PBF/LOFT Lead Rod Test Program experiment predictions document

Technical Report · Thu Nov 30 23:00:00 EST 1978

OSTI ID:6526457

Varacalle, D J; Cox, W R; Niebruegge, D A; Seiber, S J; Brake, T E; Driskell, W E; Nigg, D W; Tolman, E L

The PBF/LOFT Lead Rod (LLR) Test Program is being conducted to provide experimental information on the behavior of nuclear fuel under normal and accident conditions in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The PBF/LLR tests are designed to simulate the test conditions for the LOFT Power Ascension Tests L2-3 through L2-5. The test program has been designed to provide a parametric evaluation of the LOFT fuel (center and peripheral modules) over a wide range of power. This report presents the experiment predictions for the three four-rod LOCA tests.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6526457
• Report Number(s): TFBP-TR-307
• 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
BLOWDOWN
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
MOCKUP
PERFORMANCE TESTING
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
STRUCTURAL MODELS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS