Two-phase flow visualization in a transparent, atmospheric pressure, boiling water loop
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE84016857.Files
16086121.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 26 p.
- Report number
- CONF-850614--1
Conference
- Title
- ASME-ASCE fluids engineering conference and joint mechanics conference.
- Dates
- 24-26 Jun 1985.
- Place
- Albuquerque, NM (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16086121
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; FUEL ELEMENT CLUSTERS; LMFBR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR INSTRUMENTATION; REACTOR SAFETY; SIMULATION; TESTING; TWO-PHASE FLOW; US DOE
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; FUEL ASSEMBLIES; LIQUID METAL COOLED REACTORS; NATIONAL ORGANIZATIONS; PHASE TRANSFORMATIONS; REACTORS; SAFETY; US ORGANIZATIONS