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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sample of the irradiated fuel will be withdrawn for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

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