Reactor Room Experimental SF6 Tests to Determine Probable Stack Activity Response to Radioactive Releases Page: 3 of 15
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conclusion from these results is that a simple model can
adequately represent a puff release to obtain data useful for
emergency response within a few (less than 10) minutes, Further-
more, the mathematical model, as currently programmed to perform
these estimates, should be revised to provide more accuracy. This
revision consists of assuming a response curve of a chi-squared
diutribution with three degree of freedom.
DI SC IO
A series of testal were performed in L-Area in late February by
the SRI Reactor Engineering Division to determine the air flow
characteristics in the process area. The occurrence of these
test provided an opportunity for the Environmental Transport
Group to perform some additional experimenta2 with a minimum of
additional effort. These additional experiments were performed to
obtain information that could be useful for obtaining an early
estimate of the probable total stack activity monitor response In
the event of an accidental release of activity in the process
room. If it can be shown that the stack activity monitor would
exhibit a 'typical' shape as the activity passes the monitor, the
magnitude of an incident release may be reliably predicted for
emergency response purposes long before the release to the
environment is complete.
$ASGROUND I NFORM&TIN
Computer methods developed at SRL for emergency response
associated with reactor accidents have required an estimate of
core damage before a source term could be defined. This was a
severe restraint because estimates of the exterit of core damage
were based on analysis methods that were sensitive to basic, and
probably u*raliable, assumptions. These analyses could be
accomplished only after a significant delay and could result in
inappropriate emergency response action. Therefore, a program was
developed to bass source term estimates on the response of the
total stack activity monitor located in each reactor area.
Locations of these mnitore are being standardized, and responses
to unit releases of various isotopes have been computed3 to
develop source terms from the monitor response. This capability
is offered as an option in the SRL Emergency Response Code,
The most probable incident leading to core damage is criticality
following a loading error during charge-discharge operations.
This is still a very low probability event and histoxically no
uninteational criticality has ever occurred at the Savannah River
Plapt. Any fuel mlted during such an incident is expected to
remain in a molten state for only a brief period due to fuel
lumping, or termination of the incident by safety system
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Cooper, R. E. Reactor Room Experimental SF6 Tests to Determine Probable Stack Activity Response to Radioactive Releases, report, August 19, 2002; South Carolina. (https://digital.library.unt.edu/ark:/67531/metadc742836/m1/3/: accessed April 23, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.