Published 1980 | Version v1
Report

Application of the one-dimensional two-fluid model to transient two-phase flows

  • 1. Atomic Energy of Canada, Pinawa, Manitoba

Description

In safety analyses associated with nuclear reactors, vapor-liquid flows produced by rapid depressurization due to discharge through a break of initially subcooled liquid flowing in a network of pipes is of particular interest. In this work, a set of working equations for transient one-dimensional two-phase flows which allow unequal phase velocities and temperatures are presented. Specific attention is focussed on the equations for separated and mixed flow structures. The relationships for interface and wall transfer processes, and the difference between the phase and interface pressures for these idealized flow structures are considered. The mathematical and physical behavior of the model is examined by studying propagation velocities of acoustic waves in various flow regimes. The model is applied to a simple benchmark problem to demonstrate its practicality. Interface heat transfer and virtual mass terms are shown to play significant roles in the predicted transients

Additional details

Publishing Information

Imprint Title
Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods
Journal Page Range
p. 2064-2095.
Report number
NUREG/CP--0014(Vol.3)

Conference

Title
ANS/ASME topical meeting on reactor thermal-hydraulics.
Dates
9 - 12 Oct 1980.
Place
Saratoga, NY, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12641523
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; ONE-DIMENSIONAL CALCULATIONS; POWER REACTORS; PRESSURE DROP; REACTOR ACCIDENTS; REACTOR SAFETY; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; FLUID FLOW; REACTORS; SAFETY