Modeling a forced to natural convection boiling test with the program LOOP-W. [LMFBR]
Conference
·
OSTI ID:6854257
Extensive testing has been conducted in the Simulant Boiling Flow Visualization (SBFV) loop in which water is boiled in a vertical transparent tube by circulating hot glycerine in an annulus surrounding the tube. Tests ranged from nonboiling forced convection to oscillatory boiling natural convection. The program LOOP-W has been developed to analyze these tests. This program is a multi-leg, one-dimensional, two-phase equilibrium model with slip between the phases. In this study, a specific test, performed at low power where non-boiling forced convection was changed to boiling natural convection and then to non-boiling again, has been modeled with the program LOOP-W.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6854257
- Report Number(s):
- CONF-840614-67; ON: DE84014256
- Resource Relation:
- Conference: Annual meeting of the American Nuclear Society, New Orleans, LA, USA, 3 Jun 1984; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF FLOW
NATURAL CONVECTION
TEST FACILITIES
BOILING
EXPERIMENTAL DATA
FLOW RATE
REACTOR SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
ACCIDENTS
BREEDER REACTORS
CONVECTION
DATA
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
NUMERICAL DATA
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF FLOW
NATURAL CONVECTION
TEST FACILITIES
BOILING
EXPERIMENTAL DATA
FLOW RATE
REACTOR SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
ACCIDENTS
BREEDER REACTORS
CONVECTION
DATA
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
NUMERICAL DATA
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding