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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 />

.

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