U.S. Department of EnergyOffice of Scientific and Technical Information
Rod-bundle transient-film boiling of high-pressure water in the liquid-deficient regime. [PWR]
Abstract
Results are reported from a recent experiment investigating dispersed flow film boiling of high pressure water in upflow through a rod bundle. The data, obtained under mildly transient conditions, are used to assess correlations currently used to predict heat transfer in these circumstances. In light of the scarcity of similar data, the data should prove useful in the development and assessment of new heat transfer models. The experiment was conducted at the Oak Ridge National Laboratory in the Thermal-Hydraulic Test Facility, a highly instrumented, non-nuclear, pressurized-water loop containing 64, 3.66-m (12-ft) long rods (of which 60 are electrically heated). The rods are arranged in a square array typical of 17 x 17 fuel rod assemblies in late generation PWRs. Data were collected over typical reactor blowdown parameter ranges.
- Authors:
- Publication Date:
- Research Org.:
- Oak Ridge National Lab., TN (USA)
- OSTI Identifier:
- 5338924
- Report Number(s):
- CONF-820604-10
ON: DE82017489; TRN: 82-015959
- DOE Contract Number:
- W-7405-ENG-26
- Resource Type:
- Conference
- Resource Relation:
- Conference: AIAA/ASME joint conference on fluids, plasma, thermophysics and heat transfer, St Louis, MO, USA, 7 Jun 1982; Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; BLOWDOWN; BOILING; REACTOR SAFETY; TEST FACILITIES; TWO-PHASE FLOW; ACCIDENTS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; MECHANICS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Citation Formats
Morris, D G, Mullins, C B, and Yoder, G L. Rod-bundle transient-film boiling of high-pressure water in the liquid-deficient regime. [PWR]. United States: N. p., 1982.
Web.
Morris, D G, Mullins, C B, & Yoder, G L. Rod-bundle transient-film boiling of high-pressure water in the liquid-deficient regime. [PWR]. United States.
Morris, D G, Mullins, C B, and Yoder, G L. 1982.
"Rod-bundle transient-film boiling of high-pressure water in the liquid-deficient regime. [PWR]". United States. https://www.osti.gov/servlets/purl/5338924.
@article{osti_5338924,
title = {Rod-bundle transient-film boiling of high-pressure water in the liquid-deficient regime. [PWR]},
author = {Morris, D G and Mullins, C B and Yoder, G L},
abstractNote = {Results are reported from a recent experiment investigating dispersed flow film boiling of high pressure water in upflow through a rod bundle. The data, obtained under mildly transient conditions, are used to assess correlations currently used to predict heat transfer in these circumstances. In light of the scarcity of similar data, the data should prove useful in the development and assessment of new heat transfer models. The experiment was conducted at the Oak Ridge National Laboratory in the Thermal-Hydraulic Test Facility, a highly instrumented, non-nuclear, pressurized-water loop containing 64, 3.66-m (12-ft) long rods (of which 60 are electrically heated). The rods are arranged in a square array typical of 17 x 17 fuel rod assemblies in late generation PWRs. Data were collected over typical reactor blowdown parameter ranges.},
doi = {},
url = {https://www.osti.gov/biblio/5338924},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1982},
month = {Fri Jan 01 00:00:00 EST 1982}
}