Sodium boiling tests in a 19-pin internally guard heated simulated LMFBR fuel assembly with a six-channel internal blockage: record of experimental data for THORS bundle 3C

Technical Report · Tue May 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/6053419· OSTI ID:6053419

Morris, R. H. ^[1]

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1. Oak Ridge National Laboratory (ORNL)

A recored is presented of experimental data obtained during boiling propagation tests with bundle 3C in the Liquid-Metal Fast Breeder Reactor (LMFBR) Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility. The objective of these tests was to verify that boiling in the wake of a local blockage will not propagate axially or radially. Bundle 3C consisted of 19 electrically heated pins (fuel pin simulators (FPSs)), having the same configuration and heat flux capability as Fast Flux Test Facility (FFTF) and Clinch River Breeder Reactor (CRBR) fuel, surrounded by 12 heated edge pins installed in a stainless steel duct. A 6.4-mm (0.25-in.) stainless steel plate attached to the central pin blocked the six central channels 381 mm (15.0 in.) downstream from the start of the heated section. The test bundle and the loop were designed to simulate prototypic boundary pressure conditions and downstream heat capacity characteristics.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 6053419
• Report Number(s): ORNL/TM-6792
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BOILING
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
PHASE TRANSFORMATIONS
REACTORS
TEMPERATURE GRADIENTS
TEST FACILITIES