W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance. [LMFBR]

Conference · Thu May 01 04:00:00 EDT 1980

OSTI ID:5284617

Meyers, S. C.; Henderson, J. M.

The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponsored by the Department of Energy (DOE) as part of the National Fast Breeder Reactor (FBR) Safety Assurance Program. The experiments are being conducted under the direction of Argonne National Laboratory (ANL) and Hanford Engineering Development Laboratory (HEDL). The irradiation phase of the W-1 SLSF experiment was conducted between May 27 and July 20, 1979, and terminated with incipient fuel pin cladding failure during the final boiling transient. Experimental hardware and facility performed as designed, allowing completion of all planned tests and test objectives. This paper focuses on high temperature in-fuel thermocouples and discusses their development, fabrication, and performance in the W-1 experiment.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 5284617
• Report Number(s): HEDL-SA-2015-FP; CONF-800607-65
• 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
DESIGN
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MEASURING INSTRUMENTS
PERFORMANCE
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TEST FACILITIES
THERMOCOUPLES