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Critical heat flux determination in an annulus section; Determinacion del flujo critico de calor en una seccion anular

Abstract

The present report explains the phenomenon of Critical heat flux. The study of this physical phenomenon is carried out during the boiling of a liquid and is of supreme importance for the calculation and operation of a nuclear reactor even in the moderns generators of steam (thermoelectric and nucleoelectrics), industrial cooling and in all those industrial process that use a liquid subject to sources of heating and to conditions of work excessively high (temperatures and pressures) so that stay in operation in an appropriate manner and sure. Once well-known this value, the equipment used in these process works with a maximum heat that is smaller than the Critical Heat Flux. The study of the Critical Heat Flux has achieved important advances in the last years, mainly for the enormous obligation that in this moment involved the safety to world level, this has forced to researchers and designers of this type of equipment to center their attention in the obtaining of a correlation which of general way explains it. In this reports two correlations will be compared that they contribute to the evaluation of the Critical Heat Flux in annulus and that they try to be generals in this type of  More>>
Authors:
Publication Date:
Apr 01, 1997
Product Type:
Thesis/Dissertation
Report Number:
INIS-MX-004
Reference Number:
SCA: 420400; PA: AIX-28:030619; EDB-97:056688; NTS-97:012062; SN: 97001765265
Resource Relation:
Other Information: TH: Thesis (Mechanical Engineer).; PBD: 1997
Subject:
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; CRITICAL HEAT FLUX; ANNULAR SPACE; BENCH-SCALE EXPERIMENTS; BOILING; CORRELATIONS; DATA ACQUISITION SYSTEMS; FORCED CONVECTION; HEAT TRANSFER; HYDRAULIC EQUIPMENT; NATURAL CONVECTION
OSTI ID:
455532
Research Organizations:
Instituto Politecnico Nacional, Mexico City (Mexico). Escuela Superior de Ingenieria Mecanica y Electrica
Country of Origin:
Mexico
Language:
Spanish
Other Identifying Numbers:
Other: ON: DE97620577; TRN: MX9700026030619
Availability:
INIS; OSTI as DE97620577
Submitting Site:
INIS
Size:
86 p.
Announcement Date:
Apr 17, 1997

Citation Formats

Reyes C, C A. Critical heat flux determination in an annulus section; Determinacion del flujo critico de calor en una seccion anular. Mexico: N. p., 1997. Web.
Reyes C, C A. Critical heat flux determination in an annulus section; Determinacion del flujo critico de calor en una seccion anular. Mexico.
Reyes C, C A. 1997. "Critical heat flux determination in an annulus section; Determinacion del flujo critico de calor en una seccion anular." Mexico.
@misc{etde_455532,
title = {Critical heat flux determination in an annulus section; Determinacion del flujo critico de calor en una seccion anular}
author = {Reyes C, C A}
abstractNote = {The present report explains the phenomenon of Critical heat flux. The study of this physical phenomenon is carried out during the boiling of a liquid and is of supreme importance for the calculation and operation of a nuclear reactor even in the moderns generators of steam (thermoelectric and nucleoelectrics), industrial cooling and in all those industrial process that use a liquid subject to sources of heating and to conditions of work excessively high (temperatures and pressures) so that stay in operation in an appropriate manner and sure. Once well-known this value, the equipment used in these process works with a maximum heat that is smaller than the Critical Heat Flux. The study of the Critical Heat Flux has achieved important advances in the last years, mainly for the enormous obligation that in this moment involved the safety to world level, this has forced to researchers and designers of this type of equipment to center their attention in the obtaining of a correlation which of general way explains it. In this reports two correlations will be compared that they contribute to the evaluation of the Critical Heat Flux in annulus and that they try to be generals in this type of geometry, the Shah correlation`s and the Katto correlation`s. The same as most of the correlations, these have been calculated so that the fluid of work is water, although they have also been proven with others fluids. The results obtained in this report only will show the degree of advance which the investigation of this phenomenon has achieved in annulus and to low amounts of flow of liquid, like which they are in the Experimental Heat Transfer Circuit located in the Department of Physics of the National Institute of Nuclear Research. (Author).}
place = {Mexico}
year = {1997}
month = {Apr}
}