ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
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Preparation of UF3-Bearing Fuels<br />
C. M. Blood<br />
H. A. Friedman<br />
F. P. Boody<br />
F. W. Miles<br />
G. M. Watson<br />
Materials Chemistry Division<br />
Since preliminary results have shown that UF,-<br />
bearing fuels are less corrosive to lnconel than<br />
UF4-beariny fuels, considerable effort has been<br />
devoted to studying methods for preparing these<br />
materials. The experiments performed thus far<br />
have given results that ore not as yet well under-<br />
stood.<br />
The tabulated values for standard free energy of<br />
formation indicate that at 800OC the reaction<br />
$U0 + %UF,+UF,, 4F0 - -16 kcal,<br />
should proceed to essential completion if the com-<br />
pounds are in their standard states. There is ample<br />
evidence that UF, dissolved in NaZrF, is more<br />
stable to reduction by chromium than would be<br />
e~pected,~ but the difference between the expected<br />
and the actual stability is hardly sufficient to<br />
suggest that reduction of UF, by uranium metal<br />
should be detectably incomplete.<br />
The reduction of UF, to UF, with uranium or<br />
zirconium metal has been attempted in a large<br />
number of preparations by the following technique.<br />
About 500 g of material containing the predetermined<br />
quantity of UF, is treated with HF and H, in nickel<br />
equipment in the usual fashion to render it essen-<br />
tially free from contaminants. This purified mixture<br />
is cooled below the melting point, and the desired<br />
quantity of uranium or zirconium metal turnings is<br />
added. The reaction is allowed to proceed while<br />
the mixture in the reactor is stirred by a stream of<br />
hydrogen bubbling through it, Samples of the melt<br />
can be obtained by drawing a sample into a filter<br />
stick of nickel containing a sintered-nickel filter<br />
medium, The specimens removed from the filter<br />
stick are available for petrographic, x-ray, and wet<br />
chemical exam inati on.<br />
The data obtained from several preparations are<br />
presented in Table 5.13. It is obvious that com-<br />
plete reduction was not obtained in any preparation<br />
and that reduction in the NaF-KF-LiF system was<br />
much less complete than in the other solvents.<br />
While the number of experiments performed to date<br />
may be too small to establish reliable trends, the<br />
following pertinent observations cam be made on<br />
the basis of examination of these experiments and<br />
results.<br />
PERIOD ENDlNG SEPTEMBER 70, 1954<br />
UF, in ZrF, Systems. About 90% of the antici-<br />
pated reduction was obtained when large quantities<br />
of reducing agent were used to obtain UF, in<br />
ZrF4-bearing mixtures. In view of he extreme<br />
precautions which must be observed to prevent<br />
oxidation of the material during preparation and<br />
handling, it appears safe to state that about 90% of<br />
the UF, can be reduced under optimum conditions.<br />
No alkali metal was observed under the operating<br />
conditions used. The extent of reduction in these<br />
systems could be qualitatively distinguished by<br />
petrographic examination.<br />
UF, in Molten LiF. More than 90% of the UF, in<br />
molten LiF was reduced in each case, but complete<br />
reduction was not accomplished. It is not possible<br />
to say whether the difference between 0.96 at<br />
825OC and 0.91 at 850°C is real. No alkali metal<br />
vapor was detected. Petrographic examination<br />
detected the presence of small quontities of UF,.<br />
UF, in Molten NaF-KF-LiF.<br />
In five experiments<br />
at 780 to 80OT the maximum reduction obtained in<br />
NaF-KF-Li F was 48% of that expected. The extent<br />
of reduction was only slightly affected by an in-<br />
crease in the reducing agent from 92 to 121% and<br />
by an increase in the reaction time from 3 to 52 hr.<br />
At lower equilibration temperatures the extent of<br />
reduction was increased. The highest value was<br />
obtained at the shortest equilibration time and with<br />
the largest excess of reducing agent.<br />
In all the experiments at 780 to 8OO0C, alkali<br />
metal vapor was evident; however, at 60OoC no<br />
alkali vapor was observed. It is possible that a<br />
part of the difficulty in obtaining complete reduction<br />
is due to reactions of the type<br />
U + 3KF;=--"UF, + 3K0 , AFO = t26.1 kcal,<br />
and<br />
UF, + KFeUF, + KO , L\Fo = t30.3 kcol,<br />
where the metallic potassium being relatively<br />
volatile is removed from the reaction by the hydro-<br />
gen stream. It is also possible that the dispropor-<br />
tionation reaction<br />
UF,&$UF, + tu, AP = +16 kcal,<br />
is responsible. However, it is especially difficult<br />
to see why this reaction should be more important<br />
in an NaF-KF-LiF solution than in an LiF solution.<br />
Under petrographic examination the products of<br />
the eight experiments with NaF-KF-LiF solution<br />
appeared to be identical even though by chemical<br />
analyses they showed widely different UF,-to=UF,<br />
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