Summary of uncertainty analysis of dispersion and deposition modules of the MACCS and COSYMA consequence codes: A joint USNRC/CEC study
Conference
·
OSTI ID:10102875
- Sandia National Labs., Albuquerque, NM (United States)
- Delft Univ. (Netherlands)
- Hawaii Univ., Hilo, HI (United States)
- Kernforschungszentrum Karlsruhe GmbH (Germany)
- Nuclear Regulatory Commission, Washington, DC (United States)
- Commission of the European Communities, Brussels (Belgium)
This paper briefly describes an ongoing project designed to assess the uncertainty in offsite radiological consequence calculations of hypothetical accidents in commercial nuclear power plants. This project is supported jointly by the Commission of European Communities (CEC) and the US Nuclear Regulatory Commission (USNRC). Both commissions have expressed an interest in assessing the uncertainty in consequence calculations used for risk assessments and regulatory purposes.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10102875
- Report Number(s):
- SAND--93-2383C; CONF-940312--30; ON: DE94001423; BR: GB0103012
- Country of Publication:
- United States
- Language:
- English
Similar Records
Probabilistic Accident Consequence Uncertainty - A Joint CEC/USNRC Study
Joint USNRC/EC consequence uncertainty study: The ingestion pathway, dosimetry and health effects expert judgment elicitations and results
Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 1: Main report
Conference
·
Wed Jul 28 00:00:00 EDT 1999
·
OSTI ID:9734
Joint USNRC/EC consequence uncertainty study: The ingestion pathway, dosimetry and health effects expert judgment elicitations and results
Conference
·
Thu Aug 01 00:00:00 EDT 1996
·
OSTI ID:270729
Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 1: Main report
Technical Report
·
Sun Jun 01 00:00:00 EDT 1997
·
OSTI ID:510290
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502
220900
99 GENERAL AND MISCELLANEOUS
990200
C CODES
COMPUTER CALCULATIONS
DATA COVARIANCES
FISSION PRODUCT RELEASE
M CODES
MATHEMATICS AND COMPUTERS
NUCLEAR POWER PLANTS
RADIATION EFFECTS
RADIOACTIVE EFFLUENTS
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT
220502
220900
99 GENERAL AND MISCELLANEOUS
990200
C CODES
COMPUTER CALCULATIONS
DATA COVARIANCES
FISSION PRODUCT RELEASE
M CODES
MATHEMATICS AND COMPUTERS
NUCLEAR POWER PLANTS
RADIATION EFFECTS
RADIOACTIVE EFFLUENTS
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT