Uncertainty and sensitivity analysis of early exposure results with the MACCS Reactor Accident Consequence Model
Creators
- 1. Arizona State Univ., Tempe, AZ (United States)
- 2. GRAM, Inc., Albuquerque, NM (United States)
- 3. Los Alamos National Lab., NM (United States)
- 4. Sandia National Labs., Albuquerque, NM (United States)
Description
Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the early health effects associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 34 imprecisely known input variables on the following reactor accident consequences are studied: number of early fatalities, number of cases of prodromal vomiting, population dose within 10 mi of the reactor, population dose within 1000 mi of the reactor, individual early fatality probability within 1 mi of the reactor, and maximum early fatality distance. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: scaling factor for horizontal dispersion, dry deposition velocity, inhalation protection factor for nonevacuees, groundshine shielding factor for nonevacuees, early fatality hazard function alpha value for bone marrow exposure, and scaling factor for vertical dispersion
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI95006186; NTIS (documentation only); ESTSC (complete software package), P.O. Box 1020, Oak Ridge, TN 37831-1020 (United States); GPO.Files
26040717.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 135 p.
- Report number
- NUREG/CR--6135
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26040717
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- BIOSPHERE; COMPUTERIZED SIMULATION; FISSION PRODUCT RELEASE; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; SIMULATION; THERMAL POWER PLANTS
Optional Information
- Contract/Grant/Project number
- Contract AC04-94AL85000
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- SAND--93-2371.