Published February 1987
| Version v1
Journal article
Post-dryout heat transfer of high-pressure steam-water two-phase flow in single rod channel and multi rod bundle
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Dept. of Nuclear Safety Research
Description
Low flow rate post-dryout heat transfer experiments of steam-water two-phase flow were conducted at the Japan Atomic Energy Research Institute using single rod and 25 rod heat transfer test facilities. The experiments covered mass flow rates from 20 to 800 kg/m2 s, qualities from 0.0 to 1.0 and pressures from 3 to 12 MPa. New correlations for the post-dryout heat transfer coefficient have been proposed by improving the Groeneveld correlation. The proposed correlations can account for the dependence of the heat transfer on the heat transfer surface temperature which the original Groeneveld correlation cannot do explicitly. The agreement between the predicted and measured values is satisfactory. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 99
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 157-165
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 3. international topical meeting on reactor thermal hydraulics.
- Dates
- 15-18 Oct 1985.
- Place
- Newport, RI (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 18057095
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORRELATIONS; DRYOUT; FLOW RATE; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LOSS OF COOLANT; REACTOR CHANNELS; SUPERHEATING; TEMPERATURE MEASUREMENT; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; HEATING; REACTOR ACCIDENTS; REACTOR COMPONENTS