ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
You also want an ePaper? Increase the reach of your titles
YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.
.<br />
-<br />
7<br />
6<br />
5<br />
$ 4<br />
OT<br />
I-<br />
ul<br />
E 3<br />
3<br />
t-<br />
a<br />
3<br />
E 2<br />
1<br />
0<br />
203<br />
10-1 10'<br />
RUPTURE TIME (hr)<br />
<strong>ORNL</strong> -DWG 67-7941<br />
Fig. 16.6. Comparutive Rupture Strains for Various Heats of Hastelloy N Irradiated and Tested at 1200'F.<br />
We removed a second set of Hastelloy N speci-<br />
mens in June 1967. The specimens removed from<br />
<strong>the</strong> core had been at temperature for 5500 ht and had<br />
accumulaied a peak <strong>the</strong>rmal dose of approximately<br />
4 i lo2') neutroms/ctn'. The core specimens were<br />
modified alloys containing approximately 0.5% Ti<br />
(heat 31545) and 0.5% Zr (heat 21554). A stringer<br />
of vessel specimens was also removed. These<br />
specimens had been exposed to <strong>the</strong> MSRE cell<br />
environment for about 11,000 hr and had accumulated<br />
a peak <strong>the</strong>rmal dose of about 3 x 10'' neutrons/cm2.<br />
The vessel specimens were made of <strong>the</strong> same heats<br />
used in constructing <strong>the</strong> MSRE.<br />
We have not completed <strong>the</strong> mechanical testing of<br />
<strong>the</strong>se m a t eria Is, but preliminary metallo graphic<br />
studies have been completed The primary concern<br />
with <strong>the</strong> vessel specimen was whe<strong>the</strong>r <strong>the</strong>y were<br />
being nitrided by <strong>the</strong> cell environment. Figure 16.7<br />
shows <strong>the</strong> surface of heat 5085. There is no evi-<br />
dence of^ nitriding, and <strong>the</strong> maximum depth of oxida-<br />
tion is about 0.003 in. The specimen taken from<br />
1 o3<br />
heat 5065 happened to be a weld made in construct-<br />
ing <strong>the</strong> stringer. This specimen is shown in Fig.<br />
16.8. The amount of surface oxidation is greater,<br />
but <strong>the</strong> depth of oxidation is still. small, and <strong>the</strong>re<br />
is no evidence of nitriding.<br />
Heat 21545 contained 0.5% Ti, arid our main con-<br />
cern was whe<strong>the</strong>r <strong>the</strong> alloy would corrode in <strong>the</strong><br />
fused salt environment. Figure 16.9 shows that<br />
<strong>the</strong>re is some slight surface reaction but no ex-<br />
tensive corrosion. Heat 21554 contained 0.5% Zr,<br />
and we were again concerned with <strong>the</strong> corrosion re-<br />
sistance. Figure 16.10 shows <strong>the</strong> surfaces of <strong>the</strong><br />
surveillance specimens of this heat and indicates<br />
<strong>the</strong> lack of significant corrosion.<br />
Thus we are encouraged by <strong>the</strong> observations that<br />
(1) <strong>the</strong> MSRE grades of Hastelloy N are not being<br />
oxidized at a high rate, and <strong>the</strong>re is no evidence of<br />
nitriding in <strong>the</strong> cell environmeni; and (2) <strong>the</strong> small<br />
zirconium and titanium additions that we are making<br />
to Hastelloy N do not appear detrimental.<br />
i<br />
I<br />
I.<br />
.rO4