Published August 1985 | Version v1
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Transient three-phases three-component flow. Pt. 2

Creators

Description

Using a one-dimensional slip model a comparison between predicted and experimental results for boiling two-phase flow, pre- and post-DNB flow and heat transfer, loss-of-flow experiment for nuclear heated rod bundle for typical PWR and critical flow was made and the usefulness of the entropy concept was demonstrated. (orig.)

Availability note (English)

MF available from INIS under the Report Number.

Abstract (German)

Anhand einer mit dem eindimensionalen Schlupfmodell durchgefuehrten Nachrechnung von Experimentaldaten fuer siedende Zweiphasenstroemung, Stroemung und Waermeuebergangsmechanismus vor und nach der Siedekrise, Loss-of-flow-Experiment fuer typische PWR und kritische Stroemung wurde die Brauchbarkeit des Entropiekonzepts zur Simulation technisch interessanter Faelle nachgewiesen. (orig.)

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Additional details

Additional titles

Subtitle (English)
One-dimensional slip model - comparison theory - experiment
Original title (German)
Transiente Dreiphasen Dreikomponenten Stroemung. T. 2
Original subtitle (German)
Eindimensionales Schlupfmodell - Vergleich Theorie - Experiment.

Publishing Information

Imprint Pagination
89 p.
Report number
KFK--3926

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
17012940
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALGORITHMS; BOILING; COMPARATIVE EVALUATIONS; CRITICAL FLOW; ENTROPY; EQUATIONS; FLOW RATE; LOSS OF FLOW; MATHEMATICAL MODELS; MULTIPHASE FLOW; NUMERICAL SOLUTION; PWR TYPE REACTORS; SIMULATION; SLIP; SOUND WAVES; TRANSIENTS; TWO-PHASE FLOW; VOIDS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; EVALUATION; FLUID FLOW; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS