RELAP5YA simulation of LOFT small-break experiments L3-6 and L5-1
The loss-of-fluid test (LOFT) small-break tests were simulated using the RELAP5YA computer code at Yankee Atomic Electric Company (YAEC) as part of the integral code assessment program. RELAP5YA was developed at YAEC from RELAP5/MOD1 to provide a method for licensing analysis for small-break loss-of-coolant accidents (SBLOCAs) in pressurized water reactors (PWRs). The LOFT facility is a 50-MW(thermal) volumetrically scaled PWR that has been designed to simulate the significant thermal-hydraulic events expected in a commercial PWR during postulated LOCAs. The tests selected for this assessment were LOFT tests L3-6/L8-1 and L5-1. The present RELAP5YA model of the LOFT facility consists of 99 volumes, 105 junctions, and 59 heat slabs and includes all the necessary components (e.g., pumps and valves) and control systems (e.g., trip logic and pressure regulating valves) to provide an accurate simulation of the test sequence. These comparisons of the calculated and measured data for the LOFT small-break tests indicate that RELAP5YA generally matched important safety-related phenomena, such as system depressurization, primary coolant mass inventory, and core heatup and quench. The benchmarking results are currently being employed at YAEC to direct RELAP5YA modeling improvements for PWR SBLOCA applications.
- OSTI ID:
- 6941463
- Report Number(s):
- CONF-8711195-; TRN: 88-032076
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
REACTOR SAFETY EXPERIMENTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
R CODES
PWR TYPE REACTORS
BENCHMARKS
PRIMARY COOLANT CIRCUITS
QUENCHING
REACTOR ACCIDENTS
REACTOR CORES
REACTOR SAFETY
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
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FLUID MECHANICS
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REACTOR COOLING SYSTEMS
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RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled