ORNL-2106 - the Molten Salt Energy Technologies Web Site

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PERlOD ENDlNG JUNE IO, 1956
TABLE 4.3.1. SEDIMENTATION OF NlF2 IN MOLTEN NaF-ZrFq (SO-SO mole %)-AT 6OO0C
Relative Position
of Sampling
1 (top)
2
3
4
5 (bottom)
Initially
Nickel Concentration (wt %)
After After After After
0.5 hr 2 hr 8 hr 72 hr
lnltial Nickel Content* - ““2 wt %
1.60 0.28 0.20
1.74 0.73 0.30 0.22 0.20
1.72 1.7(2 2.20 1.40 0.21
1.78 1.86 2 62 3.48 1.23
2 13 2.02 3.02 3.54 2.99
Initial Nickel Content* - 1 wt %
1 (top) 0.22
2 0.30 0.16
3 0.3 1 0.17
4 1.71 0.18
5 (bottom) 3.06
‘The nickel was added as NiFT
TABLE 4.3.2. SEDIMENTATION OF NiFZ IN MOLTEN NaF-ZrF4-UF4 (48-48-4 mole %) AT 6OO0C
Re’ative Position
of Sampling
1 (top) 1.26
Initial Ni Content - 2 wt %
Nickel Concentration (wt %)
Initial Ni Content - 1 wt X
Initial Ni Content - 0.5 wt %
After 2 hr After 48 hr After 2 hr After 48 hr After 48 hr
2 1.23 0.25 0.36 0.18 0.24
3 2.12 0.34 0.40 0.20 0.33
4 2.78 2.75 2.53 0.47 0.22
5 (bottom) 2.81 6.94 3.08 0.85
temperatures in an effort to develop a UF, desorption
procedure which avoids UF, decomposition.
The decomposition reaction would lead to uranium
being held up on the NaF bed and would thus
necessitate a subsequent recovery step. Tests
were conducted by saturating an NaF bed with UF
at 100°C and then heating the bed, as a close3
at the desired temperature for 1 to 4 hr. In
some of the tests the bed was subjected to os much
ture cycle. However, no significant correlations
were apparent as to the effect of UF, pressure or
length of time of treatment. The residual uranium
content in several tests at 400OC varied in the
range 18 to 26%. At 300°C the decomposition ef-
fect was much less, a residual uranium content of
2% being produced. Use of excess F, (10 psia) in
tests at 4OOOC also resulted in less decomposition,
with residual uranium contents of 8 to 14%.
as 55 psia UF, pressure during the high-tempera- The residual uranium present in the product of all
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