Published November 1987
| Version v1
Journal article
Simple model for calculating steam entrainment into the downcomer of a nuclear heating reactor
Creators
- 1. Ingenieurhochschule Zittau (German Democratic Republic). Sektion Kraftwerksanlagen und Energieumwandlung
- 2. Moskovskij Ehnergeticheskij Inst. (USSR)
Description
On the basis of flow performance in a nuclear heating reactor of integrated type using natural circulation of the coolant flowing as a two-phase mixture in several sections, the gas fraction, ψ, entrained into the downcomer is defined which is of importance for stable operation of the reactor. Analysis of the experimental investigations hitherto carried out has resulted in identifying a variety of influencing factors which are classified and, for the most part, enter into the model developed for calculating the entrainment coefficient ψ. Comparison with experimental data shows that the calculational model satisfactorily reflects the physical dependencies in first approximation. (author)
Additional details
Additional titles
- Original title (German)
- Ein einfaches Modell zur Berechnung des Mitreissens von Dampf in den Sinkschacht eines Kernheizreaktors
Publishing Information
- Journal Title
- Kernenergie
- Journal Volume
- 30
- Journal Issue
- 11-12
- Series
- Kernenergie.
- Journal Page Range
- 442-449
- ISSN
- 0023-0642
- CODEN
- KERNA
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- German Democratic Republic
- INIS RN
- 19023597
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- AIR; BUBBLES; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; DISTRICT HEATING; ENTRAINMENT; EXPERIMENTAL DATA; GERMAN DEMOCRATIC REPUBLIC; INTERNATIONAL COOPERATION; MATHEMATICAL MODELS; NATURAL CONVECTION; NUCLEAR POWER PLANTS; PRIMARY COOLANT CIRCUITS; STEAM; THERMODYNAMICS; TWO-PHASE FLOW; USSR; WATER
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; COOPERATION; DATA; DEVELOPED COUNTRIES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; EVALUATION; FLUID FLOW; FLUIDS; GASES; HEAT TRANSFER; HEATING; HYDROGEN COMPOUNDS; INFORMATION; NUCLEAR FACILITIES; NUMERICAL DATA; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SOLVENTS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS