Validation of RETRAN-03 by simulating a peach bottom turbine trip and boiloff at the full integral simulation test facility
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:6935417
- Computer Simulation and Analysis, Inc., Idaho Falls, ID (United States)
This paper reports that the RETRAN-03 computer code is validated by simulating two tests that were performed at the Full Integral Simulation Test (FIST) facility. The RETRAN-03 results of a turbine trip (test 4PTT1) and failure to maintain water level at decay power (test T1QUV) are compared with the FIST test data. The RETRAN-03 analysis of test 4PTT1 is compared with a previous TRAC-BWR analysis of the test. Sensitivity to various model nodalizations and RETRAN-03 slip options are studied by comparing results of test T1QUV. The predicted thermal-hydraulic responses of both tests agree well with the test data. The pressure response of test 4PTT1 and the boiloff rate for test T1QUV are accurately predicted. Core uncovery time is found to be sensitive to the upper downcomer and upper plenum nodalization. The RETRAN-03 algebraic and dynamic slip options produce similar results for test T1QUV.
- OSTI ID:
- 6935417
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 100; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
220400 -- Nuclear Reactor Technology-- Control Systems
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCURACY
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EQUIPMENT
EVALUATION
FAILURES
HEAT TRANSFER
HYDROGEN COMPOUNDS
MACHINERY
OXYGEN COMPOUNDS
POWER REACTORS
R CODES
REACTORS
SIMULATION
TEST FACILITIES
TESTING
THERMAL REACTORS
TURBINES
TURBOMACHINERY
VALIDATION
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
220400 -- Nuclear Reactor Technology-- Control Systems
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCURACY
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EQUIPMENT
EVALUATION
FAILURES
HEAT TRANSFER
HYDROGEN COMPOUNDS
MACHINERY
OXYGEN COMPOUNDS
POWER REACTORS
R CODES
REACTORS
SIMULATION
TEST FACILITIES
TESTING
THERMAL REACTORS
TURBINES
TURBOMACHINERY
VALIDATION
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS