ORNL-2106 - the Molten Salt Energy Technologies Web Site
ORNL-2106 - the Molten Salt Energy Technologies Web Site
ORNL-2106 - the Molten Salt Energy Technologies Web Site
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ANP PROJECT PROGRESS REPORT<br />
transfer calculations of Robinson and Weekesl’<br />
were modified to apply to <strong>the</strong> presently planned<br />
position for <strong>the</strong> loop in <strong>the</strong> LlTR by using certain<br />
simplifying assumptions. The tip of <strong>the</strong> loop is<br />
to be 1.5 in. below <strong>the</strong> center line of <strong>the</strong> reactor.<br />
This is more than 4.5 in. below <strong>the</strong> position of<br />
maximum flux. The flux measured near <strong>the</strong> fuel<br />
tube in <strong>the</strong> previously operated loop” was taken<br />
as <strong>the</strong> depressed flux for that loop. it was assumed<br />
that <strong>the</strong> flux depression was <strong>the</strong> same for corre-<br />
sponding parts of <strong>the</strong> present loop. The difference<br />
in shape of <strong>the</strong> flux profile for <strong>the</strong> two loop po-<br />
sitions was ignored in calculating <strong>the</strong> fuel tube<br />
wal I temperature differential. Fi s sion-product<br />
poison contributions to <strong>the</strong> macroscopic cross<br />
section of <strong>the</strong> fuel were assumed to be negligible.<br />
12M. T. Robinson and D. W. Weekes, Design Calcu-<br />
lations for a Miniature Higb-Temperature In-Pile Circu-<br />
lating Fuel Loop, <strong>ORNL</strong>-1808 (Sept. 19, 1955).<br />
3<br />
-<br />
3<br />
0<br />
x 2<br />
B<br />
s<br />
J<br />
J<br />
w<br />
m<br />
3<br />
c<br />
J<br />
W<br />
3<br />
LL<br />
t’<br />
X<br />
3<br />
J<br />
LL<br />
240<br />
0 0<br />
The transmission coefficient for neutrons in <strong>the</strong><br />
fuel was determined from work reported by Holmes,13<br />
and it was used in conjunction with <strong>the</strong> flux distri-<br />
bution along <strong>the</strong> loop, as shown in Fig. 4.2.12,<br />
to determine <strong>the</strong> total loop power.<br />
Finally, to find <strong>the</strong> temperature differential<br />
through <strong>the</strong> lnconel fuel tube wall, <strong>the</strong> curves of<br />
heat transfer variations along <strong>the</strong> loop designated<br />
Mark Vlll in <strong>the</strong> work of Robinson and Weekesl’<br />
were modified for <strong>the</strong> higher total power of <strong>the</strong><br />
loop being investigated. A plot of <strong>the</strong> calculated<br />
temperature differential through <strong>the</strong> tube wal I vs<br />
<strong>the</strong> position on <strong>the</strong> loop for proposed operating<br />
conditions is presented in Fig. 4.2.13. The maxi-<br />
mum combined temperature corrections for all three<br />
errors totaled 3sOC.<br />
13D. K. Holmes, Problems of Neutron Population in<br />
Localized Absorbers, <strong>ORNL</strong> CF-56-1-141 (Jan. 27,<br />
1956).<br />
50 00 4 50 200<br />
DISTANCE ALONG LOOP FROM INLET TO COOLED SECTION (cm)<br />
W<br />
uwwmwub<br />
<strong>ORNL</strong>-LR-DWG 14747 .<br />
Fig. 42.12. Calculated Profile of Flux at Fuel Tube Surface Along <strong>the</strong> LlTR Vertical In-Pile Loop. .<br />
2 50<br />
a<br />
L