Published December 1990 | Version v1
Journal article Metadata-only

Calculation of critical heat flux for estimation of fuel element reliability

Creators

  • 1. VE Kombinat Kernkraftwerke, Greifswald (Germany, F.R.). Betriebsteil Kernkraftwerke Rheinsberg

Description

The relationships for calculating DNB heat fluxes hitherto used in the GDR and by other operators of the WWER-type reactor are evaluated. As a result they are found to do not seem appropriate to answer the questions arising with estimation of core condition safety in a satisfactory manner. It is recommended to pass over to relationships simply and solely based on parameters of a singly flow channel, and such a relationship is presented. (author)

Additional details

Additional titles

Original title (German)
Berechnung von kritischen Waermestromdichten zur Einschaetzung der Brennelementsicherheit

Publishing Information

Journal Title
Kernenergie
Journal Volume
33
Journal Issue
12
Series
Kernenergie.
Journal Page Range
466-467
ISSN
0023-0642
CODEN
KERNA

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
22023433
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
DEPARTURE NUCLEATE BOILING; REACTOR CORES; REACTOR SAFETY; WWER-3 REACTOR
Descriptors DEC
BOILING; ENRICHED URANIUM REACTORS; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS