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Title: HEDL W-1 SLSF experiment LOPI transient and boiling test results. [LMFBR]

Conference ·
OSTI ID:5260731

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