Two-phase flow visualization in a transparent, atmospheric pressure, boiling water loop
The Simulant Boiling Flow Visualization (SBFV) loop, a transparent, atmospheric pressure test apparatus employing boiling water as a simulant for boiling liquid sodium, has been designed and operated at Oak Ridge National Laboratory. The objective of testing in this loop has been to study two-phase flow behavior that is phenomenologically similar to that observed in sodium boiling experiments, as part of the US Department of Energy Breeder Reactor Safety Program. A detailed description of the design of the SBFV loop is presented, as well as experimental results that show the similarity between low-power boiling behavior in water and liquid sodium. Future tests are planned in a seven-pin flow visualization bundle that will be installed in the SBFV loop. The design of this bundle is also discussed.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5859485
- Report Number(s):
- CONF-850614-1; ON: DE84016857
- Resource Relation:
- Conference: ASME-ASCE fluids engineering conference and joint mechanics conference, Albuquerque, NM, USA, 24 Jun 1985; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
THORAX pretest prediction of a sodium-boiling transient in a 19-pin simulated LMFBR driver bundle
Forced-to-natural convection transition tests in parallel simulated liquid metal reactor fuel assemblies
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR ACCIDENTS
TEST FACILITIES
TWO-PHASE FLOW
ATMOSPHERIC PRESSURE
BOILING
REACTOR INSTRUMENTATION
REACTOR SAFETY
ROD BUNDLES
SIMULATION
US DOE
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
LIQUID METAL COOLED REACTORS
NATIONAL ORGANIZATIONS
PHASE TRANSFORMATIONS
REACTORS
SAFETY
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210500 - Power Reactors
Breeding