HEDL W-1 SLSF experiment LOPI transient and boiling test results. [LMFBR]
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release characteristics of fast reactor fuel pins under Loss-of-Piping-Integrity (LOPI) accident conditions and determine stable sodium boiling initiation and recovery limits in a prototypic fuel pin bundle array. The results of the experiment address major second level of assurance (LOA-2) safety issues and provide increased insight and understanding of phenomena that would inherently terminate hypothesized accidents with only limited core damage. The irradiation phase of the experiment, consisting of thirteen individual transients, was performed between May 27 and July 20, 1979. The final transient produced approximately two seconds of coolant boiling, cladding dryout, and incipient fuel pin failure. The facility and test hardware performed as designed, allowing completion of all planned tests and achievement of all test objectives.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 5260731
- Report Number(s):
- HEDL-SA-2012-FP; CONF-800607-74; TRN: 80-013616
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Las Vegas, NV, USA, 8 Jun 1980
- Country of Publication:
- United States
- Language:
- English
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Fuel pin behavior under slow overpower transient conditions; HEDL W-2 SLSF experiment results. [LMFBR]
W-1 SLSF experiment. [LMFBR]
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF COOLANT
TEST FACILITIES
HEAT TRANSFER
HYDRAULICS
PERFORMANCE
SPECIFICATIONS
DRYOUT
FUEL ELEMENT FAILURE
FUEL PINS
REACTOR SAFETY
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
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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