Modification of the MACCS consequence code

Conference · Wed Jan 01 04:00:00 EST 1992

OSTI ID:7146555

Miller, L A ^[1]; Chanin, D I ^[2]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Technadyne Engineering Consultants, Albuquerque, NM (United States)

This report discusses the MACCS code was originally developed under US Nuclear Regulatory Commission (USNRC) sponsorship to estimate the offsite consequences of potential severe accidents at nuclear power plants using meteorological data that varies on an hourly basis. The code models the transport and dispersion of plumes of radioactive material released from the facility to the atmosphere. Although MACCS was intended for nuclear power plant applications, it is now widely used at DOE facilities for safety assessments of a highly diverse nature. A principal limitation of the code in these applications is the set of radionuclides which may be considered. To assess consequences from non-reactor facilities (e.g., fusion and accelerator facilities) the MACCS code is currently undergoing development to expand its capabilities with the primary modification being the expansion of the radionuclide set to include short-lived fission products and activation products. With this improvement, MACCS will be capable of estimating the consequences from a large variety of facilities. In addition, a more sophisticated and flexible ingestion pathway model is being incorporated into the code.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 7146555
• Report Number(s): SAND-92-1725C; CONF-9208117--10; ON: DE92040269
• Country of Publication: United States
• Language: English

Related Subjects

054000 -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
DEPOSITION
EMERGENCY PLANS
ENVIRONMENTAL EXPOSURE PATHWAY
FISSION PRODUCT RELEASE
INGESTION
INHALATION
INTAKE
ISOTOPES
M CODES
MODIFICATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PLUMES
POWER PLANTS
PUBLIC HEALTH
RADIATION PROTECTION
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR ACCIDENTS
THERMAL POWER PLANTS