Effect of balance of plant and control system feedback on amplitude of power and flow oscillations
Conference
·
OSTI ID:6492269
The BNL Engineering Plant Analyzer (EPA) for BWR power plants predicts as amplitude of 1300% of full power for limit-cycle, core-wide power oscillations after postulated scram failure at the LaSalle-2 power plant. This is larger than the TRAC-G predictions by General Electric (GE) and the RETRAN predictions by the Electric Power Research Institute. Modeling and computing errors in the EPA are analyzed here as potential causes for EPA's over-predictions of peak fission power. It is concluded that the EPA is more likely to under-predict than to over-predict fission power peaks. It is found that the omission of dynamic BOP feedback effects from TRAC-G modeling and the premature termination of TRAC-G calculations account for most of TRAC-G's under-prediction of the fission power peaks. 7 refs., 9 figs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6492269
- Report Number(s):
- BNL-NUREG-45274; CONF-9010224--5; ON: DE91004012
- 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
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BOUNDARY CONDITIONS
BWR TYPE REACTORS
COMPUTER CODES
CONTROL SYSTEMS
ENERGY TRANSFER
EXCURSIONS
FEEDBACK
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
LA SALLE COUNTY-2 REACTOR
MATHEMATICAL MODELS
MECHANICS
OSCILLATIONS
POWER REACTORS
R CODES
REACTIVITY
REACTOR ACCIDENTS
REACTOR CONTROL SYSTEMS
REACTOR KINETICS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BOUNDARY CONDITIONS
BWR TYPE REACTORS
COMPUTER CODES
CONTROL SYSTEMS
ENERGY TRANSFER
EXCURSIONS
FEEDBACK
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
LA SALLE COUNTY-2 REACTOR
MATHEMATICAL MODELS
MECHANICS
OSCILLATIONS
POWER REACTORS
R CODES
REACTIVITY
REACTOR ACCIDENTS
REACTOR CONTROL SYSTEMS
REACTOR KINETICS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS