ORNL-2106 - the Molten Salt Energy Technologies Web Site
ORNL-2106 - the Molten Salt Energy Technologies Web Site ORNL-2106 - the Molten Salt Energy Technologies Web Site
ANP PROJECT PROGRESS REPORT 120 TABLE 2.3.4. SURFACE TENSION MEASUREMENTS ON NaF-ZrF4 (53-47 MOLE W) Temperature Sample Weight Weight Loss Final Composition* Density Surface Tension x/z (OC) (9 ) (%I (mole % ZrFJ (9/cm3) (dynes/cm) ~ ~ ~~~~ ~ ~ ~ ~ 601 ** 0.870 28.2 36 d 1.71706 3.043 141 603** 0.870 28.2 36.6 1.66592 3.040 141 61 1 0.4502 3.1 43.5 1.53637 3.030 141 61 0 0.4502 3.1 43.5 1.56345 3.031 134 601 0.4502 3.1 43.5 1.60542 3.043 122 601 0.4502 3.1 43.5 1.57069 3.043 132 601 Od502 3.1 43.5 1.55482 3.043 136 601 0.4502 3.1 43.5 1.56994 3.043 131 610 0.5097 3.7 41.4 1.68795 3.031 117 610 0.5097 3.7 41.4 1.65982 3.031 124 6 02 -. 0.5 097 3.7 41.4 1.64464 3.043 128 *Calculated from anolysis of material after test. **Tested in vacuum; all other samples tested under helium atmosphere. TABLE 2.3.5. CONSTANTS OF EQUATION FOR SPECIFIC CONDUCTANCE, K, OF FUSED LITHIUM, POTASSIUM, AND CESIUM FLUORIDES K = a + (b X lo’*), + (c x 10-6)t2, ohm-l-cm’l, where t is in OC Salt a b c Standard Deviation Applicable Temperature (ohm-’ Scm‘’) Range (‘C) LiF + 3.805 + 1.004 -3.516 0.008 847-1027 KF -3.493 + 1.480 -6.608 0.009 - 869-1040 CsF -4.51 1 + 1.642 -7.632 0.009 Salt a TABLE 2.3.6. CONSTANTS OF EQUATION FOR DENSITY, p, OF FUSED LITHIUM, POTASSIUM, AND CESIUM FLUORIDES LiF 2.2243 0.4902 KF 2.4685 0.651 5 p = a - (b x 9/cm3, where 1 is in OC b 725-921 Standard Deviation, Experimental Temperature (7 (s/cm3) Range PC) 0.0003 0.0003 876-1 047 881-1 037 Cs F 45489 1.2806 0.0004 712-912 * *
u 2.4. PRODUCTION OF FUELS c G. J. Nessle G. M. Watson L. G. Overholser I EXPERIMENTAL PREPARATION OF c tid VARIOUS FLUORIDES B. J. Sturm Continued use of structural metal fluorides for research necessitated the preparation of additional quantities of these materials by the several methods developed previously. As in the past, use was made of chemical, x-ray, and petrographic examinations to establish the identity and purity of the materials. Additional CrF, was prepared by hydrofluorination of anhydrous CrCI,, as well as by the thermal decomposition of (NH ) CrF6. The latter is pre- 4.3 pared by the interaction of hydrated CrF, with NH,F.HF, and it may also be reduced by hydrogen to yield CrF,. Several batches of NiF, were prepared by the hydrofluorination of either hydrated NiF, or hydrated NiCI,. One batch of AgF was prepared by hydrofluorination of AG,CO,. Methods described previously’ were used for the preparation of additional quantities of CeF, and of LaF,. An attempt to remove oxide from a KF-ZrF, mixture by hydrofluorination was unsuccessful. Runs at 60OOC failed to remove the oxide completely and, while this could be accomplished at 85OOC, the loss of ZrF, was sufficient to alter the composition to the point where the material was unsatisfactory for its intended purpose. A batch of CuF, was prepared for use as a carrier in certain spectrographic boron analyses. Material low in boron and silicon was requested for this purpose. Anhydrous CuF, was hydrofluorinated for 4 hr at 4OO0C, but this short period of treatment failed to reduce the boron content to a sufficiently low level. However, extending the period of hydrofluorination to 20 hr terial that was acceptable. A fuel mixture containing Li7 and nium was prepared for radiation damage studies. Since Li7 was available only as the carbonate, a preliminary run was made with normal Li,CO, UF, KF, NaF, and excess NH,F*HF to establish whether fusion of this mixture would yield an oxide-free product. After the prel iminary run proved successful the procedure was applied to the mixture containing Li’ and U2,’. The material was PERIOD ENDING JUNE 10, 1956 oxide free, but a sulfur content of 170 ppm was reported, most of which came from the LiiCO,. The fuel was subjected to 5 cycles, each of which entailed a 10- to 15-hr hydrogen treatment and 1 hr of hydrofluorination at 80OoC. The product then contained 45 ppm of sulfur and a trace of oxide, Hydrofluorination at 70O0C for 6 hr then produced an oxide-free product. LABORATORY-SCALE PURIFICATION OPE RATIONS F. L. Daley W. T. Ward With appropriate modifications, the standard hy- drofluorination-hydrogenation process was used to prepare a number of especially pure materials requested for various purposes. Of these only an NaF-ZrF,-UF, mixture containing additives of BaF,, LaF,, and RbF had not previously been pre- pared by the standard procedure. operational foci I- ities to transfer and dispense small samples (200 to 500 g), especially into apparatus for accurate evaluation of physical properties of materials, were constructed and used successfully during this quar- ter. There is evidence that direct transfer of the purified melt into the apparatus has significantly improved the purity of the test material and, ac- cordingly, increased confidence in the test results. Copper-I ined stainless steel reactors were used successfully in the purification operations. P ILOT-SC AL E PUR I FICATION OP ER AT IONS J. P. Blakely C. R. Croft J. Truitt e pilot-scale purification facility processed 68 es totaling approximately 1300 Ib of various de compositions for use in small-scale corro- sion testing, phase equilibrium studies, and phys- ical property studies. The bulk of the materiai was produced during February when the facility was operating on a threeshift, 24-hr-day basis. As a result, the backlog reported last quarter was eliminated and normal operations were resumed. ’B. J. Sturm, ANP Quat. Pmg. Rep. March 10, 1956. ORNL-2061, p 100. 121
- Page 55 and 56: i E ART FACILITY F. R. McQuilkin Co
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u 2.4. PRODUCTION OF FUELS<br />
c G. J. Nessle G. M. Watson<br />
L. G. Overholser<br />
I EXPERIMENTAL PREPARATION OF<br />
c<br />
tid<br />
VARIOUS FLUORIDES<br />
B. J. Sturm<br />
Continued use of structural metal fluorides for<br />
research necessitated <strong>the</strong> preparation of additional<br />
quantities of <strong>the</strong>se materials by <strong>the</strong> several methods<br />
developed previously. As in <strong>the</strong> past, use was<br />
made of chemical, x-ray, and petrographic examinations<br />
to establish <strong>the</strong> identity and purity of <strong>the</strong><br />
materials.<br />
Additional CrF, was prepared by hydrofluorination<br />
of anhydrous CrCI,, as well as by <strong>the</strong> <strong>the</strong>rmal<br />
decomposition of (NH ) CrF6. The latter is pre-<br />
4.3<br />
pared by <strong>the</strong> interaction of hydrated CrF, with<br />
NH,F.HF, and it may also be reduced by hydrogen<br />
to yield CrF,. Several batches of NiF, were prepared<br />
by <strong>the</strong> hydrofluorination of ei<strong>the</strong>r hydrated<br />
NiF, or hydrated NiCI,. One batch of AgF was<br />
prepared by hydrofluorination of AG,CO,. Methods<br />
described previously’ were used for <strong>the</strong> preparation<br />
of additional quantities of CeF, and of LaF,.<br />
An attempt to remove oxide from a KF-ZrF, mixture<br />
by hydrofluorination was unsuccessful. Runs<br />
at 60OOC failed to remove <strong>the</strong> oxide completely<br />
and, while this could be accomplished at 85OOC,<br />
<strong>the</strong> loss of ZrF, was sufficient to alter <strong>the</strong> composition<br />
to <strong>the</strong> point where <strong>the</strong> material was unsatisfactory<br />
for its intended purpose.<br />
A batch of CuF, was prepared for use as a carrier<br />
in certain spectrographic boron analyses. Material<br />
low in boron and silicon was requested for<br />
this purpose. Anhydrous CuF, was hydrofluorinated<br />
for 4 hr at 4OO0C, but this short period of<br />
treatment failed to reduce <strong>the</strong> boron content to a<br />
sufficiently low level. However, extending <strong>the</strong><br />
period of hydrofluorination to 20 hr<br />
terial that was acceptable.<br />
A fuel mixture containing Li7 and<br />
nium was prepared for radiation damage studies.<br />
Since Li7 was available only as <strong>the</strong> carbonate, a<br />
preliminary run was made with normal Li,CO,<br />
UF, KF, NaF, and excess NH,F*HF to establish<br />
whe<strong>the</strong>r fusion of this mixture would yield an<br />
oxide-free product. After <strong>the</strong> prel iminary run proved<br />
successful <strong>the</strong> procedure was applied to <strong>the</strong> mixture<br />
containing Li’ and U2,’. The material was<br />
PERIOD ENDING JUNE 10, 1956<br />
oxide free, but a sulfur content of 170 ppm was<br />
reported, most of which came from <strong>the</strong> LiiCO,.<br />
The fuel was subjected to 5 cycles, each of which<br />
entailed a 10- to 15-hr hydrogen treatment and 1 hr<br />
of hydrofluorination at 80OoC. The product <strong>the</strong>n<br />
contained 45 ppm of sulfur and a trace of oxide,<br />
Hydrofluorination at 70O0C for 6 hr <strong>the</strong>n produced<br />
an oxide-free product.<br />
LABORATORY-SCALE PURIFICATION<br />
OPE RATIONS<br />
F. L. Daley W. T. Ward<br />
With appropriate modifications, <strong>the</strong> standard hy-<br />
drofluorination-hydrogenation process was used<br />
to prepare a number of especially pure materials<br />
requested for various purposes. Of <strong>the</strong>se only an<br />
NaF-ZrF,-UF, mixture containing additives of<br />
BaF,, LaF,, and RbF had not previously been pre-<br />
pared by <strong>the</strong> standard procedure. operational foci I-<br />
ities to transfer and dispense small samples (200<br />
to 500 g), especially into apparatus for accurate<br />
evaluation of physical properties of materials, were<br />
constructed and used successfully during this quar-<br />
ter. There is evidence that direct transfer of <strong>the</strong><br />
purified melt into <strong>the</strong> apparatus has significantly<br />
improved <strong>the</strong> purity of <strong>the</strong> test material and, ac-<br />
cordingly, increased confidence in <strong>the</strong> test results.<br />
Copper-I ined stainless steel reactors were used<br />
successfully in <strong>the</strong> purification operations.<br />
P ILOT-SC AL E PUR I FICATION OP ER AT IONS<br />
J. P. Blakely C. R. Croft<br />
J. Truitt<br />
e pilot-scale purification facility processed 68<br />
es totaling approximately 1300 Ib of various<br />
de compositions for use in small-scale corro-<br />
sion testing, phase equilibrium studies, and phys-<br />
ical property studies. The bulk of <strong>the</strong> materiai<br />
was produced during February when <strong>the</strong> facility<br />
was operating on a threeshift, 24-hr-day basis. As<br />
a result, <strong>the</strong> backlog reported last quarter was<br />
eliminated and normal operations were resumed.<br />
’B. J. Sturm, ANP Quat. Pmg. Rep. March 10, 1956.<br />
<strong>ORNL</strong>-2061, p 100.<br />
121