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 UF, Stability W. C. Whitley R. J. Sheil Materials Chemistry Division During the past quarter studies have been under way on the stability of UF, separately and mixed with KF. Disproportionation of UF, in KF in Inconel at 1000°C has been established. When contained alone in Inconel, UF, does not detect- ably disproportionate below 125OOC. Stability of UF, at Elevated Temperatures. The disproportionation of UF, as a function of temper- ature was studied earlier under high vacuum. Recent availability of high-purity UF, made de- sirable a study of the high-temperature stability of UF, in a helium atmosphere. For these experi- ments 25-9 samples of UF, that contained 99.4% of the uranium in the trivalent form were sealed by welding in lnconel tubes containing 4 atm of helium. After being heated at the desired temper- ature for 1 hr, the tubes were removed from the furnace and were air quenched to minimize re- combination of UF, and uranium metal. After the UF, samples were cooled to room temperature and ground in an inert atmosphere, they were examined petrographically, by x-ray diffraction, and by chemical analysis. The sample heated to 120OOC showed no evidence of disproportionation, the sample heated to 125OOC showed very slight evidence, and the sample heated to 130OOC showed definite evidence. In addition to the increase in UF, content noted in the petrographic examination, an increase in U4' was shown by chemical analy- sis (from 0.6 to 1.6%), and the presence of uranium in the tube walls that had been in contact with the UF3,was established. These data show that UF, is more sfable at elevated temperatures than estimates of its thermodynamic properties l5 had indicated. It is interesting to note that the sample of UF, heated to 13OOOC was practically insoluble in boiling 10 N HCI, whereas samples heated to lower temperatures dissolved readily in this solvent. This could indicate that either a sintering action occurred, which takes place in oxide systems well below the melting point, or 14L. Brewer et al., Thermodynamic Properties and Equilibria at High Temperatures of Uranium Halides, Oxides, Nitrides, and Carbides, MDDC-1543 (Sept. 20, 1945. rev. ADr, . 1. . 1947). 15A. Glassner, A Survey of the Free Energies of Formation of the Fluorides, Chlorides. and Oxides of the Elements to 2500°K, ANL-5107 (Oct. 22, 1953). 60 that the small amount of liquid UF, formed at the high temperature exerted a cementing action of the UF, crystals on solidifying. Stability of UF, in KF. An attempt was made to determine the stability of UF, in molten KF as a function of temperature by starting with dry KF P and high purity UF, (99.4%). idixtures of KF and UF, in the molar ratios of KF to UF, of 3.0, 1.5, and 1.0 were mixed, sealed in lnconel capsules containing ?$ atm of helium, and heated for 2 hr at various temperatures before air quenching. A period of two weeks elapsed between the time of the experiment and the time that the samples were submitted for chemical analysis for total uranium and U3', and thus there is some doubt of the significance of the U3' determinations. However, both the total uranium and the trivalent uranium values exhibited a downward trend with increasing temperature in the temperature range 750 to 1050OC for mixtures having a 3 to 1 KF-UF, molar ratio. An average of 7 moles of UF, disappeared per gram-atom of uranium lost, presumably by alloying * . of the uranium metal with the lnconel capsule walls. Mixtures having 1.5 to 1 and 1 to 1 KF-UF, molar ratios were heated to 850 and 1050°C. Analyses of these melts also showed the downward trend in U3' and total uranium values with increasing - temperature. In these samples, however, the ratio of moles of UF, (or gram-atoms of trivalent uranium) to gram-atoms of uranium lost averaged about 5 as compared with the theoretical value of 4. The capsules used to contain these materials were not analyzed for metallic uranium; however, a similar experiment was performed in which an 85 mole '% KF-15 mole % UF, mixture was heated to 1000°C in an lnconel capsule for 90 min. The melt was sampled by drilling aiter the top and bottom of the capsule had been cut off. The remainder of the melt was dissolved out, and the walls were carefully cleaned mechanically; then, approximately 7 mils of the tube wall that had been in contact with the melt was removed by drilling. Flashes of light observed during drilling gave a qualitative indication of the presence of uranium in the tube walls which was confirmed by chemical analysis, * which showed 17.9 wt % uranium. The total of 0.28 g of uranium that was recovered from the tube walls represented 3.6% of the total uranium coni) tained in the KF-UF, mixture. Analysis of the melt showed 70% of the total uranium to be in the trivalent state. It seems certain that dispro-

portionation of UF, occurred at a lower tempera- ture than would have been expected in the absence of KF. Further experimentation is planned to determine the stability of UF, in KF and other solvents as a function of temperature and of con- tainer material. Preliminary experiments indicate that UF, may be more stable when dissolved in KF in a platinum container than in a nickel con- tainer. Differential Thermal Analysis C. J. Barton Materials Chemistry Division D. L. Stockton Merck and Company, Inc. As a result of the high frequency of failures ex- perienced with nickel capsules containing NaF-UF, samples, a new system was designed for containing samples during differential thermal analysis. Graphite containers constructed so that the thermo- couple junctions can be immersed directly in the melt are now being used. The new system is designed to permit evacuation before introduction of helium as the inert atmosphere. A cylindrical graphite block (3% in. in diameter and 6 in. high) serves as a heat sink inside a nickel reaction vessel (4 in. in diameter and 7 in. deep) with a flanged head. Six graphite thimbles, '/2 in. ID, $ in. OD, and 3 in. deep, are spaced on a hexagonal array inside the upper half of the graphite block. Each thimble is filled to a depth of about 1 in. with either sample (about 6 g) or reference material, AI,O,; the sample depth is reduced by about 50% upon melting. A g-in.-dia nickel tube which contains two Chromel-Alumel thermocouples contained in a each sample thimble. .. PERIOD ENDING DECEMBER 70, 7954 sensitivity as compared with the nickel capsule technique and may be very useful if the oxidation difficulty can be overcome. Further experimen- tation with this apparatus and with simplified equipment that will permit the use of smaller samples is in progress. CHEMICAL REACTIONS IN MOLTEN SALTS F. F. Blankenship L. G. Overhol!jer W. R. Grimes Materials Chemistry Division Reduction of FeF, by H, in NaF-ZrF, Systems C. M. Blood Materials Chemistry Division The reduction of FeF, with hydrogen is of particular significance in considering the time necessary for purification of NaZrF5 mixtures, as discussed previously, l6 and has therefore been studied in considerable detail. The reaction FeF, + H 2 e FeO + 2HF was previously explored by a dynamic method and by an equilibration method that actually determined equilibrium conditions of the system. During the past quarter the dynamic method was employed further. Measurements of the equilibrium HF pressures from the reduction of FeF, in NaZrF5 by hydrogen gave, as a preliminary result, an equilibrium constant, K, of 0.2 at 600°C as compared with the value of 2.0 at 8OOOC previously reported.16 The equilibrium constant is calculated from the equation where P is expressed in atmospheres and C in mole fractions. , to UF, in Fluoride Melts ditions on the extent of reduction of UF, to UF, in fluori ued by the use of a Dreviouslv described Drocedure.' To dlstermine to obtain a sufficiently vacuum-tight assembly to 17C. M. Bled et al., ANP Quar. Prog. Rep. Sept. 10, avoid oxidation of UF,. It has shown very high 1954, ORNL-1771, p 77. ~~ ... . . . . . 61

ANP QUARTERLY PROGRESS REPORT<br />

UF, Stability<br />

W. C. Whitley R. J. Sheil<br />

Materials Chemistry Division<br />

During <strong>the</strong> past quarter studies have been under<br />

way on <strong>the</strong> stability of UF, separately and mixed<br />

with KF. Disproportionation of UF, in KF in<br />

Inconel at 1000°C has been established. When<br />

contained alone in Inconel, UF, does not detect-<br />

ably disproportionate below 125OOC.<br />

Stability of UF, at Elevated Temperatures. The<br />

disproportionation of UF, as a function of temper-<br />

ature was studied earlier under high vacuum.<br />

Recent availability of high-purity UF, made de-<br />

sirable a study of <strong>the</strong> high-temperature stability<br />

of UF, in a helium atmosphere. For <strong>the</strong>se experi-<br />

ments 25-9 samples of UF, that contained 99.4%<br />

of <strong>the</strong> uranium in <strong>the</strong> trivalent form were sealed<br />

by welding in lnconel tubes containing 4 atm of<br />

helium. After being heated at <strong>the</strong> desired temper-<br />

ature for 1 hr, <strong>the</strong> tubes were removed from <strong>the</strong><br />

furnace and were air quenched to minimize re-<br />

combination of UF, and uranium metal. After <strong>the</strong><br />

UF, samples were cooled to room temperature and<br />

ground in an inert atmosphere, <strong>the</strong>y were examined<br />

petrographically, by x-ray diffraction, and by<br />

chemical analysis. The sample heated to 120OOC<br />

showed no evidence of disproportionation, <strong>the</strong><br />

sample heated to 125OOC showed very slight<br />

evidence, and <strong>the</strong> sample heated to 130OOC showed<br />

definite evidence. In addition to <strong>the</strong> increase in<br />

UF, content noted in <strong>the</strong> petrographic examination,<br />

an increase in U4' was shown by chemical analy-<br />

sis (from 0.6 to 1.6%), and <strong>the</strong> presence of uranium<br />

in <strong>the</strong> tube walls that had been in contact with <strong>the</strong><br />

UF3,was established. These data show that UF,<br />

is more sfable at elevated temperatures than<br />

estimates of its <strong>the</strong>rmodynamic properties l5<br />

had indicated. It is interesting to note that <strong>the</strong><br />

sample of UF, heated to 13OOOC was practically<br />

insoluble in boiling 10 N HCI, whereas samples<br />

heated to lower temperatures dissolved readily in<br />

this solvent. This could indicate that ei<strong>the</strong>r a<br />

sintering action occurred, which takes place in<br />

oxide systems well below <strong>the</strong> melting point, or<br />

14L. Brewer et al., Thermodynamic Properties and<br />

Equilibria at High Temperatures of Uranium Halides,<br />

Oxides, Nitrides, and Carbides, MDDC-1543 (Sept. 20,<br />

1945. rev. ADr, . 1. . 1947).<br />

15A. Glassner, A Survey of <strong>the</strong> Free Energies of<br />

Formation of <strong>the</strong> Fluorides, Chlorides. and Oxides of<br />

<strong>the</strong> Elements to 2500°K, ANL-5107 (Oct. 22, 1953).<br />

60<br />

that <strong>the</strong> small amount of liquid UF, formed at <strong>the</strong><br />

high temperature exerted a cementing action of <strong>the</strong><br />

UF, crystals on solidifying.<br />

Stability of UF, in KF. An attempt was made to<br />

determine <strong>the</strong> stability of UF, in molten KF as a<br />

function of temperature by starting with dry KF<br />

P<br />

and high purity UF, (99.4%). idixtures of KF and<br />

UF, in <strong>the</strong> molar ratios of KF to UF, of 3.0, 1.5,<br />

and 1.0 were mixed, sealed in lnconel capsules<br />

containing ?$ atm of helium, and heated for 2 hr<br />

at various temperatures before air quenching. A<br />

period of two weeks elapsed between <strong>the</strong> time of<br />

<strong>the</strong> experiment and <strong>the</strong> time that <strong>the</strong> samples were<br />

submitted for chemical analysis for total uranium<br />

and U3', and thus <strong>the</strong>re is some doubt of <strong>the</strong><br />

significance of <strong>the</strong> U3' determinations. However,<br />

both <strong>the</strong> total uranium and <strong>the</strong> trivalent uranium<br />

values exhibited a downward trend with increasing<br />

temperature in <strong>the</strong> temperature range 750 to 1050OC<br />

for mixtures having a 3 to 1 KF-UF, molar ratio.<br />

An average of 7 moles of UF, disappeared per<br />

gram-atom of uranium lost, presumably by alloying * .<br />

of <strong>the</strong> uranium metal with <strong>the</strong> lnconel capsule<br />

walls. Mixtures having 1.5 to 1 and 1 to 1 KF-UF,<br />

molar ratios were heated to 850 and 1050°C. Analyses<br />

of <strong>the</strong>se melts also showed <strong>the</strong> downward trend<br />

in U3' and total uranium values with increasing<br />

-<br />

temperature. In <strong>the</strong>se samples, however, <strong>the</strong> ratio<br />

of moles of UF, (or gram-atoms of trivalent uranium)<br />

to gram-atoms of uranium lost averaged about<br />

5 as compared with <strong>the</strong> <strong>the</strong>oretical value of 4. The<br />

capsules used to contain <strong>the</strong>se materials were not<br />

analyzed for metallic uranium; however, a similar<br />

experiment was performed in which an 85 mole '%<br />

KF-15 mole % UF, mixture was heated to 1000°C<br />

in an lnconel capsule for 90 min. The melt was<br />

sampled by drilling aiter <strong>the</strong> top and bottom of <strong>the</strong><br />

capsule had been cut off. The remainder of <strong>the</strong><br />

melt was dissolved out, and <strong>the</strong> walls were carefully<br />

cleaned mechanically; <strong>the</strong>n, approximately<br />

7 mils of <strong>the</strong> tube wall that had been in contact<br />

with <strong>the</strong> melt was removed by drilling. Flashes<br />

of light observed during drilling gave a qualitative<br />

indication of <strong>the</strong> presence of uranium in <strong>the</strong> tube<br />

walls which was confirmed by chemical analysis,<br />

*<br />

which showed 17.9 wt % uranium. The total of<br />

0.28 g of uranium that was recovered from <strong>the</strong> tube<br />

walls represented 3.6% of <strong>the</strong> total uranium coni)<br />

tained in <strong>the</strong> KF-UF, mixture. Analysis of <strong>the</strong><br />

melt showed 70% of <strong>the</strong> total uranium to be in<br />

<strong>the</strong> trivalent state. It seems certain that dispro-

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