Published February 1993 | Version v1
Journal article Metadata-only

Assessment of the code RELAP5/MOD2 against loss of feedwater without scram

Creators

  • 1. Union Fenosa, Madrid (Spain)

Description

The integral effect test L9-3 (loss of feedwater without reactor trip) performed at the LOFT facility was analyzed as part of an assessment of the RELAP5/MOD2 code with the aim of qualifying this simulation tool for analysis of pressurization transients in pressurized water reactors. The code proved suitable for analysis of this kind of transients. Some conclusions of relevance to simulation of anticipated transients without scram scenarios with forced circulation could be drawn. (orig.)

Abstract (German)

Im Rahmen einer Analyse des Programmsystems RELAP5/MOD2 mit dem Ziel, seine Eignung zur Simulierung von Drucktransienten in Druckwasserreaktoren nachzuweisen, wurde der an der LOFT-Anlage durchgefuehrte integrale Test L9-3 (Speisewasserverlust ohne Schnellabschaltung) simuliert. Die Ergebnisse der Analyse waren zufriedenstellend. Einige Folgerungen hinsichtlich der Simulierung von Drucktransienten ohne Schnellabschaltung werden mitgeteilt. (orig.)

Additional details

Publishing Information

Journal Title
Kerntechnik (1987)
Journal Volume
58
Journal Issue
1
Journal Page Range
p. 20-25.
ISSN
0932-3902
CODEN
KERNEU

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
24050779
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ATWS; COMPUTERIZED SIMULATION; FEEDBACK; FEEDWATER; HEAT TRANSFER; LOSS OF COOLANT; POWER DISTRIBUTION; PRESSURE DEPENDENCE; PRESSURIZATION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SIMULATION; TIME DEPENDENCE; TRANSFER FUNCTIONS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUNCTIONS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS