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Table II. Fraction of radioactive material released and respirable.
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DOE Standard Accident Analysis For Aircraft Crash Into Hazardous Facilities
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Radioactive Material Onsite Exposure Determination


DOE-STD-3014-96
Radioactive Material Offsite Exposure Determination. The exposure to
7.2.3.2
the maximally exposed individual at or beyond the site boundary will be
estimated in terms consistent with the screening guidelines presented in
Section 4.1. For radioactive material releases, Reference 3 contains a
series of nomographs for common radioactive materials that provide dose
estimates under various conditions relevant to aircraft crash scenarios.
These nomographs may be used to provide a screening value for the site
boundary dose for the materials and conditions specified. Using the
nomographs to calculate doses should account for the additive property
of dose over all isotopes of concern, so that isotopes are evaluated
cumulatively, as opposed to individually, against guidelines. If a particular
facility has materials or conditions not covered by the nomographs
provided, the simple Gaussian dispersion equation that was used to
develop the nomographs will be used to estimate the dose at the site
boundary, using the shortest distance to the site boundary as the
evaluation point and an atmospheric stability of F, with a wind speed of
2 m/s, as explained in Reference 8. For releases that are potentially
buoyant, the buoyancy will be ignored for the purposes of screening
calculations. The centerline dose can be estimated using the following
equation:
n
Qi
SAi
CEDEi
BR
Dose
(7-1)
u
i 1
y
z
where:
Dose
=
dose (sievert [rem]) - CEDE;
Q
=
material released and respirable (i.e., source term) (g);
SA
=
specific activity (Curies/gram [Ci/g], [Bq/g] );
CEDE =
committed effective dose equivalent (rem/Ci [Sv/Bq]
inhaled assuming a 1-Ám activity median aerodynamic
diameter particle size);
breathing rate (3E-4 m3/s);
BR =
83


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