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Here you go Dave:
Sandy Perle
Supervisor Health Physics
Florida Power and Light Company
Nuclear Division
(407) 694-4219 Office
(407) 694-3706 Fax
sandy_perle@email.fpl.com
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RSIC CODE PACKAGE CCC-398
1. NAME AND TITLE
MILDOS: Calculation of Radiation Doses from Uranium Recovery
Operations.
2. CONTRIBUTORS
U.S. Nuclear Regulatory Commission, Washington, D. C.
Pacific Northwest Laboratory, Richland, Washington.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; CDC.
4. NATURE OF PROBLEM SOLVED
MILDOS estimates impacts from radioactive emissions from uranium
milling facilities. These impacts are presented as dose commitments to
individuals and the
regional population within an 80 km radius of the facility. Only
airborne releases of radioactive materials are considered: releases to
surface water and to groundwater
are not addressed in MILDOS. This is a multi-purpose code system,
within the range of its proper application, and can be used to
evaluate population doses for NEPA
assessments, maximum individual doses for predictive 40 CFR 190
compliance evaluations, or maximum offsite air concentrations for
predictive evaluations of 10
CFR 20 compliance.
The MILDOS package includes models for both point sources (stacks,
vents) and area sources (ore pads, tailings areas). Gaseous releases
are limited to consideration
of 222Rn plus ingrowth of daughters. Exposure pathways of concern are
assumed to be inhalation of airborne radioactive material, ingestion
of vegetables, meat, and
milk contaminated via deposition, and external exposure to radiation
emitted by airborne activity and activity deposited on ground
surfaces. Liquid exposure
pathways are not treated by MILDOS.
5. METHOD OF SOLUTION
Emissions of radioactive materials from fixed point source locations
and from area sources are modeled using a sector-averaged Gaussian
plume dispersion model
which utilizes user-provided wind frequency data. Mechanisms such as
deposition of particulates, resuspension, radioactive decay and
ingrowth of daughter
radionuclides are included in the transport model. Annual average air
concentrations are computed, from which subsequent impacts to humans
through various
pathways are computed. Ground surface concentrations are estimated
from deposition buildup and ingrowth of radioactive daughters. The
surface concentrations are
modified by radioactive decay, weathering, and other environmental
processes. MILDOS allows the user to vary the emission sources as a
step function of time by
adjusting the emission rates; this can include shutting them off
completely. Thus, the results of a computer run can be made to reflect
changing processes throughout
the facility's operational lifetime.
6. RESTRICTIONS OR LIMITATIONS
A maximum of 20 sources can be used in a single run.
7. TYPICAL RUNNING TIME
No study has been made by RSIC of typical running times for MILDOS.
8. COMPUTER HARDWARE REQUIREMENTS
MILDOS is operable on the CDC computers.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
10. REFERENCES
Giorgio Gnugnoli, Suggested Revision in the use of the MILDOS Code,
Memorandum (October 1980).
Giorgio N. Gnugnoli and Dan E. Martin, ``MILDOS Computer Code User's
Manual,'' Preliminary document (May 1980).
D. L. Strenge and T. J. Bander, MILDOS A Computer Program for
Calculating Environmental Radiation Doses from Uranium Recovery
Operations,
NUREG/CR-2011/PNL-3767 (April 1981).
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents and a reel of magnetic tape
which contains the source code and sample problem input written in
EBCDIC card images; total
records 2780.
12. DATE OF ABSTRACT
February 1982; revised February 1983.
KEYWORDS: ENVIRONMENTAL DOSE; RADIOACTIVITY; AIRBORNE; INTERNAL DOSE;
AIR-GROUND