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.