MELCOR Accident Consequence Code System (MACCS)
- Sandia National Labs., Albuquerque, NM (USA)
- GRAM, Inc., Albuquerque, NM (USA)
- Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA)
This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previously used CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projection, dose accumulation by a number of pathways including food and water ingestion, early and latent health effects, and economic costs. The MACCS code can be used for a variety of applications. These include (1) probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, (2) sensitivity studies to gain a better understanding of the parameters important to PRA, and (3) cost-benefit analysis. This report is composed of three volumes. Volume I, the User's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems. Volume II, the Model Description, describes the underlying models that are implemented in the code, and Volume III, the Programmer's Reference Manual, describes the code's structure and database management. 59 refs., 14 figs., 15 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7247757
- Report Number(s):
- NUREG/CR-4691-Vol.2; SAND--86-1562-Vol.2; ON: TI90008262
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
AGRICULTURE
AIR QUALITY
BIOCHEMISTRY
BWR TYPE REACTORS
C CODES
CHEMISTRY
COMPUTER CODES
COMPUTERIZED SIMULATION
DATA BASE MANAGEMENT
EARTH ATMOSPHERE
ECOLOGICAL CONCENTRATION
ECONOMICS
ENVIRONMENTAL EFFECTS
ENVIRONMENTAL EXPOSURE PATHWAY
ENVIRONMENTAL QUALITY
ENVIRONMENTAL TRANSPORT
FORTRAN
FUNCTIONS
GAUSS FUNCTION
HAZARDS
HEALTH HAZARDS
INDUSTRY
M CODES
MANAGEMENT
MASS TRANSFER
MATHEMATICAL MODELS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PLANTS
POWER PLANTS
PROGRAMMING LANGUAGES
PWR TYPE REACTORS
RADIATION PROTECTION
RADIATION TRANSPORT
RADIOECOLOGICAL CONCENTRATION
RADIONUCLIDE MIGRATION
REACTOR ACCIDENTS
REACTORS
RISK ASSESSMENT
SAMPLING
SIMULATION
STATISTICAL MODELS
THERMAL POWER PLANTS
U CODES
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATER QUALITY
WEATHER