Calculation results for the heat transfer crisis conditions during fast transient processes
Creators
Description
The impact of axial power distribution, heat transfer across the fuel/cladding gap and various correlations on the calculations of boiling crisis has been studed for transient regimes connected with the reactivity variations. The simulated transient was characterized by the power versus time curve that corresponded to the control rod bundle shot-out at the following core nominal initial parameters: p = 12.3 MPa, T = 270 grad.C, G = 2700 kg/(m2s). Selection of decreased values of the heat transfer coefficient for the gap resulted in an earlier boiling crisis onset or attaining the minimum critical/actual heat flux density ratio. A comparison is made for Osmachkin's and Bezrukov's correlations employment to the critical heat flux density calculations
Additional details
Additional titles
- Original title (Russian)
- Характер результатов расчетного определения условий кризиса теплообмена при быстрых переходных процессах
Publishing Information
- Imprint Title
- Thermal physics 84. Thermal aspects of WWER nuclear reactor safety. V. 2
- Journal Page Range
- p. 43-65.
- Report number
- INIS-mf--11564
Conference
- Title
- Thermal physics 84. Thermal aspects of WWER nuclear reactor safety.
- Dates
- Oct 1984.
- Place
- Varna (Bulgaria).
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
- 20085817
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; POWER DISTRIBUTION; THEORETICAL DATA; WWER TYPE REACTORS
- Descriptors DEC
- DATA; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT FLUX; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs.; 3 tabs.; 9 figs. Imprint:Teplofizika 84. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov VVEhR. Tom 2.;Sbornik dokladov seminara SEhV, Varna, NRB, Oktyabr' 1984 g.