RELAP5YA simulation of large-break tests in the two-loop test apparatus
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5534955
The RELAP5YA computer code has been used to simulate two tests on the two-loop test apparatus (TLTA): 6426/1 and 6425/2. The TLTA is a scaled version of a boiling water reactor (BWR). TLTA 6426/1 simulates a double-ended guillotine loss-of-coolant accident (LOCA) in the recirculation line without emergency core cooling (ECC). TLTA 6425/2 is similar except that all ECC systems are operational. RELAP5YA was developed at Yankee Atomic Electric Co. from RELAP5/MOD1 to provide a conservative method for licensing analyses that would also simulate LOCA phenomena in a qualitatively correct manner. Major features distinguishing RELAP5YA from RELAP5/MOD1 include a jet pump component model and constitutive models for interphase drag, critical heat flux, rewet and quench phenomena, and multiple-surface radiation heat transfer. In addition, RELAP5YA contains evaluation model features suitable for performing licensing analyses of light water reactors that conform to regulatory requirements. These evaluation model features have not been used in the present calculations.
- OSTI ID:
- 5534955
- Report Number(s):
- CONF-870601-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 54
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5YA simulation of TLTA small-break tests with degraded ECCS
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
RELAP5YA simulation of LOFT small-break experiments L3-6 and L5-1
Conference
·
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
Technical Report
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6570634
RELAP5YA simulation of LOFT small-break experiments L3-6 and L5-1
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6941463
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
CRITICAL HEAT FLUX
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FAILURES
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PIPES
R CODES
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
RUPTURES
SAFETY
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
CRITICAL HEAT FLUX
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FAILURES
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PIPES
R CODES
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
RUPTURES
SAFETY
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS