05.08.2013 Views

ORNL-1771 - Oak Ridge National Laboratory

ORNL-1771 - Oak Ridge National Laboratory

ORNL-1771 - Oak Ridge National Laboratory

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

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 />

77

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!