ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
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ANP QUARTERLY PROGRESS REPORT<br />
-<br />
<strong>ORNL</strong>-LR-OWG 3783A<br />
0 20 40 60 EO (02.5 I25 i45 165 185 205<br />
s. DISTANCE FROM INLET (cm)<br />
Fig. 9.4. Fuel Temperature in Miniature in-Pile<br />
Loop for a Cooling Air Reynolds Number of 20,000<br />
as a Function of Distance from <strong>the</strong> Inlet and <strong>the</strong><br />
Reynolds Number for <strong>the</strong> Fuel.<br />
1 24<br />
REMOVAL OF Xe13’ FROM<br />
MOLTEN FLUORIDE FUELS<br />
M. T. Robinson<br />
Sol id State Division<br />
W. A. Brooksbank<br />
Anal yt i ca I Chemi stry Division<br />
D. E. Guss<br />
USAF<br />
The study, described previ~usly,~ for determining<br />
whe<strong>the</strong>r Xe135 would escape from ART-type purging<br />
equipment rapidly enough to prevent serious poisoning<br />
was continued. It was realized at <strong>the</strong> time<br />
this study was initiated that <strong>the</strong> ARE might answer<br />
<strong>the</strong> question satisfactorily, but it was decided to<br />
go ahead with experiments to measure <strong>the</strong> xenon<br />
solubility under <strong>the</strong> more pertinent ART conditions.<br />
It was considered unlikely that 97% of <strong>the</strong> equilibrium<br />
xenon would be removed from <strong>the</strong> ARE without<br />
special purging equipment, and, yet, this is<br />
what happened according to two independent sets<br />
of calculations. During <strong>the</strong> initial stages of<br />
reactor operation, data were obtained from a reactivity<br />
calibration of <strong>the</strong> ARE regulating rod by<br />
noting changes in rod position required to maintain<br />
criticality as increments of U235 were added to <strong>the</strong><br />
fuel. The value of <strong>the</strong> rod was calculated to be I<br />
0.030 t0.006% Ak/in., which agrees well with <strong>the</strong><br />
preliminary value reported by J. L. Meem (cf, Sec.<br />
1, “Circulating-Fuel Aircraft Reactor Experiment”).<br />
When <strong>the</strong> ARE was operated for 25 hr at an estimated<br />
2 Mw, constant power was maintained by<br />
adjustment of <strong>the</strong> regulating rod. At <strong>the</strong> end of<br />
this period of operation, <strong>the</strong> rod had been withdrawn<br />
an amount equivalent to a reactivity decrease of<br />
0.015 k 0.003%. The expected decrease in reactivity<br />
was calculated to be:<br />
From burnup of U235 0.001%<br />
From Srn149 poisoning 0.008%<br />
From Xe135 poisoning 0.4 1 %<br />
Since over one-half <strong>the</strong> observed change in reactivity<br />
may be accounted for by burnup and Sm149<br />
poisoning, <strong>the</strong> amount of Xe135 retained in <strong>the</strong> fuel<br />
was less than 1 to 2% of <strong>the</strong> amount expected. -<br />
4M. T. Robinson et al., ANP Quar. Prog. Rep. Sept.<br />
* .-<br />
10, 1954, <strong>ORNL</strong>-1771, p 140. .