Sodium boiling and mixed oxide fuel thermal behavior in FBR undercooling transients; W-1 SLSF experiment results

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:6265272

Henderson, J M; Wood, S A; Knight, D D

The W-1 Sodium Loop Safety Facility (SLSF) Experiment was conducted to study fuel pin heat release characteristics during a series of LMFBR Loss-of-Piping Integrity (LOPI) transients and to investigate a regime of coolant boiling during a second series of transients at low, medium and high bundle power levels. The LOPI transients produced no coolant boiling and showed only small changes in coolant temperatures as the test fuel microstructure changed from a fresh, unrestructured to a low burnup, restructured condition. During the last of seven boiling transients, intense coolant boiling produced inlet flow reversal, cladding dryout and moderate cladding melting.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA); General Electric Co., Sunnyvale, CA (USA). Advanced Reactor Systems Dept.
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 6265272
• Report Number(s): HEDL-SA-2263-FP; CONF-810803-13; ON: DE81029759
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MECHANICS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES