1. NAME AND TITLE
FONTA: Code System For Calculating Individual And Collective Doses From Reactor
Accidents Using Pasquill's Plume Model.
AUXILIARY ROUTINES
The CORE inventory for FONTA can be determined using the CCC-271/ORIGEN code package.
2. CONTRIBUTOR
Research Association for Atomic Energy, Inc., Vienna, Austria.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; Siemens 4004, BS 2000.
4. NATURE OF PROBLEM SOLVED.
FONTA calculates the radiological consequences of accidental releases of radioactive substances
into the atmosphere. The doses to seven organs may be evaluated summing up the doses due to
immersion, inhalation, and irradiation by deposits. Contributions of 54 isotopes may be taken into
consideration for the evaluation of individual and collective doses.
5. METHOD OF SOLUTION
The calculation method is based on Pasquill's plume model which is modified by some corrections
such as plume rise effect, building wake effect, and the effects of wet and dry deposition. The local
dependency of the doses is taken into account by subdividing the sector covered by the plume into ring
segments at the centers of which are located the test points for the dose calculation.
6. RESTRICTIONS OR LIMITATIONS
FONTA is dimensioned for a maximum of 54 isotopes and 30 ring segments.
7. TYPICAL RUNNING TIME
No study has been made by RSIC of typical running times for FONTA.
8. COMPUTER HARDWARE REQUIREMENTS
FONTA is operable on the Siemens 4004.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required. FINSIM from the Siemens Subroutine Package SSPLIB is
required for the numerical integration.
10. REFERENCE
F. Woloch and G. Kamelander, "FONTA, A Program for Calculating the Radiological
Consequences of Radioactive Releases Due to Hypothetical Accidents in Nuclear Power Plants," RS-116/77 (September 1977).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
code and sample problem input.
12. DATE OF ABSTRACT
April 1982; reviewed June 1982.
KEYWORDS: AIRBORNE; ENVIRONMENTAL DOSE; FISSION PRODUCTS; GAUSSIAN PLUME MODEL; INTERNAL DOSE; RADIOACTIVITY RELEASE; REACTOR ACCIDENT