1. NAME AND TITLE
AISITE II: Reactor Siting Code System.
2. CONTRIBUTOR
Atomics International, Canoga Park, California, via National Energy Software Center,
Argonne National Laboratory, Argonne, Illinois.
3. CODING LANGUAGE AND COMPUTER
FORTRAN IV; IBM 360/370 with graphical display device.
4. NATURE OF PROBLEM SOLVED
AISITE II is a reactor siting code written to provide a tool for parametric investigation of reactor siting. It automatically varies any one of 46 parameters such as reactor power, building leak rate, iodine clean-up rate, and halogen filter efficiency, computing the exclusion area, and low population boundary zones as functions of that parameter.
The printed edit consists of the dose versus distance data, fractional contribution by isotope group to the inhalation dose, and critical distances for both a 2-hour and a 30-day release. Graphical displays can be obtained for critical distances as a function of the variable parameter and dose versus distance for any organ or the critical organ, for each value of the parameter.
Three models are available for fission product release with up to 4 levels of containment.
5. METHOD OF SOLUTION
AISITE II evaluates analytic solutions to differential equations.
Features of the code include built-in libraries of isotope decay constants, average gamma-ray
energies, yields, absorption coefficients in air, mass of organs, etc. Addressable data are used so
that multiple cases can be run where only changes are specified. Programming is modular so that
models are easily replaced when necessary.
6. RESTRICTIONS OR LIMITATIONS
100 isotopes
20 distances
10 values of variable parameter
8 organs
4 levels of containment
7. TYPICAL RUNNING TIME
One case with 10 distances and 10 values of the variable parameter requires about 20 seconds
for both printed and graphical output.
8. COMPUTER HARDWARE REQUIREMENTS
An IBM 360/370 computer is required.
9. COMPUTER SOFTWARE REQUIREMENTS
A FORTRAN IV compiler is required.
10. REFERENCES
R. A. Blaine and E. L. Bramblett, "AISITE II: A Digital Computer Program for Investigation of Reactor Siting," NAA-SR-9982 (October 1964).
M. Hoffman and W. A. Rhoades, "AICRT3: A General Code for Display of Digital Data,"
NAA-SR-MEMO-9069 (October 1963).
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents and one (1.2MB) DOS diskette which contains the
source code and sample problem input, plus output from the sample problem.
12. DATE OF ABSTRACT
December 1981.
KEYWORDS: FISSION PRODUCT INVENTORY; ISOTOPE INVENTORY; ENVIRONMENTAL DOSE