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Title: MACCS1.5; Reactor Accident Consequence Code

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. Sandia National Labs., Albuquerque, NM (United States)
Publication Date:
Research Org.:
Idaho National Engineering Lab., Idaho Falls, ID (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
OSTI Identifier:
139338
Report Number(s):
ESTSC/NRC-000002D622000; NESC-722; CCC-546
Resource Type:
Technical Report
Resource Relation:
Other Information: DN: MACCS1.5 calls three DEC VMS system subroutines to obtain the current date, time of day, and elapsed CPU time.; PBD: 1 Feb 1990
Country of Publication:
United States
Language:
English
Subject:
99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; 22 NUCLEAR REACTOR TECHNOLOGY; 54 ENVIRONMENTAL SCIENCES; M CODES; REACTOR ACCIDENTS; RISK ASSESSMENT; C CODES; D CODES; SOURCE TERMS; DIFFUSION; COMPUTER PROGRAM DOCUMENTATION

Citation Formats

Chanin, D I, and Cranwell, R M. MACCS1.5; Reactor Accident Consequence Code. United States: N. p., 1990. Web.
Chanin, D I, & Cranwell, R M. MACCS1.5; Reactor Accident Consequence Code. United States.
Chanin, D I, and Cranwell, R M. Thu . "MACCS1.5; Reactor Accident Consequence Code". United States.
@article{osti_139338,
title = {MACCS1.5; Reactor Accident Consequence Code},
author = {Chanin, D I and Cranwell, R M},
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/139338}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {2}
}

Technical Report:
Other availability
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