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ORNL-1771 - Oak Ridge National Laboratory

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ANP QUr4RTERLY PROGRESS REPORT<br />

Additional irradiations of lnconel capsules con-<br />

taining fluoride fuels were carried out in the MTR.<br />

Only one capsule containing a UF3-bearing fuel<br />

has been examined, and it shows no corrosion.<br />

This is in contrast to the capsules containing<br />

UF,-benring fuel in which minor increases in<br />

penetration have at times been observed in the<br />

irradiated specimens as compared with the out-of-<br />

pile controls. However, it should be eniiphasized<br />

that even in the UF4-bearing capsules, the ap-<br />

pearance of small deviations from the controls<br />

could be due to experimental difficulties,<br />

Inspection of the previously described LlTR in-<br />

pile circulating-fuel loop, which failed prior to the<br />

startup, disclosed that the failure was caused by a<br />

break in the weld connecting the pump discharge<br />

nipple to the fuel line. Design revisions and<br />

refabrication of some components are in progress.<br />

Developmental work continued on a smaller loop<br />

for operation in an LlTR A-piece. Work on a loop<br />

for insertion in the MTR is described in Sec. 3,<br />

I 1<br />

Experimenta I Reactor Engineering. ”<br />

Development of equipment continued for in-pile<br />

stress-corrosion tests on lnconel in contact with<br />

fluoride mixtures, and testing of the MTR tensile-<br />

creep rig neared completion. Detailed examination<br />

was completed of an lnconel loop in which sodium<br />

was circulated at high temperature in the <strong>ORNL</strong><br />

Graphite Reactor, and no evidence of radiation-<br />

induced corrosion was found in the Inconel.<br />

Metal lographic examinntions were carried out in<br />

the hot cells on irradiated fuel plates for the<br />

Prutt & Vhitney Aircraft Division, and studies were<br />

made on anneal ing-out of fiss ion-fragment dorncsge.<br />

Work continued on examination of wire and multiple-<br />

plate type units for GE-ANP.<br />

MfR STATIC CORROSION TESTS<br />

W. E. Browning G. W. Keilholtz<br />

Solid State Division<br />

A new series of capsules was irradiated in the<br />

MTR to compare NaF-ZrF, fuels containing LJF,<br />

with those containing WF,. The property to be<br />

compared is the effect of fission on static eor-<br />

134<br />

J. B. Tricc<br />

Solid State Division<br />

A. J. Miller<br />

ANI‘ Proiect<br />

rosion of lnconel by the fuels at 1500OF. The<br />

series includes five capsules containing 1.79<br />

mole 76 UF,, 49.3 mole % ZrF,, and 48.9 mole %<br />

NirF and five capsules containing 1.74 mole %<br />

UF, 48.2 mole % ZrF,, and 50.1 mole 96 NaF.<br />

Analyses are being run to confirm the purity of the<br />

UF, with respect to UF, contamination. For<br />

every capsule, there will be an out-of-pile control<br />

capsule. Each fuel generates 1100 w/cm3 in the<br />

A-38 position in the MTR.<br />

Six capsules have been irradiated for the speci-<br />

fied two-week period. Five have been received<br />

at <strong>ORNL</strong> after irradiation; three of them have been<br />

opened and two have been examined -- one con-<br />

taining UF, and one containing UF,. Both capsules<br />

had been irradiated with the metal-liquid interface<br />

at 1500 k SOOF. The UF3-bearing capsule had<br />

experienced one temperature excursion to 1660 t<br />

5OoF for less than 30 sec, but the temperature of<br />

the UF,-beariiig capsule never exceeded 1550 5<br />

50‘F. The fuel in each capsule was frozen two or<br />

three times during its history. No evidence of<br />

corrosion or film could $e seen in the UF,-bearing<br />

Inconel capsule, There was subsurface void<br />

formation in the UF4-bearing lnconel capsule to a<br />

depth of about 2 mils. No intergranular corrosion<br />

or concentration of voids at the grain boundaries<br />

wos evident.<br />

Analytical samples of the irradiated fuel were<br />

taken with two sizes of drills. Theuranium concen-<br />

trations in the central and outer samples were<br />

identical, within experimental error (13%), and were<br />

of the value expected after burnup correction.<br />

Analyses for iron, chromium, and nickel gave the<br />

following results: Fe, 0.03 to 0.14 wt %; Ni, 0.01<br />

to 0.05 wt %; Cr, less than IOe4 wt %. There were<br />

no significant differences in the final iron, nickel,<br />

and chromium compositions between the two cap-<br />

sules. Analyses of the unirradiated fuels have<br />

not been completed.<br />

It would be unwise to draw conclusions on the<br />

basis of only one pair of samples; however, if<br />

these first results arc confirmed in future capsules,<br />

[IF, fuels may be considered quite desirable as<br />

far as radiation-indiiced corrosion is concerned.

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