ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
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ANP QUARTERLY PROGRESS REPORT<br />
Fig. 1.8.<br />
Weld Crack.<br />
Cross Section Through Thermocouple<br />
below criticality or at very low power levels.<br />
Samples were withdrawn by pressurizing <strong>the</strong> pump<br />
bowl sufficiently to cause flow through a heated<br />
lnconel tube into a sampling device, which was<br />
constructed to allow line flushing before col-<br />
lection of <strong>the</strong> sample.<br />
Analyses of <strong>the</strong> samples were carried out by<br />
<strong>the</strong> ANP Analytical Chemistry Group and are<br />
shown in Table 1.1. As may be seen, <strong>the</strong><br />
chromium content of <strong>the</strong> fuel was essentially<br />
constant at 100 ppm after 155 hr of circulation<br />
of <strong>the</strong> fuel carrier through <strong>the</strong> reactor. If corrosion<br />
of <strong>the</strong> lnconel is assumed to have been uniform<br />
over <strong>the</strong> surface of <strong>the</strong> system - and since it was<br />
operating iso<strong>the</strong>rmally during this period, such<br />
an assumption is reasonable - <strong>the</strong> chromium con-<br />
centration of 100 ppm would represent about 0.5<br />
20<br />
TABLE 1.1. ARE FUEL SAMPLE ANALYSES<br />
Hours After<br />
Filling with<br />
Barren Carrier<br />
19<br />
60<br />
110<br />
1 55<br />
157<br />
178<br />
182<br />
205<br />
242<br />
24 6<br />
268<br />
286<br />
3 07<br />
Uranium Chromium<br />
(wt X) (PPm)<br />
1.84<br />
3.45<br />
5.43<br />
9.54<br />
12.21<br />
12.27<br />
12.54<br />
12.59<br />
13.59<br />
81<br />
90<br />
102<br />
100<br />
150<br />
190<br />
2 00<br />
205<br />
300<br />
320<br />
37 8<br />
420<br />
445<br />
mil of attack on <strong>the</strong> Inconel.<br />
As was anticipated, <strong>the</strong> chromium content of<br />
<strong>the</strong> melt was found to increase a few hours after<br />
each addition of fuel concentrate (Na,UF,). By<br />
<strong>the</strong> time <strong>the</strong> final sample was taken, after 307 hr<br />
of molten fluoride circulation, <strong>the</strong> chromium content<br />
was found to be 445 ppm. Again, if a uniform<br />
rate of attack of <strong>the</strong> lnconel is assumed and if<br />
<strong>the</strong> removal of circulated material from <strong>the</strong> system<br />
during this time (to maintain desired pump liquid<br />
level) is taken into account, this chromium content<br />
would represent about 5 mils of attack on <strong>the</strong><br />
lnconel system. If <strong>the</strong> data in Table 1.1 are<br />
plotted as chromium content vs time, it is seen<br />
that <strong>the</strong> chromium content had begun to level off<br />
by <strong>the</strong> time <strong>the</strong> final sample was taken. A projection<br />
of <strong>the</strong> slope of <strong>the</strong> chromium curve indicates<br />
a maximum chromium concentration of about<br />
600 ppm after several hundred hours of operation.<br />
There is no doubt that mass transfer of chromium<br />
metal began soon after power operation started,<br />
since <strong>the</strong>re were <strong>the</strong>n large temperature differentials<br />
across portions of <strong>the</strong> system. Sampling<br />
was not possible at this time and could not, of<br />
course, have given information on mass transfer.<br />
Heat transfer characteristics of <strong>the</strong> ARE did not<br />
appear to have changed during its 150 Mwhr of<br />
operation, and so whatever mass transfer occurred<br />
was unimportant. Details of mass transfer will<br />
be studied when sectioning of <strong>the</strong> equipment<br />
becomes possible.