Importance of emergency response actions to reactor accidents within a probabilistic consequence assessment model
Conference
·
OSTI ID:464373
An uncertainty and sensitivity analysis of early health consequences of severe accidents at nuclear power plants as a function of the emergency response parameters has been performed using a probabilistic consequence assessment code. The importance of various emergency response parameters in predicting the consequences for a range of accident source terms was determined through training a neural network algorithm which relates the sensitivity of the output to various choices of the input. Extensions of this approach should be helpful to planners in prioritizing the emergency responses at nuclear power plants.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 464373
- Report Number(s):
- BNL-NUREG-63798; CONF-970419-6; ON: DE97003251; TRN: 97:009908
- Resource Relation:
- Conference: 6. American Nuclear Society (ANS) topical meeting on emergency preparedness and response, San Francisco, CA (United States), 22-25 Apr 1997; Other Information: PBD: [1997]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
NUCLEAR POWER PLANTS
REACTOR ACCIDENTS
HEALTH HAZARDS
EMERGENCY PLANS
SENSITIVITY ANALYSIS
REACTOR SAFETY
SOURCE TERMS
PROBABILITY
NEURAL NETWORKS
ALGORITHMS
PROBABILISTIC ESTIMATION
SAFETY ANALYSIS
M CODES
COMPUTER CALCULATIONS
FISSION PRODUCT RELEASE
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
EVACUATION
SHELTERS
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
NUCLEAR POWER PLANTS
REACTOR ACCIDENTS
HEALTH HAZARDS
EMERGENCY PLANS
SENSITIVITY ANALYSIS
REACTOR SAFETY
SOURCE TERMS
PROBABILITY
NEURAL NETWORKS
ALGORITHMS
PROBABILISTIC ESTIMATION
SAFETY ANALYSIS
M CODES
COMPUTER CALCULATIONS
FISSION PRODUCT RELEASE
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
EVACUATION
SHELTERS