Published 1981 | Version v1
Book Metadata-only

Precalculation of a FLECHT experiment using the FLUT program

Creators

  • 1. Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)

Description

The FLUT program has been developed for simulation of the fluid dynamics in a PWR primary loop during the refill and flooding phase of LOCA. The development work is done by GRS on behalf of the Federal Minister for Research and Technology. An initial working version of the program has been used for precalculation of two FLECHT experiments. (orig./GL)

Abstract (German)

Das Rechenprogramm FLUT wird zur Simulation der Fluiddynamik im Primaerkreis eines DWR waehrend der Wiederauffuell- und Flutphase des Kuehlmittelverluststoerfalles entwickelt. Diese Entwicklung wird von der GRS im Auftrag des BMFT durchgefuehrt. Nach Fertigstellung einer ersten Arbeitsversion wurde das Programm zur Vorausrechnung von zwei FLECHT-Experimenten eingesetzt. (orig./GL)

Additional details

Additional titles

Original title (German)
Vorausrechnung eines FLECHT-Experiments mit dem Rechenprogramm FLUT

Publishing Information

Publisher
Fachinformationszentrum Energie, Physik, Mathematik.
Imprint Place
Eggenstein-Leopoldshafen, Germany, F.R.
Imprint Title
Annual meeting on nuclear technology '81 - Reactor conference 1981
Imprint Pagination
668 p.
Journal Page Range
p. 69-72.

Conference

Title
Annual meeting on nuclear technology '81 (JK '81).
Dates
24 - 26 Mar 1981.
Place
Duesseldorf, Germany, F.R.

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
12596555
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; F CODES; FUEL CANS; HEAT TRANSFER; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SIMULATION; TEMPERATURE DEPENDENCE; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; FLUID FLOW; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:ISSN 0173-0924.;Jahrestagung Kerntechnik '81 - Reaktortagung 1981.;Tagungsbericht. Sektion 2: Thermo- und Fluiddynamik.