LOFT L1-5 Level I Fuel Module Requalification Test report

Technical Report · Mon Aug 07 00:00:00 EDT 1978

OSTI ID:6490021

Cannon, J W; Chick, D W; Franz, W A; Serrano, W; Talbert, R J; Yarbrough, W M; Carpenter, W R; Knight, D W; Zentner, M D; Zimmerman, W L

Level I Fuel Module Requalification testing, completed at LOFT for the L1-5 Loss of Coolant Experiment (LOCE) on May 13, 1978, showed no evidence of any significant damage to the reactor system. No significant differences were noted in control rod drop times at cold conditions with no flow, exact critical measurements, axial flux profiles, or differential control rod worth measurements. The control rod drop times for hot conditions with flow were slower than the baseline times, possibly due to different flow conditions, but significantly less than technical specification limits. The nuclear signature measurement showed one change from the baseline, which appeared to originate outside the core.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6490021
• Report Number(s): LTR-111-108; TRN: 79-004030
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
PERFORMANCE TESTING
REACTOR CORES
CONTROL ROD WORTHS
FUEL ASSEMBLIES
LOSS OF COOLANT
NEUTRON FLUX
SIMULATION
ACCIDENTS
PWR TYPE REACTORS
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors