Published September 1999 | Version v1
Journal article

Critical heat flux in a vertical tube at low and medium pressures. Pt. I. Experimental results

  • 1. Ecole Polytechnique, Montreal, PQ (Canada). Inst. de Genie Nucleaire
  • 2. Chalk River Laboratories, AECL Research, Chalk River (Canada)

Description

For pt.II see ibid., vol.193, p.91-103, 1999. This paper presents experimental CHF data obtained for vertical up flow in an 8 mm I.D. test section, for a wide range of exit qualities (5-75%) and exit pressures ranging from 5 to 40 bar. The experiments were carried out for heated lengths of 0.75, 1, 1.4, 1.8, 2.5 and 3.5 m. A number of different coordinate systems are used to present the experimental results, these include CHF as a function of the inlet subcooling, as a function of the outlet thermodynamic quality, and as a function of the boiling length. An analysis of these commonly used representations of the CHF, has shown, that for all of the cases studied, the critical heat flux is dependent in some manner on the heated length. This dependence greatly complicates the possibility of obtaining a universal correlation for the critical heat flux at low and medium pressures. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
193
Journal Issue
1-2
Journal Page Range
p. 73-89
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
Switzerland
INIS RN
31000279
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BOILING; COOLING; CRITICALITY; HEAT TRANSFER; PIPES; PRESSURE DEPENDENCE; THERMODYNAMICS
Descriptors DEC
ENERGY TRANSFER; PHASE TRANSFORMATIONS

Optional Information

Notes
22 refs.