Fuel pin behavior under slow overpower transient conditions; HEDL W-2 SLSF experiment results. [LMFBR]

Conference · Sat Aug 01 00:00:00 EDT 1981

OSTI ID:6265265

Henderson, J M; Seeman, S E; Wood, S A; Metcalf, I L

The HEDL W-2 Sodium Loop Safety Facility (SLSF) Experiment was the first overpower transient test in the US to utilize full-length, fully-preconditioned LMFBR fuel pins. The 7-pin fuel bundle was irradiated for a total of 26 days at a nominal steady-state peak linear pin power level of 42 kW/m (12.8 kW/ft). A 5 cent/s overpower ramp was imposed following five days of continuous steady-state irradiation. Between 10 and 20 seconds into the transient, test instrumentation indicated a limited fuel pin cladding breach. Significant cladding disruption, molten fuel motion, and moderate fuel-coolant interactions occurred at 22 seconds into the transient.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 6265265
• Report Number(s): HEDL-SA-2284-FP; CONF-810803-10; ON: DE81029795; TRN: 81-016660
• Resource Relation: Conference: Topical meeting on reactor safety aspects of fuel behavior, Sun Valley, ID, USA, 2 Aug 1981
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PINS
PERFORMANCE TESTING
THERMAL STRESSES
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
HEAT TRANSFER
HYDRAULICS
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
REACTOR SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding