Benchmarking of LOFT LRTS-COBRA-FRAP safety analysis model

Conference · Sat May 01 00:00:00 EDT 1982

OSTI ID:6546029

Hanson, G H; Atkinson, S A; Wadkins, R P

The purpose of this work was to check out the LOFT LRTS/COBRA-IV/FRAP-T5 safety-analysis models against test data obtained during a LOFT operational transient in which there was a power and fuel-temperature rise. LOFT Experiment L6-3 was an excessive-load-increase anticipated transient test in which the main steam-flow-control valve was driven from its operational position to full-open in seven seconds. The resulting cooldown and reactivity-increase transients provide a good benchmark for the reactivity-and-power-prediction capability of the LRTS calculations, and for the fuel-bundle and fuel-rod temperature-response analysis capability of the LOFT COBRA-IV and FRAP-T5 models.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6546029
• Report Number(s): EGG-M-12982; CONF-821103-61; ON: DE83005337
• Resource Relation: Conference: American Nuclear Society winter meeting, Washington, DC, USA, 14 Nov 1982; Other Information: Microfiche only, copy does not permit paper copy reproduction
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
REACTOR ACCIDENTS
COMPUTER CALCULATIONS
FUEL ASSEMBLIES
FUEL CANS
FUEL RODS
PRIMARY COOLANT CIRCUITS
REACTOR SAFETY
SECONDARY COOLANT CIRCUITS
TEMPERATURE GRADIENTS
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
FUEL ELEMENTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors