Published 1981 | Version v1
Report

One-dimensional transient unequal velocity two-phase flow by the method of characteristics

Description

An understanding of two-phase flow is important when one is analyzing the accidental loss of coolant or when analyzing industrial processes. If a pipe in the steam generator of a nuclear reactor breaks, the flow will remain critical (or choked) for almost the entire blowdown. For this reason the knowledge of the two-phase maximum (critical) flow rate is important. A six-equation model--consisting of two continuity equations, two energy equations, a mixture momentum equation, and a constitutive relative velocity equation--is solved numerically by the method of characteristics for one-dimensional, transient, two-phase flow systems. The analysis is also extended to the special case of transient critical flow. The six-equation model is used to study the flow of a nonequilibrium sodium-argon system in a horizontal tube in which the nonequilibrium sodium-argon system in a horizontal tube in which the critical flow condition is at the entrance. A four-equation model is used to study the pressure-pulse propagation rate in an isothermal air-water system, and the results that are found are compared with the experimental data. Proper initial and boundary conditions are obtained for the blowdown problem. The energy and mass exchange relations are evaluated by comparing the model predictions with results of void-fraction and heat-transfer experiments. A simplified two-equation model is obtained for the special case of two incompressible phases. This model is used in the preliminary analysis of batch sedimentation. It is also used to predict the shock formation in the gas-solid fluidized bed

Availability note (English)

University Microfilms Order No. 82-11,418.

Additional details

Publishing Information

Imprint Pagination
171 p.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14761727
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Thesis, Non-conventional Literature
Descriptors DEI
ARGON; BLOWDOWN; CRITICAL FLOW; INCOMPRESSIBLE FLOW; MATHEMATICAL MODELS; SODIUM; STEAM GENERATORS; TWO-PHASE FLOW
Descriptors DEC
ALKALI METALS; BOILERS; ELEMENTS; FLUID FLOW; METALS; NONMETALS; RARE GASES; VAPOR GENERATORS