1. NAME AND TITLE
EFDOS: Calculation of Effective Committed Dose Equivalents by Inhalation of Radioactive
Materials Occurring in Routine Atmospheric Releases from Nuclear Fuel Cycle
Power Reactor & Nuclear Fuel Development Corporation, Tokai Works, Tokai-mura, Ibaraki-ken,
3. CODING LANGUAGE AND COMPUTER
Fortran IV; IBM 370/3033.
4. NATURE OF PROBLEM SOLVED
EFDOS calculates internal exposure due to the inhalation of radioactive materials occurring in
routine atmospheric releases from nuclear fuel cycle facilities.
5. METHOD OF SOLUTION
The atmospheric dispersion of radioactive materials is calculated by the Gaussian type diffusion (dispersion) equation based on the supposition that the spatial density distributions of radioactive materials are represented by the Gaussian distribution both horizontally and vertically. The calculation is based on the method shown in the report ``Concerning the Weather Guide with Respect to the Safety Analysis in Facilities of Atomic Power Plant,'' Atomic Energy Commission of Japan (June 14, 1977). In addition to the corrections for the decrease of density in the air due to gravitational settling, dry deposition, precipitation scavenging, and radiological decay are carried out referring to the method used in the AIRDOS-EPA code.
The calculation of internal exposure due to inhalation is based on the ICRP Publication 30,
Supplements, and determines the committed dose equivalent for separate target organs and the effective
committed dose equivalent.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
CPU time for a calculation using meteorological data for one year with a condition of 1 nucleus,
16 angles, and 10 distances is about 2 seconds on the IBM 3033.
8. COMPUTER HARDWARE REQUIREMENTS
EFDOS is operable on the IBM 370/3033 computers.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran G compiler is required.
a. Included in package:
Y. Kitahara and K. Shinohara, "EFDOS A Computer Program for Calculating Effective
Committed Dose Equivalents by Inhalation of Radioactive Materials Occurring in Routine Atmospheric
Releases from Nuclear Fuel Cycle Facilities," PNC N843-81-04 (January 1981).
b. Background information:
Atomic Energy Commission of Japan, "The Meteorological Guide with Respect to Safety Analysis of Atomic Reactor Facilities for Power Generation" (June 14, 1977).
R. E. Moore et al., "AIRDOS-EPA: A Computerized Methodology for Estimating Environmental Concentrations and Dose to Man from Airborne Releases of Radionuclides," ORNL-5532 (1979).
ICRP Publication 30, Supplement to Part 1: "Limits for Intakes of Radionuclides by Workers"
(1979); Supplement to Part 2 (1981).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document (10.a) and one (1.2MB) DOS diskette which contains the
source code and sample problem input and output.
12. DATE OF ABSTRACT
February 1982; revised February 1983.
KEYWORDS: INTERNAL DOSE; AIRBORNE; AIR TRANSPORT; GAUSSIAN PLUME MODEL; ENVIRONMENTAL DOSE