Countercurrent flow limited (CCFL) heat flux in the high flux isotope reactor (HFIR) fuel element
The countercurrent flow (CCF) performance in the fuel element region of the HFIR is examined experimentally and theoretically. The fuel element consists of two concentric annuli filled with aluminum clad fuel plates of 1.27 mm thickness separated by 1.27 mm flow channels. The plates are curved as they go radially outward to accomplish constant flow channel width and constant metal-to-coolant ratio. A full-scale HFIR fuel element mock-up is studied in an adiabatic air-water CCF experiment. A review of CCF models for narrow channels is presented along with the treatment of CCFs in system of parallel channels. The experimental results are related to the existing models and a mechanistic model for the annular'' CCF in a narrow channel is developed that captures the data trends well. The results of the experiment are used to calculate the CCFL heat flux of the HFIR fuel assembly. It was determined that the HFIR fuel assembly can reject 0.62 Mw of thermal power in the CCFL situation. 31 refs., 17 figs.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6361303
- Report Number(s):
- ORNL/TM-11638; ON: DE91005601; TRN: 91-001725
- Country of Publication:
- United States
- Language:
- English
Similar Records
Advanced test reactor countercurrent flow experiment
Advanced neutron source reactor thermal-hydraulic test loop facility description
Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HFIR REACTOR
FUEL ELEMENTS
REACTOR COOLING SYSTEMS
C CODES
EXPERIMENTAL DATA
FLOW MODELS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
REACTOR CHANNELS
COMPUTER CODES
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
INFORMATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATHEMATICAL MODELS
MECHANICS
NUMERICAL DATA
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
990200 - Mathematics & Computers