PBF/LOFT Lead Rod Program Test LLR-4A Quick Look Report

Technical Report · Fri Jun 01 04:00:00 EDT 1979

OSTI ID:5278097

Varacalle, Jr, D J; Garner, R W

This report describes the prliminary results of the PBF/LOFT Lead Rod (LLR) Program Test LLR-4A conducted in the Power Burst Facility Test Reactor at the Idaho National Engineering Laboratory. Test LLR-4A was conducted on May 18, 1979. The PFB/LLR Tests (LLR-3, LLR-5, and LLR-4) were designed to simulate the test conditions for LOFT loss-of-coolant experiment (LOCEs) tests L2-3 through L2-5. Test LLR-4A was added to the PBF/LLR program following completion of Test LLR-4 to investigate the effects of preconditioning and a successive LOCE transient on deformed fuel rods. The test conditions and performance sequence for this test were identical to the LLR-4 test.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5278097
• Report Number(s): TFBP-TR-320; ON: TI85016692
• Country of Publication: United States
• Language: English

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220600 -- Nuclear Reactor Technology-- Research
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DATA
EXPERIMENTAL DATA
FUEL ELEMENTS
FUEL RODS
INFORMATION
LOFT REACTOR
LOSS OF COOLANT
NUMERICAL DATA
PBF REACTOR
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS