Published July 1986
| Version v1
Journal article
On the method of heat exchange calculation for critical and postcritical regimes in sodium-water steam generators
Creators
Description
Technique for calculating heat exchange in sodium-water steam generators with provisions for steam-water flow non-equilibrium character and moisture additional evaporation in pipes is suggested. Zone of heat exchange crisis representing the zone of transition from developed boiling to postcritical zone is considered. Comparison of estimated and experimental data performed for the following ranges of steame generator parameters: pressure p=7.8-14.0 MPa, coolant flow rate ρw=350-1000 kg/(m2xs), inlet sodium temperature T=590-825 K shows their good agreement
Additional details
Additional titles
- Original title (Russian)
- О методике расчета теплообмена в зоне кризиса и закризисной зоне парогенераторов натрий-вода
Publishing Information
- Journal Title
- At. Ehnerg.
- Journal Volume
- 61
- Journal Issue
- 1
- Series
- At. Ehnerg.
- Journal Page Range
- 55-57
- ISSN
- 0004-7163
- CODEN
- AENGA
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 18074005
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- DRYOUT; EXPERIMENTAL DATA; FLOW RATE; FLUX DENSITY; HEAT FLUX; HEAT TRANSFER; HIGH PRESSURE; HIGH TEMPERATURE; MEDIUM PRESSURE; NUCLEAR POWER PLANTS; SODIUM COOLED REACTORS; SPATIAL DISTRIBUTION; STEAM; STEAM GENERATORS; THEORETICAL DATA; TWO-PHASE FLOW; WATER
- Descriptors DEC
- BOILERS; DATA; DISTRIBUTION; ENERGY TRANSFER; FLUID FLOW; HYDROGEN COMPOUNDS; INFORMATION; LIQUID METAL COOLED REACTORS; NUCLEAR FACILITIES; NUMERICAL DATA; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER PLANTS; REACTORS; SOLVENTS; THERMAL POWER PLANTS; VAPOR GENERATORS
Optional Information
- Notes
- For English translation see the journal Soviet Journal of Atomic Energy (USA).