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.