Comparison of numerical results with experimental data for single-phase natural convection in an experimental sodium loop
Description
A comparison is made between computed results and experimental data for single-phase natural convection in an experimental sodium loop. The tests were conducted in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility, an engineering-scale high temperature sodium facility at the Oak Ridge National Laboratory used for thermal-hydraulic testing of simulated LMFBR subassemblies at normal and off-normal operating conditions. Heat generation in the 19 pin assembly during these tests was typical of decay heat levels. Tests were conducted both with zero initial forced flow and with a small initial forced flow. The bypass line was closed in most tests, but open in one. The computer code used to analyze these tests [LONAC (LOw flow and NAtural Convection)] is an ORNL-developed, fast running, one-dimensional, single-phase finite difference model for simulating forced and free convection transients in the THORS loop
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A04/MF A01.Files
10495019.pdf
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 53 p.
- Report number
- CONF-790808--13
Conference
- Title
- 18. ASME national heat transfer conference.
- Dates
- Aug 1979.
- Place
- San Diego, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10495019
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; FUEL ASSEMBLIES; HEAT TRANSFER; LMFBR TYPE REACTORS; NATURAL CONVECTION; PRESSURE DROP; PRIMARY COOLANT CIRCUITS
- Descriptors DEC
- BREEDER REACTORS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS