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vapor; however, nickel vessels have been satisfactory. For satisfactory operation, the nickel vessels must be loaded in helium dry boxes, and a dry helium atmosphere must be maintained over the samples at all times. The available UC1, has served for preliminary experiments for defining the techniques; however, the C1-to-U ratio of 3.9 and the low melting point of 565°C (literature value for pure UG1, is 590 k 1°C) make this material unsuitable as a standard for study. This material w i l l be sublimed under vacuum and subsequently handled under dry, inert atmospheres to provide pure UCl, for future studies. Preliminary data have been obtained, meanwhile, on NaC1-UC1, mixtures. The eutectic and eutectoid halts reported by Kraus(') have, in general, been confirmed. Actual data w i l l be reported when pure materials become avail able. FUEL MIXTURES CONTAINING UF, N!. C. Whitley V. S. Coleman C. J. Barton Materials Chemistry Division Preliminary results of studies of a l kali fluorid e-u ran ium t ri fluoride systems were reported previously.( 2, The effort in this field was concen- trated on the NaF-UF, and KF-UF, binary systems during the past quarter. Data were obtained with two types of apparatus: the large vacuum-tight apparatus previously described( and small weided stainless steel reactors fitted with a thin-walled thermocouple w e l l in the center. In order to assure an inert atmosphere, the fluoride mixture was introduced into the reactor through a 1/4-in. tube, and the reactor was evacuated at room temperature, filled with inert gas, and then sealed by pinching and welding the tube. Mixing of the contents of the reactor was accomplished by -_I____ ("V. S. Coleman and W. C. Whitley, AMP Quar. Prog. Rep. Sept. 10, 1952, ORNL-1375, pa 79. PERIOD ENDING DECEMBER PO, 1952 inverting after it had been heated enough to bring all the material into solution. The mixture was not stirred during the cooling cycle. A comparison was made of cooling curves for the same composition in the two types of apparatus. The thermal effects occurred at about the same temperature with both types oE apparatus, but the breaks were some- what better defined with the small reactor. This is probably due to better contact between the thermocouple and melt in this apparatus and to the smaller heat capacity of the thin- walled thermocouple well. The thermal data were supplemented by examination of the solid phases by means of the petrographic microscope and, for a limited number of samples, by x-ray d i f frac tion techniques . NaF-UF,. Cooling curves have been run on mixtures covering the range from 5 to 85 mole % UF,. It was observed that the cooling curve breaks, except for the lowest break at about 59OoC, seemed to decrease upon prolonged heating at elevated tempera tu res. This change in thermal effects ap- parently results from the development of UF, and/or UO, in the melt. Both products are foiind in the fused material., in which the IJF, is combined with NaF. An intensive effort was made to find the source of the oxygen and to eliminate it from the system; but, to date, this effort has not been entirely successful, and some doubt exists as to the accuracy of the thermal data that have been obtained. However, several conclusions about the sys tern seem warranted: 1. A compound is formed between NaF and UF,. It is lavender in color, uniaxial positive, and has a refractive index for the ordinary say of 1.552 and for the extraordinary ray of 1.564.( 3, 2. The most probable composition for the compound, based on both thermal (3)petrographic examination by T. N. McVay. 109
ANP PROJECT QUARTERLY PROGRESS REPORT data and examination of the solid phases, is 3NaF*2UF3. This composition could be in error because of the presence of V4 in the melts, as mentioned above. 3. A eutectic exists between NaF and the compound, which is probably close to 27 mole % UF,, and it melts at approximately 685OC. The data obtained with mixtures containing more than 50 mole 7% UF, do not fit any recognizable pattern. The significance of the break at approximately 590°C, which was observed wit,h all compositions in this system, is still not clear. Further work toward solving these problems is in p rogress. KF-UF,. It is clear that a complex compound between KF and UF, is formed and that a eutectic between KF and the compound melting at approximately 690°C occurs at about 18 mole % UF,. 110 700na l i 600 20 30 40 Fig. 10.3. The System NaBF4-KBF,. The solid phases have not been thoroughly studied, and the optical properties of the compound have not been de- termined. Study of this system w i l l be resumed when the oxidation phe- nomenon mentioned above has been brought under control. ALKALI FLUOBQRATE SYSTEMS J. G. Surak Materials Chemi s t ry Di vi sion Thermal analysis studies of alkali fluoborate systems, which have been described in previous reports,(') were continued during the early part of the quarter. Additional data on the NnSF4 -KBF4 system have permitted construction of the tentative equi- librium diagram shown in Fig. 10.3. The liquidus curve appears to go (4).J. G. Surak, R. E. Moore, C. J. Barton, ANP Qua.. Prog. Rep. Sept. 10, 1952, ORNL- 1375. p. 82. ................. ....... 0 , 4y" I 1 60 70 80 !
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98- 108. 109. 110- 117. 118. 119-12
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Reports previously issued in this s
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e e e PAGE Moore Nullmatic pressure
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.. CrF. .Na. CrFd .Li. CrF6 .......
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PAGE Melting point of 60% Pd-40% Ni
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ANP PROJECT QUARTERLY PROGRESS REPO
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AYP PROJECT QUARTERLY PROGRESS REPO
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in the hot condition corresponds to
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c-' w FILL TANKS LINE VOLUME APPROX
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the disintegration rates and energi
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2. EXPERIMENTAL REACTOR ENGINEERING
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design of the first combination sea
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the construction of the shaft and r
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on packed seals for pumps and valve
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filling, fluoride leakage occurred
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for 1975 hr at 1500nF.~5) The first
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MASS VELOCITY ( Ib/hr .ft2) - PEXIO
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28C - 240 m W w IT e3 w D z 0 I- CJ
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These conditions were maintained fo
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3. GENERAL DESIGN STUDIES A. P. Fra
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- 8 e 90 85 80 75 rn- 7;) u) w z W
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0 03 06 - PERIOD ENDING DECEMBER 10
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In the theory of power oscillations
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J O dt C’ Again, because of the p
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and The assumed boundary conditions
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where N, = number of atoms per cubi
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4 5 6 7 a 9 10 11 12 13 14 15 16 17
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MSTANCE FROM REACTOR AXIS (in) Pmrm
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z 11 t- o a LT LL 1 .O 0.8 5 0.6 -
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300 250 >- I- 2 & 150 ct W LL 50 0
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T BLE 5. RADIAL PmITxm- (in. 1 REAC
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ANP PROJECT QUARTElilLY PROGRESS RE
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BRAZING ALLOY Nic robr az 60% Mn-40
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ANP PRQJECT QUARTERLY PROGRESS REPO
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ANP PROJECT QUARTERLY PIJQGRESS REP
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ANP PRQJECT QUAMTERLY PWOd;l"aESS R
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on air radiations and simulated fla
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184 Fie. 13.6. Pyrex Thermal Convec
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ANP PROJECT QU.4RTEtlLY I'ROGRESS R
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SUMMARY AND INTRODUCTION The list o
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CF-52-11-85 ORNL- 1 43 3 OWL- 137 2
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H. Seal and Pump Development PERIOD
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12. 13. 14. 15. 16. 1.7. 18. 19. Pr
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i 3. U0,-NaOH Slurry Loop 4. Operat
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7. Fuel Spherical Particle Producti
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