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