAM GENERATORS
Descriptors DEC
ACCIDENTS; BOILERS; COOLING SYSTEMS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS