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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Therefore, <strong>the</strong> ARE supplied evidence that <strong>the</strong><br />
rare gases escape readily from <strong>the</strong> fluoride fuels<br />
under dynamic conditions. Since <strong>the</strong> amount of<br />
xenon present in a circulating-fuel reactor is probably<br />
more than <strong>the</strong> amount produced in one complete<br />
fuel cycle (50 sec in <strong>the</strong> ARE), <strong>the</strong> amount remaining<br />
in <strong>the</strong> fuel will be measured by using an ARE<br />
fuel sample for radiochemical comparison of <strong>the</strong><br />
concentration of <strong>the</strong> fission products (Sr89, Cs137,<br />
and Ce’,’) which come through rare-gas precursors<br />
with those ( CS’~~ and Zr95) which do not,<br />
The gamma-ray scintillation spectrometer to be<br />
used for <strong>the</strong> experiments has been calibrated with<br />
Cs137, Na2*, and Hg203, and <strong>the</strong> equipment has<br />
been tested with radioactive noble gases taken<br />
from samples of off-gas from <strong>the</strong> iodine dissolver<br />
used by <strong>the</strong> Radioisotopes Department of <strong>the</strong><br />
Operations Division. The gases used were primarily<br />
Xe133 and Xe135. In order to prevent <strong>the</strong><br />
ma rays from o<strong>the</strong>r short-lived nuclides from<br />
competing unfavorably with those from Xe135 and<br />
thus making resolution of <strong>the</strong> Xe’35 isotope difficult,<br />
a charcoal adsorption column (0.190 in. in<br />
diameter and 0.5 in. long) for delaying isotopes<br />
such as those of krypton was tested at room temperature<br />
by using KrE5 and <strong>the</strong> gamma-ray spectrometer,<br />
It was found that <strong>the</strong> charcoal trap would delay<br />
krypton isotopes for about 10 min (at a flow rate<br />
of about 15 cm3/min) and xenon isotopes for about<br />
200 min. Thus spectrometer would measure<br />
only long-lived is<br />
Fission products may be lost from ARE-type fuel<br />
by volatility of <strong>the</strong> fission product or of one of its<br />
precursors; by interaction of <strong>the</strong> fission product or<br />
es such as ~ e ~ ~ ~ .<br />
by any of <strong>the</strong>se means, since it will be “carried”<br />
by <strong>the</strong> large quantity (50 mole %) of ordinary ZrF,<br />
PERIOD ENDING DECEMBER 70,1954<br />
in <strong>the</strong> fuel and since it has no known rare-gas<br />
precursor (if Kr95 exists, it probably has a very<br />
short half life, say 1 or 2 sec). This isotope will<br />
be used <strong>the</strong>refore as <strong>the</strong> basis for normaliiring <strong>the</strong><br />
yields of <strong>the</strong> o<strong>the</strong>r radioisotopes to be studied.<br />
Volatility of <strong>the</strong> rare gases will be examined by<br />
studying <strong>the</strong> yields of Sr89 and of CS~~’‘ which<br />
come through 2.6-min Kr89 and 3.0-min Xe137,<br />
respectively, Low yields for <strong>the</strong>se two isotopes<br />
would indicate high volatilities for <strong>the</strong>ir parents,<br />
Kr89 and Xe137. A fur<strong>the</strong>r check of <strong>the</strong> experiments<br />
will be made by using Ce141, a descendant of<br />
3-sec Xe141, which should be retained in <strong>the</strong> fuel,<br />
and Cs136, a shielded nuclide formed directly in<br />
fission. Comparison of Zr9’ with Cs136 anti Ce141<br />
will give a measure of <strong>the</strong> loss of <strong>the</strong> important<br />
alkali and rare-earth elements through adsorption<br />
on metal surfaces, since C S ’ ~ and ~ rare-earth<br />
elements will be present only in trace quantities<br />
but chemical zirconium will be present in very<br />
large quantities, as mentioned above.<br />
The data obtained from <strong>the</strong> ARE fuel sample will<br />
be compared with similar data to be obtained from an<br />
irradiated sampleof NaF-ZrF,-UF, (50-46-4 mole %)<br />
that will be maintained solid to retain all <strong>the</strong> fission<br />
products, The cooling period for <strong>the</strong> irradiated<br />
sample will be <strong>the</strong> same as that for <strong>the</strong> ARE fuel<br />
sample.<br />
LIT R HO Rl ZO NTAL- B E AM-HO L E<br />
FL UORlD E-FU EL LOOP<br />
0. Sisman J. G. Morgan<br />
W. E. Brundage M. T. Morgan<br />
C. D. Baumann A. S. Olson<br />
R. M. Carroll W. W. Parkinson<br />
and Physical Properties” (this report). The curve<br />
obtained for pressure of air vs heat removcil gives<br />
125