Quantification and uncertainty analysis of source terms for severe accidents in light water reactors (QUASAR). Part 1: methodology and program plan. Volume 1
Technical Report
·
OSTI ID:5358074
The methodological framework and program plan for systematic quantification and propagation of uncertainties in radiological source terms for light water reactors are presented. The QUASAR methodology is based on detailed sensitivity analysis of the Source Term Code Package (STCP), followed by a systematic uncertainty analysis on the most sensitive parameters/variables, and phenomenological issues related to prediction of radiological releases to the environment.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA). Accident Analysis Group
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5358074
- Report Number(s):
- NUREG/CR-4688-Vol.1; BNL-NUREG-52008-Vol.1; ON: TI86015106
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
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BWR TYPE REACTORS
REACTOR ACCIDENTS
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EMERGENCY PLANS
REACTOR CORE DISRUPTION
SENSITIVITY ANALYSIS
ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
PWR TYPE REACTORS
EMERGENCY PLANS
REACTOR CORE DISRUPTION
SENSITIVITY ANALYSIS
ACCIDENTS
REACTORS
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