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
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ANP PROJECT PROGRESS REPORT<br />
PREPARATION OF SOLUTIONS OF LaF3,<br />
BaF,, AND RbF IN NaF-ZrPpUF4<br />
F. L. Daley<br />
W. T. Ward<br />
A special preparation containing La F,-Ba F,-RbF<br />
(2.8-1.0-1.1 mole %) dissolved in a standard NaF-<br />
ZrF,-UF, (50-46-4 mole %) mixture was requested<br />
for use in determining whe<strong>the</strong>r <strong>the</strong> introduction of<br />
<strong>the</strong> simulated fission products would produce sip<br />
nificant viscosity changes. The usual methods of<br />
purification and filtration were used, and <strong>the</strong> equip-<br />
ment was modified so that small filtered samples<br />
could be dispensed directly into <strong>the</strong> tubes used for<br />
<strong>the</strong> viscosity measurements. The resulting prepara-<br />
tion was studied to obtain some indication of <strong>the</strong><br />
solubilities of <strong>the</strong> fission products at 8WC in<br />
this solvent. It is believed that <strong>the</strong> solubility of<br />
LaF, may be typical of <strong>the</strong> solubilities of <strong>the</strong> rare-<br />
earth fluorides, since LaF, presumably forms solid<br />
solutions with o<strong>the</strong>r rare-earth fluorides.<br />
Two filtered samples of <strong>the</strong> NaF-ZrF,-UF, mix-<br />
ture without <strong>the</strong> additive were obtained, and two<br />
more samples were obtained after <strong>the</strong> fission-<br />
product mixture was added. A small portion of<br />
solution -which remained unfiltered in <strong>the</strong> reactor<br />
after withdrawal of all <strong>the</strong> samples was also re<br />
covered for analysis. All filtrations were performed<br />
No F-Zr F,-U F4<br />
at approximately 800 f 10°C. During <strong>the</strong> course of<br />
<strong>the</strong> viscosity measurements, <strong>the</strong> presence of a<br />
finely divided solid material was detected in <strong>the</strong><br />
molten mixture, and a small sample of <strong>the</strong> solid<br />
was obtained by decantation. The solid was<br />
tentatively jdsntified by x-ray diffraction analysis<br />
as free LaF,, with occluded solvent. The results<br />
of chemical analyses of all <strong>the</strong> samples taken<br />
are presented in Table 2.2.15.<br />
The results indicate no greater concentration of<br />
additives in <strong>the</strong> unfiltered portion (reactor heel)<br />
than in <strong>the</strong> filtered samples, and consequently it<br />
appears that <strong>the</strong> additives were completely dis-<br />
solved at 800OC. From visual observations, how-<br />
ever, <strong>the</strong> solution seemed to be essentially satu-<br />
rated at this temperature. The saturating phase<br />
appeared to be free LaF,, and <strong>the</strong> probable solu-<br />
bility value for this compound at 800OC seems to<br />
be about 2.5 wt %. During <strong>the</strong> preparation of this<br />
material no particular effort was made to control<br />
<strong>the</strong> filtration temperature at exactly 80O0C, and<br />
visual observations could not be made conveniently<br />
enough to fix a liquidus temperature; however, <strong>the</strong><br />
order of magnitude of <strong>the</strong> solubility of LaF, in<br />
NaF-ZrF4-UF, (50-46-4 mole %) appears to be<br />
about 2 mole 96 at 80OOC.<br />
TABLE 2.2.15. CHEMICAL COMPOSITION OF NaF=ZrF4-UF4 SAMPLES BEFORE AND AFTER<br />
INTRODUCTION OF La F3-BaF2-RbF TO SIMULATE FISSION PRODUCTS<br />
Filtration temperature, 8OO0C<br />
Maior Constituents (wt %) Impurities (ppm)<br />
Na zr U Bo La Rb F Ni Cr Fe<br />
Sample 1 10.7 38.8 8.8 0 0 0 41.9 90 50 65<br />
Sample 2 10.3 38.8 8.7 0 0 0 42.5 35 40 45<br />
Theoretical 10.41 37.98 8.62 0 0 0 42.99<br />
NaF-ZrF4YF,, plus<br />
La FB-Ba FZ-Rb F<br />
Sample 3 9.2 35.7 8.0 1.23 2.62 0.86 41.7 80 50 90<br />
Sample 4 9.5 34.6 7.7 1.16 2.56 1.00 41.8 100 65 160<br />
Reactor heel 8.9 37.8 8.2 1.18 2.31 0.87 41.2 25 65 150<br />
Theoretical 9.64 35.17 7.98 1.25 3.40 0.82 41.74<br />
Solid detected during 18.1 0.62 26.6<br />
108<br />
viscosity measurements<br />
.<br />
W<br />
.