ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
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84<br />
and <strong>the</strong>re was never any evidence sf a soEuble telluride species, However,<br />
considerable evidence existed that tellurium "moved" through salt from one<br />
point to ano<strong>the</strong>r in a salt system.<br />
The hypo<strong>the</strong>sis was that <strong>the</strong> tellurium<br />
actually moved as a low-pressure pure metall vapor and not as a reacted<br />
species. 'Ehe most representative experimental system dle~el~iped for ex-<br />
posing metal specimens eo tel%urim invo%~ed suspendling <strong>the</strong> spe~imen~ in<br />
a skirred vessel of salt: with granu%@S 0% Cr3Te4 and CPgT@6 lying at <strong>the</strong><br />
bottom of <strong>the</strong> salt. A very low partial pressure of tePEurim was in equi-<br />
librim with <strong>the</strong> Ck3T@4 and C~gTe6~ which resulted in BaStePEOy-M speci-<br />
mens w ith crack severities similar to those noted in samples from <strong>the</strong><br />
MSRE, NUEIBRH.LS samples were exposed to salt that contained tellurium, and<br />
<strong>the</strong> most important finding was that modified Hastelloy-N c~ntai~~ing 1 to 2% niobiW had good reSistaXlC@ to eTRb8-i&e%ement by tt?llUgf-UlR (Fig. 16).<br />
h e Sekfe.5 Qf experiments Was Tun to inVeStfgatf2 <strong>the</strong> effects O f <strong>the</strong><br />
oxidation state of tellurium-containing salt on <strong>the</strong> temdency for cracks<br />
to be f o ~ ~ ~ me d , supposition being examined was that <strong>the</strong> salt might be<br />
made reducing enough to tie up <strong>the</strong> tellurium in some fnnocuo~~ metal com-<br />
plex.<br />
The salt was made more oxidizing by adding WiF2 and more reducing<br />
by adding elemental beryblim. The experiment had electrochemical probes<br />
for determining <strong>the</strong> ratio of urarnim in <strong>the</strong> +4 state (UPq) to that im <strong>the</strong><br />
4-3 state (UF3) as an indicator of <strong>the</strong> sxfdation state of <strong>the</strong> salt,<br />
sile spe~imens of standard ~asteiloy-~ were suspended in <strong>the</strong> salt for<br />
about 260 k at 700°C.<br />
<strong>the</strong> specimens were inserted so that each set of specimens was exposed to<br />
one condition. After exposurep <strong>the</strong> specimens were strained to failure and<br />
were examined metallographically to determine <strong>the</strong> extent of cracking e '%he<br />
results of measurements at several oxidation states are shown in Fig. 17.<br />
~t ~4+/~3+ ratios sf QO or less, very little cracking occurred, and at<br />
ratios above 80, <strong>the</strong> cracking was extensive. These observations offer<br />
encouragement. that 8 reactor could be operated in a chemical regime where<br />
<strong>the</strong> tellurium would not be embrittling even to standard Hastelloy-N.<br />
least le6% of <strong>the</strong> uranium would need to be in <strong>the</strong> +3 oxidation state<br />
(UF3js amd this eonditi~n seems quite reasonable from chemical and prac-<br />
tical considerations.<br />
Ten-<br />
The oxidation state of <strong>the</strong> salt was stabilized, and<br />
At