Davis-Besse uncertainty study
The uncertainties of calculations of loss-of-feedwater transients at Davis-Besse Unit 1 were determined to address concerns of the US Nuclear Regulatory Commission relative to the effectiveness of feed and bleed cooling. Davis-Besse Unit 1 is a pressurized water reactor of the raised-loop Babcock and Wilcox design. A detailed, quality-assured RELAP5/MOD2 model of Davis-Besse was developed at the Idaho National Engineering Laboratory. The model was used to perform an analysis of the loss-of-feedwater transient that occurred at Davis-Besse on June 9, 1985. A loss-of-feedwater transient followed by feed and bleed cooling was also calculated. The evaluation of uncertainty was based on the comparisons of calculations and data, comparisons of different calculations of the same transient, sensitivity calculations, and the propagation of the estimated uncertainty in initial and boundary conditions to the final calculated results.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor and Plant Systems
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6243997
- Report Number(s):
- NUREG/CR-4946; EGG-2510; ON: DE87013628
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
DATA COVARIANCES
DAVIS BESSE-1 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
LOSS OF FLOW
MECHANICS
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL REACTORS
TRANSIENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
DATA COVARIANCES
DAVIS BESSE-1 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
LOSS OF FLOW
MECHANICS
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL REACTORS
TRANSIENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS