Published August 1995 | Version v1
Journal article Metadata-only

A methodology for the analysis of a thermal-hydraulic phenomenon investigated in a test facility

Creators

  • 1. Dept. of Mechanical and Nuclear Constructions, Pisa Univ. (Italy)
  • 2. Lab. for Thermal-Hydraulics, Paul Scherrer Inst., Villigen (Switzerland)

Description

A methodology for analysing non-homogeneous sets of experimental data for a selected phenomenon from separate effect test facilities and integral test facilities is presented in this paper. The critical heat flux from the validation matrices was chosen as the phenomenon to be studied; the results obtained in three test facilities are analysed. The method presented is applied for estimating the accuracy with which a thermalhydraulic transient code can predict the critical heat flux in an actual nuclear power plant. (orig.)

Abstract (German)

Gegenstand des Beitrags ist ein Verfahren zur Analyse ungleichartiger Datensaetze, die bei der experimentellen Untersuchung eines bestimmten thermohydraulischen Phaenomens in speziellen oder integralen Testeinrichtungen gewonnen wurden. Bei dem untersuchten Phaenomen handelt es sich hier um die kritische Waermestromdichte; experimentelle Daten aus drei Testeinrichtungen werden analysiert. Das Verfahren wird benutzt, um die Genauigkeit abzuschaetzen, mit der ein thermohydraulischer Rechencode zur Beschreibung von Uebergangszustaenden die kritische Waermestromdichte in einem Kernkraftwerk vorhersagen kann. (orig.)

Additional details

Publishing Information

Journal Title
Kerntechnik (1987)
Journal Volume
60
Journal Issue
4
Journal Page Range
p. 166-174.
ISSN
0932-3902
CODEN
KERNEU

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
27031973
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Descriptors DEI
ACCURACY; BWR TYPE REACTORS; COMPUTER CALCULATIONS; CRITICAL HEAT FLUX; FILM BOILING; HYDRAULICS; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; THERMODYNAMICS; VERIFICATION
Descriptors DEC
BOILING; ENRICHED URANIUM REACTORS; HEAT FLUX; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS