Published April 2001 | Version v1
Journal article

Critical heat flux under zero flow conditions in vertical annulus with uniformly and non-uniformly heated sections

Description

The experimental study of water CHF (critical heat flux) under zero flow conditions has been carried out in an annulus flow channel with uniformly and non-uniformly heated sections over a pressure range of 0.52-14.96 MPa. In the present boiling system, the CHFs occur in the upper region of the heated section, in contrast to the results in the experiments for boiling tubes conducted by several investigators. The general trend of the CHF with pressure is that the CHF increases up to a medium pressure of about 6-8 MPa and decreases as the pressure is further increased. A comparison of the present data with the existing flooding CHF correlations shows that the correlations depend greatly on the effect of the heat flux distribution. When the correction terms with the density ratio and the effect of the heat flux distribution proposed in the present work are used with the CHF correlation based on the Wallis flooding correlation, it predicts the measured flooding CHF within an RMS error of 9.0%

Additional details

Identifiers

PII
S0029549300003770;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
205
Journal Issue
3
Journal Page Range
p. 265-279
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
Hungary
INIS RN
34036656
Subject category
S42: ENGINEERING;
Descriptors DEI
CORE FLOODING SYSTEMS; CRITICAL HEAT FLUX; FLOW MODELS; FLUID FLOW; PRESSURE DEPENDENCE
Descriptors DEC
ECCS; ENGINEERED SAFETY SYSTEMS; HEAT FLUX; MATHEMATICAL MODELS; REACTOR PROTECTION SYSTEMS

Optional Information

Copyright
Copyright (c) 2001 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.