Documentation for RISKIN: A risk integration code for MACCS (MELCOR Accident Consequence Code System) output
- GRAM, Inc., Albuquerque, NM (USA)
- Argonne National Lab., IL (USA)
This document has been prepared as a user's guide for the computer program RISKIN developed at Sandia National Laboratories. The RISKIN code generates integrated risk tables and the weighted mean risk associated with a user-selected set of consequences from up to five output files generated by the MELCOR Accident Consequence Code System (MACCS). Each MACCS output file can summarize the health and economic consequences resulting from up to 60 distinct severe accident source terms. Since the accident frequency associated with these source terms is not included as a MACCS input parameter a postprocessor is required to derived results that must incorporate accident frequency. The RISKIN code is such a postprocessor. RISKIN will search the MACCS output files for the mean and peak consequence values and the complementary cumulative distributive function (CCDF) tables for each requested consequence. Once obtained, RISKIN combines this data with accident frequency data to produce frequency weighted results. A postprocessor provides RISKIN an interface to the proprietary DISSPLA plot package. The RISKIN code has been written using ANSI Standard FORTRAN 77 to maximize its portability.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- DOE/EH
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6187859
- Report Number(s):
- SAND-90-7022; ON: DE91006435
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
DISTRIBUTION FUNCTIONS
DOCUMENT TYPES
ENVIRONMENTAL IMPACTS
FORTRAN
FUNCTIONS
MANUALS
PROGRAMMING LANGUAGES
R CODES
REACTOR ACCIDENTS
RISK ASSESSMENT
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
DISTRIBUTION FUNCTIONS
DOCUMENT TYPES
ENVIRONMENTAL IMPACTS
FORTRAN
FUNCTIONS
MANUALS
PROGRAMMING LANGUAGES
R CODES
REACTOR ACCIDENTS
RISK ASSESSMENT