Quantification and uncertainty analysis of source terms for severe accidents in light water reactors (QUASAR): Part 2, Sensitivity analysis techniques
Technical Report
·
OSTI ID:5578897
Existing methods for sensitivity analysis are described and new techniques are proposed. These techniques are evaluated through consideration relative to the QUASAR program. Merits and limitations of the various approaches are examined by a detailed application to the Suppression Pool Aerosol Removal Code (SPARC). 17 refs., 7 figs., 12 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5578897
- Report Number(s):
- NUREG/CR-4688-Vol.2; BNL-NUREG-52008-Vol.2; ON: TI88005035; TRN: 88-009905
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
SOURCE TERMS
PWR TYPE REACTORS
S CODES
AEROSOLS
REACTOR ACCIDENTS
REACTOR SAFETY
STATISTICS
ACCIDENTS
COLLOIDS
COMPUTER CODES
DISPERSIONS
MATHEMATICS
REACTORS
SAFETY
SOLS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled