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.