ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
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TIME (rnin)<br />
PERIOD ENDING SEPTEMBER 10, 7954<br />
m<br />
<strong>ORNL</strong>-LR-DWG 266i<br />
0 10 20 30 40 50 60 70<br />
DISTANCE FROM HtACTOR (cml<br />
Fig. 13.7. Decay of Air Glow and Reactor Gamma Fig. 13.8. Attenuation in Water of Radiation<br />
Rays. Causing Air Glow.<br />
of light. This large uncertainty is primarily at-<br />
tributable to the low sensitivity of the eye-equiva-<br />
lent photomultiplier. A more detailed discussion<br />
of these preliminary values will be given in a<br />
forthcoming report. 8<br />
FUEL ACTIVATION METHOD FOR POWER<br />
DETERMINATION OF THE ARE<br />
E. B. Johnson<br />
When the ARE goes into operation, many measure-<br />
ments of its performance will be made. Among<br />
them will be the power level at which it operates,<br />
which will be measured in more than one way. A<br />
method suggested by J. L. Meem is based on the<br />
measurement of the relative activity of fuel samples<br />
exposed in the ARE and in a known flux in another<br />
reactor (BSR). An experiment has been initiated<br />
at .the BSF to implement this suggestion.<br />
8F. C. Maienschein et al., iMeusurc7nents o/ u l?t?acto~-<br />
Induced Air Glow, <strong>ORNL</strong> CF-54-9-1 (to be issued).<br />
The activity resulting from the irradiation of<br />
fissionable material is not easy to predict because<br />
of the large number of isotopes for which calcu-<br />
lations would be required. However, for identical<br />
flux, exposure time, and waiting period after<br />
exposure, the specific activity of two samples<br />
should be the same. Furthermore, at low neutron<br />
fluxes the activity should be proportional to the<br />
flux.<br />
It is contemplated that the ARE will be operated<br />
at a nominal power level of approximately 1 w for<br />
1 hr, that it will then be shut down, and that a<br />
sample of the irradiated fuel will be withdrawn for<br />
counting and analyzing. The ARE experimental<br />
progrom will then proceed as scheduled. A decay<br />
curve will be run on this fuel sample from the ARE<br />
and compared with the decoy curve obtained on a<br />
similar fuel capsule irradiated for the same length<br />
of time in the BSR in 01 known neutron flux of about<br />
the same magnitude. From the relative activity of<br />
the two samples, the operating power of the ARE<br />
173