Experiment data report for PBF/LOFT Lead Rod Test Series (Tests LLR-S0, -3, -4, -4A, and -5)

Technical Report · Mon Oct 01 04:00:00 EDT 1979

OSTI ID:5744771

Buckland, R J; Schwieder, D H

Recorded test data are presented for Tests LLR-S0, LLR-3, LLR-4, LLR-4A, and LLR-5 of the Thermal Fuels Behavior Program PBF/LOFT Lead Rod (LLR) Test Series. This test series, conducted in the Power Burst Facility, was designed to provide a parametric evaluation of the expected mechanical response of the LOFT fuel rods to a loss of coolant event. The data, presented in the form of graphs in engineering units, have been analyzed only to the extent necessary to ensure they are reasonable and consistent. These uninterpreted data from the LLR tests are presented in advance of detailed analysis and interpretation.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 5744771
• Report Number(s): NUREG/CR-0927; TREE-1272
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FUEL ELEMENTS
FUEL RODS
LOFT REACTOR
LOSS OF COOLANT
PERFORMANCE
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS