Published 1992 | Version v1
Book

Numerical calculation of gas-liquid transient flow in channels and bends

  • 1. Univ. of Maryland, College Park, MD (United States). Dept. of Mechanical Engineering
  • 2. Univ. of Maryland, College Park, MD (United States)

Description

An accurate prediction of transient two-phase flow phenomena is quite important in safety analyses of nuclear reactors under normal, off-normal or accident conditions. In general, the ability to predict these thermohydraulic phenomena of two-phase flow depends on the availability of mathematical models and experimental correlations. The fluid flow and heat transfer encountered in reactor safety analyses are often very complex due to reactor geometries. Furthermore, full scale experiments with sufficient instrumentations are often extremely difficult to perform due to its size and adverse conditions. These indicate the importance of accurate two-phase flow models and constitutive relations which take into account the widely varying properties, system scales and geometrical effects. The algorithm used in this paper is Newton Block Gauss Seidel (NBGS) method, which has been applied to both simple and complex flow conditions in two-phase flow. This paper contains a description of difference techniques and iterative solution algorithm that is used to solve the field and constitutive equations of the two-fluid model. In practice this solution procedure has been proven to be stable and capable of generating solutions in problems where other schemes have failed. Examples of transient two dimensional air-water flow with in channels and bends with variation of inlet slip ratio and void fraction is being presented in this paper

Part of:
Multiphase flow in wells and pipelines

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1129-8
Imprint Title
Multiphase flow in wells and pipelines
Imprint Pagination
176 p.
Journal Page Range
p. 113-123.

Conference

Title
Winter annual meeting of the American Society of Mechanical Engineers (ASME).
Dates
8-13 Nov 1992.
Place
Anaheim, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25036923
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AIR; ALGORITHMS; FLOW MODELS; HEAT TRANSFER; NUMERICAL SOLUTION; REACTORS; SAFETY ANALYSIS; STEAM; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; WATER
Descriptors DEC
ENERGY TRANSFER; FLUID FLOW; FLUIDS; GASES; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; OXYGEN COMPOUNDS

Optional Information

Secondary number(s)
CONF-921110--.