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RETRAN analysis of the turbine trip tests performed at the Peach Bottom Atomic Power Station Unit 2

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:6834003
;
A model based on the RETRAN code was developed for analyzing the turbine trip tests performed at the Peach Bottom Atomic Power Station Unit 2, near the end of the second fuel cycle. Special features of the model include a detailed nodal description of the steam lines and the steam bypass system as needed to properly describe pressure wave phenomena caused by stop valve closure during the early phase of the transient, and dynamic effects associated with operation of the bypass. Furthermore, it is shown that the power excursion, deliberately enhanced by delayed scram, is strongly influenced by the nature of the pressure wave as it appears in the core region and by direct moderator heating effects. Good agreement between measured transients and most calculated counterparts makes this effort an important contribution toward qualification of RETRAN for this class of transients.
Research Organization:
Oregon State University, Corvallis, Oregon
OSTI ID:
6834003
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 57:1; ISSN NUTYB
Country of Publication:
United States
Language:
English

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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
ACCURACY
ATWS
BWR TYPE REACTORS
BYPASSES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL EQUIPMENT
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
EXCURSIONS
FLOW REGULATORS
FLUID MECHANICS
HYDRODYNAMICS
MACHINERY
MATHEMATICAL MODELS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PEACH BOTTOM-2 REACTOR
PERFORMANCE TESTING
POWER PLANTS
POWER REACTORS
PRESSURE GRADIENTS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SIMULATION
STEAM LINES
STEAM SYSTEMS
STEAM TURBINES
SYSTEMS ANALYSIS
TEMPERATURE EFFECTS
TESTING
THERMAL POWER PLANTS
TRANSIENTS
TURBINES
TURBOMACHINERY
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS