ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
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A N P Q UA R I-EKIY PRO G R ESS R E P ORT<br />
The paition of a hot leg shown in Fig. 6-14 was<br />
taken from an Inconel thermal-convection loop which<br />
had circulated UF, (2,l wt !% UF, in 2.4 wt %<br />
total U) in NaF-ZrF, (53-47 innlc %) for 508 hr at<br />
a hot-leg temperature of 1500°F. The fluoride mix-<br />
ture was drained from the loop at the operating<br />
temperature to ascertain whether the layers pre-<br />
viously noted had formed during cooling of the loopa<br />
Since the layer was again present, it is now ton-<br />
sidered to have formed during operation. This<br />
conclusion was further strengthened when the<br />
metal lographic examination revealed e diffusion<br />
zone between the layer and the base metal. An<br />
examination of the layer by ii microspark spectro-<br />
graphic: technique3 showed it to be predominantly<br />
zirconium. Since this technique is not sensitive<br />
to uraniuii~, the layer could also contoin uranium.<br />
Thwe is some indication that some of the LJF,<br />
dissociates to produce uranium metal, which re-<br />
duces some of the ZrF, to produce zirconium metal.<br />
The accuracy of the analytical determination for<br />
zirconium is not sufficient to reveal ;he reaction<br />
products postulated, since some zirconium is also<br />
lost by sublimation.<br />
graphic exarninatian. The voids did not appear to<br />
be the same QS those normally found, and it is<br />
thought that they were formed when brittle inter-<br />
metallic compounds were pulled out of the base<br />
metal during polishing. No hot-leg attack could be<br />
found, as shown in Fig. 6.15, but there was a layer<br />
0.5 mil thick on the hot-leg surface. This layer<br />
was also reported to be predominantly zirconium.<br />
It has been definitely established that the use of<br />
UF, rather than UF, in ZrF4-base mixtures will<br />
lower the corrosive attack and mass transfer in<br />
lnconel systems. s-lO\Mevei, it has been found to be<br />
impossible to dissolve sufficient UF, in ZrF4-base<br />
mixtures to obtain fuels of interest for high-temper-<br />
ature ienctms, To obtain a fuel with sufficient<br />
uranium, it would be necessary to use a mixture<br />
of UF, and UF,. Data obtained from loops oper-<br />
ated with such mixtures and with standard UF,-<br />
bearing mixtures are presented in Table 6.7. The<br />
data show clearly that a mixture of UF, and UF,<br />
produces less attack than UF, alone, but the mixture<br />
does not eliminate the attack, as is the case<br />
with UF, alone.<br />
In another lncowel loop in which UF, in NaF-<br />
Effect of<br />
ZrF, wos circulated for 2000 hs at 1500°F,<br />
UF, in AJkali-Metal Base Fuels<br />
some<br />
7<br />
voids were found to a Cllcpth of 4 mils upon metallo- It has been found that more UF, can be dissolved<br />
'Examination made by C. Feidmon, Chemistry Division. in the alkal i-metal-base fluoride mixtures than in<br />
the ZrF4-base mixtures, and therefore additional<br />
tests were made with NuF-KF-LiF (1 1.5-42.0-46.5<br />
36<br />
d<br />
mole %) containing UF, UF,, and mixtures of the<br />
two.<br />
.<br />
. 8<br />
0<br />
.<br />
4p<br />
.<br />
.<br />
PI.<br />
a<br />
Fig. 8.15. Hot-Reg Surface ab Inconel Loop<br />
After Circulating UF, in HaF-ZrF4 for 2000 ha<br />
OF. Unetched. 250X. Reduced 36%.<br />
a<br />
5<br />
.