RELAP5YA simulation of LOFT small-break experiments L3-6 and L5-1
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6941463
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-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
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Experiment data report for LOFT nuclear small break experiment L3-5/L3-5A
Conference
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Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5716789
Review and evaluation of the RELAP5YA computer code and the Vermont Yankee LOCA (Loss-of-Coolant Accident) licensing analysis model for use in small and large break BWR (Boiling Water Reactor) LOCAS
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Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6570634
Experiment data report for LOFT nuclear small break experiment L3-5/L3-5A
Technical Report
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Fri Oct 31 23:00:00 EST 1980
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OSTI ID:5320707
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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REACTOR COMPONENTS
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REACTOR CORES
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BENCHMARKS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
QUENCHING
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS