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Title: MACCS1. 5

Abstract

MACCS1.5 performs probabilistic calculations of potential off site consequences of the atmospheric releases of radioactive material in reactor accidents. The principal phenomena considered in MACCS are atmospheric transport, environmental contamination, emergency response, long term 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. MACCS can be used for a variety of applications including probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, sensitivity studies to gain a better understanding of the parameters important to PRA, and cost benefit analysis. The time scale after the accident is divided into three phases: emergency, intermediate, and long term. The region surrounding the reactor is divided into a polar-coordinate grid, with the reactor located at the center, for the calculations. Two preprocessors, MAXGC and DOSFAC, are included. MAXGC generates the maximum allowable ground concentrations based on protective action guide (PAG) dose levels. DOSFAC generates the dose conversion data used by MACCS.

Authors:
 [1]
  1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
Publication Date:
Research Org.:
International Atomic Energy Agency, Vienna (Austria)
Sponsoring Org.:
NRC/RES; Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
OSTI Identifier:
5359243
Report Number(s):
ESTSC/NRC-000002IB38600; NESC-722; CCC-546
Resource Type:
Miscellaneous
Resource Relation:
Other Information: MACCS1.5 calls three DEC VMS-system subroutines to obtain the current date, time of day, and elapsed CPU time. These calls will have to be modified appropriately for use on other computer systems
Country of Publication:
United States
Language:
English
Subject:
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; 22 GENERAL STUDIES OF NUCLEAR REACTORS; M CODES; REACTOR ACCIDENTS; RISK ASSESSMENT; C CODES; COMPUTER PROGRAM DOCUMENTATION; D CODES; DIFFUSION; EVALUATION; SOURCE TERMS; ACCIDENTS; COMPUTER CODES; 990200* - Mathematics & Computers; 220900 - Nuclear Reactor Technology- Reactor Safety; 220500 - Nuclear Reactor Technology- Environmental Aspects

Citation Formats

Jones, K R. MACCS1. 5. United States: N. p., 1991. Web.
Jones, K R. MACCS1. 5. United States.
Jones, K R. Fri . "MACCS1. 5". United States.
@article{osti_5359243,
title = {MACCS1. 5},
author = {Jones, K R},
abstractNote = {MACCS1.5 performs probabilistic calculations of potential off site consequences of the atmospheric releases of radioactive material in reactor accidents. The principal phenomena considered in MACCS are atmospheric transport, environmental contamination, emergency response, long term 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. MACCS can be used for a variety of applications including probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, sensitivity studies to gain a better understanding of the parameters important to PRA, and cost benefit analysis. The time scale after the accident is divided into three phases: emergency, intermediate, and long term. The region surrounding the reactor is divided into a polar-coordinate grid, with the reactor located at the center, for the calculations. Two preprocessors, MAXGC and DOSFAC, are included. MAXGC generates the maximum allowable ground concentrations based on protective action guide (PAG) dose levels. DOSFAC generates the dose conversion data used by MACCS.},
doi = {},
url = {https://www.osti.gov/biblio/5359243}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1991},
month = {3}
}

Miscellaneous:
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