1. NAME AND TITLE
SMART: Code System for Calculating Early Offsite Consequences from Nuclear Reactor Accidents.
Brookhaven National Laboratory, Long Island, New York under sponsorship of the U.S. Nuclear Regulatory Commission.
3. CODING LANGUAGE AND COMPUTER
FORTRAN 77; IBM PC.
4. NATURE OF PROBLEM SOLVED
SMART calculates early offsite consequences from nuclear reactor accidents. Once the air and ground concentrations of the radionuclide are estimated, the early dose to an individual is calculated via three pathways: cloudshine, short-term groundshine, and inhalation.
5. METHOD OF SOLUTION
The model predicts time-integrated air concentration of each radionuclide at any location from release as a function of time-integrated source strength using the Gaussian profile or, optionally, as an average over the cross-section based on a top-hat distribution.
The solution procedure uses simplified meteorology and involves direct analytic integration of air concentration equations over time and position. Dispersion parameters are calculated from exponential fits to the Pasquill-Gifford curves for six atmospheric stability classes designated A to F.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
SMART is an interactive code, and the sample problem runs in a few seconds.
8. COMPUTER HARDWARE REQUIREMENTS
SMART runs on IBM PC or compatible computers under DOS and VAX mainframe computers running VMS.
9. COMPUTER SOFTWARE REQUIREMENTS
The code was written in FORTRAN 77 and was tested at RSIC using the Microsoft Version 4.01 compiler. The IBM PROFORT compiler was used to create the executable file included in the package.
I. K. Madni, E. G. Cazzoli and M. Khatib-Rahbar, "A Simplified Model for Calculating Early Offsite Consequences from Nuclear Reactor Accidents," NUREG/CR-5164, BNL-NUREG-52153 (July 1988).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and a 5.25 inch DS/HD (1.2 MB) diskette which includes source codes, data files, output and an executable file.
12. DATE OF ABSTRACT
KEYWORDS: AIRBORNE; ENVIRONMENTAL DOSE; INTERACTIVE; MICROCOMPUTER; REACTOR ACCIDENT; GAUSSIAN PLUME MODEL; INTERNAL DOSE; NUCLIDE TRANSPORT