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ORNL-1771 - Oak Ridge National Laboratory

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Studies of the NaF-ZrF,-UF, system were initi-<br />

ated after the solid phase studies in the NaF-ZrF,<br />

system were completed, and to date no ternary com-<br />

pounds have been discovered in the NuF-ZrF,-UF,<br />

system. A tentative equilibrium diagram has been<br />

prepared, The apparatus for vi suul observation of<br />

melting temperatures was used to observe eleven<br />

NaF-UF, mixtures in the composition range 20 to<br />

50 mole % UF,, and a partial phase diagram of the<br />

system was prepared. A new apparatus has been<br />

constructed that will permit some mnnipulations to<br />

be carried out with the fused salts in an inert<br />

atmosphere.<br />

Recent attempts to correlate the anticipated re-<br />

duction of UF, in the preparation of UF3-bearing<br />

melts with wet chemical analysis for UF, and UF,<br />

and results of petrographic examination show some<br />

surprising anomalies. When UF, dissolved in LiF,<br />

in NaF-ZrF, mixtures, or in NaF-LiF mixtures is<br />

treated under flowing hydrogen at 800°C with ex-<br />

cess uranium metal, 90% or more of the UF, is<br />

reduced to UF,. However, when this technique is<br />

applied to UF, in NaF-KF-LiF mixtures, the re-<br />

duction is only 50% complete at 800°C and, perhaps,<br />

75% complete at 600°C. Petrographic examinations<br />

of the specimens reveal no complex compounds of<br />

tetravalent uranium; it is possible that the UF, is<br />

“hidden”in solid solutions or in complex UF,-UF,<br />

compounds in which it is not at present recogniz-<br />

able.<br />

A method for the large-scale Purification of<br />

rubidium fluoride has been developed. All the<br />

rubidium fluoride obtained from commercial sup-<br />

pliers to date has contained considerably more than<br />

the specified quantity of cesium compounds, and<br />

therefore almost all of it has been returned io the<br />

vendors for further processing. The purification<br />

method developed can be used at a reasonable cost<br />

on a large scale if material sufficiently free from<br />

cesium cannot be obtained from commercial sources.<br />

Values for the equi!ibrium constant for the re-<br />

action<br />

Cr” + 2UF, 2UF, t CrF,<br />

in molten NaZrF, have been re-examined by the use<br />

of various ratios of UF3/UF, with chromium metal<br />

in the charge. From the data obtained when this<br />

5. CHEMISTRY OF MOLTEN ~ ~ ~ ~ R ~ ~ L S<br />

W. R, Grimes<br />

Materials Chemistry Division<br />

initial ratio is less than 3, average values of<br />

5 x IO-, at 600°C and 6 x lom4 at 800°C can be<br />

computed, At ratios larger than 3 the values in-<br />

crease regularly; this rise is probably due to the<br />

extreme difficulty in filtration and analysis of<br />

samples containing 1 to 20 ppm of Cr++. The<br />

values at low UF,/UF, ratios agree quite well<br />

with the corresponding values of 4.2 x lo-, at<br />

600°C and 4.1 x low4 at 800’C obtained previously<br />

when UF, and chromium metal were the charge<br />

mater i a1<br />

Fundamental studies were made of the reduction<br />

of NiF, and FeF, by H, in NaF-ZrF, systems as<br />

a means of determining possible improvements in<br />

purification techniques. Also, methods for pre-<br />

paring simple structural metal fluorides were<br />

studied. Additional measurements of decomposition<br />

potentials of KCI and of various chlorides in molten<br />

KCI at 850°C were made.<br />

Preliminury measurements of the solubility of<br />

xenon in KNO,-NaNO, eutectic (66 mole 7; NaNQ,)<br />

show values of 8.5 x low8 and mo6e/cm3 at<br />

280 and 3M)”C, respectively, at 1 atm xenon pres-<br />

sure. The all-glass apparatus used has been re-<br />

placed with CI nickel and glass combination, and<br />

measurements of xenon solubility in molten fluo-<br />

rides are being made.<br />

Large quantities of purified ZrF4-base fluorides<br />

are being prepared for engineering tests at <strong>ORNL</strong><br />

and elsewhere, and the demand for purified fluo-<br />

rides of other types for possible reactor fuel appli-<br />

cation is increasing rapidly. Consequently, an<br />

increasing fraction of the effort is devoted to pro-<br />

duction or to research in direct support of produc-<br />

tion functions.<br />

Since the consumption of NaF-ZrF, and NaF-<br />

ZrF,-UF, mixtures is expected to reach 10,000 Ib<br />

during the fiscal year, it is important to decrease<br />

the cost of production of this material. The HF-H,<br />

processing currently used is adequate from all<br />

points of view, but processing times of nearly<br />

I00 hr per batch ore now required with the rela-<br />

tively poor raw materials available. The sub-<br />

stitution of hafnium-Free ZrF, and commercially<br />

available NaFx.ZrF, for the impure ZrF, now<br />

used should afford a considerable saving. The<br />

53

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