1. NAME AND TITLE
ACRA-TRIT: The Tritium Version of ACRA-II, Estimation of Radiation Doses Caused by a
Hypothetical Reactor Accident.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
3. CODING LANGUAGE AND COMPUTER
FORTRAN IV; IBM 360/370.
4. NATURE OF PROBLEM SOLVED
ACRA-TRIT is an atmospheric dispersion code which, using a three- (or two-) dimensional
normal distribution model calculates the external dose, the internal dose due to inhalation, and the
ground contamination that can be expected from the transport, fallout, and washout of the
radioactive products released to the atmosphere in either a continuous fashion or an accidental
short-term release. Allowance is made for elevated receptors above ground, for variable height of
the plume centerline, and for reflection on the ground and on a possible inversion layer in the
5. METHOD OF SOLUTION
ACRA-TRIT prints out integrated doses over time as in CCC-213/ACRA-II.
It can produce concentrations instead of internal doses. This allows (a) studying the variation of the activity concentration of each radioisotope with time at a maximum of a hundred receptor locations, and (b) calculating the equilibrium concentration, for continuous releases, as a function of distance from the source.
Given the wind-rose statistical data of winds and atmospheric conditions, year averaged external and internal doses and ground contamination can be computed over a circle around the point of release.
ACRA-TRIT has a tritium oxidation modeling capability that allows a more realistic evaluation
of the environmental impact of future fuel reprocessing plants and nuclear fusion power reactors.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
An ACRA-TRIT case was run in 11 seconds on the IBM 360/91.
8. COMPUTER HARDWARE REQUIREMENTS
When run on an IBM 360/370, using standard I-O, ACRA-TRIT requires 500 K bytes core
9. COMPUTER SOFTWARE REQUIREMENTS
A FORTRAN IV compiler is required.
Subroutine SETUP requires 350 K bytes to compile.
P. J. Otaduy, "Tritium Oxidation and Dispersion Model," (February 1976).
F. W. Stallmann and F. B. K. Kam, "ACRAA Computer Program for the Estimation of Radiation Doses Caused by a Hypothetical Reactor Accident," ORNL-TM-4082 (April 1973).
F. B. K. Kam, "Informal Notes" (April 1974).
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 and output.
12. DATE OF ABSTRACT
December 1981; reviewed March 1982.
KEYWORDS: KERNEL; GAMMA-RAY; AIRBORNE; AIR-GROUND INTERFACE; ENVIRONMENTAL DOSE