U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 Page: 1-10
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(ref. 14). Recently a simplified method of dispersion cal-
culation has been proposed, by Pasquill15 and Meade,16 which
reflects recent dispersion field trials, as well as current
dispersion theories. This method gives the same numerical
results as the Sutton method in the present application to
a distance of about seven miles. Beyond this distance, the
new method predicts somewhat greater concentrations.
"6. The assumption is made that a shift in wind direc-
tion does not occur for the duration of the leakage of the
fission products from the containment barrier. If leakage
from the containment barrier is assumed to occur over a sig-
nificant time period (in the order of days), a reduction
factor of 2-50 could result from shifts in wind directions.
Wind meandering from any one centerline direction might also
result in a reduction factor of approximately 3.
"7. Atmospheric dispersion is assumed to occur under
inversion type weather conditions. For weather conditions
which exist for 75 percent or so of the time at most sites,
the atmospheric dispersion conditions could be more favor-
able, by factors of 5-1000.17
"8. Cloud depletion as ground deposition (particulate
fallout) is not assumed during cloud travel. Such deposi-
tion during cloud travel could reduce the low population
zone distance by factors of 2-5.
"9. In calculating the direct gamma dose, credit is
not taken for shielding by the containment structure and
applicable reactor shielding or topography. In some cases
it is recognized that such shielding could reduce the direct
gamma dose by a factor of 2-1000.
"10. Decay of fission products is assumed while they
are confined to the containment building but is not assumed
during their transit to the receptor point. The decay en-
route is not significant for the conditions of release con-
sidered here but would lower the calculated doses slightly
"11. In determining the whole body direct gamma dose,
only the external gamma dose due to the fission products
contained in the reactor building was considered signifi-
cant for the assumed conditions. The whole body direct
gamma dose due to the cloud passage for the assumed condi-
tions would contribute on the order of 1-10 percent of the
total whole body direct gamma dose at the exclusion and low
population zone distances.14"
The report4 explains that:
"...even if the postulated maximum credible accident should
occur and if the external containment shell remained intact,
the resulting exposure doses would probably be many times
lower than those calculated by the indicated method.
"On the other hand, there are potential, conceivable
conditions which would result in larger fission product re-
leases than those assumed to be released in the maximum
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Cottrell, William B. & Savolainen, A. W. U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1, report, August 1965; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc101033/m1/38/: accessed March 20, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.