Published 1982 | Version v1
Miscellaneous

Analysis of some ways of taking into account the radially non-uniform power density effects on heat transfer crisis

Description

Some ways of taking into account the radially non-uniform power density effects in the heat transfer crisis margin calculations are considered. The different approaches are evaluated by comparison with experimental data on heat transfer crisis in fuel rod bundles with high power density radial non-uniformity. Calculations with the use of subchannel method have been performed on VEVERKA code. From the obtained results the following conclusions can be drawn: the method of one-dimensional optimistic estimate on the averaged over the bundle cross-section coolant parameters is not applicable to the rod bundles with high power density radial non-uniformity; to improve the calculation reliability some more accurate correlation for the turbulent mixing coefficient is needed as well as the basing of the bundle cross-section breaking into subchannels; a good agreement with experimental data has been obtained from the one-dimensional mean estimate; for the rod bundles with the highest power density radial non-uniformity the arithmetical mean error in the critical power level calculation was about several per cent

Additional details

Additional titles

Original title (Russian)
Analiz nekotorykh sposobov ucheta vliyaniya radial'noj neravnomernosti teplovydeleniya v puchkakh sterzhnej na krizis teplootdachi

Publishing Information

Imprint Title
Thermal physics 82. Thermal aspects of WWER nuclear reactors safety. V. 4.
Journal Page Range
p. 150-158.
Report number
INIS-mf--9995

Conference

Title
Thermal physics 82. Thermal aspects of WWER nuclear reactors safety.
Dates
4-6 May 1982.
Place
Karlovy Vary (Czechoslovakia).

INIS

Country of Publication
International Centre for Scientific and Technical Information (ICSTI)
Country of Input or Organization
International Centre for Scientific and Technical Information (ICSTI)
INIS RN
16072090
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; DEPARTURE NUCLEATE BOILING; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; MATHEMATICAL MODELS; MIXING; POWER DISTRIBUTION; TURBULENT FLOW; WWER TYPE REACTORS
Descriptors DEC
BOILING; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
10 refs.; 2 figs.; 1 tab. Imprint:Teplofizika 82. Tom 4. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov WWER.;Sbornik dokladov iz seminara SEhV g.Karlovy Vary, ChSSR, Maj 1982 g.