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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in. long, 18’4, in. wide, and 2% in, thick. The<br />
beryllium layer immediately below it was 34% in.<br />
long and 245/,, in. wide.<br />
The top layer and <strong>the</strong> corners of <strong>the</strong>,second<br />
beryllium layer were subsequently removed, and<br />
<strong>the</strong> resulting reflector was 8% in. thick. The<br />
new top layer was 18’) in. wide and 34% in.<br />
1 6.<br />
long, A second longitudinal traverse was <strong>the</strong>n<br />
made. The results are shown in Fig. 4.4.4, in<br />
which <strong>the</strong>.top lobe is plotted to a scale one-half<br />
that used to plot <strong>the</strong> end lobe.<br />
Two series of lateral traverses were also made<br />
at <strong>the</strong> side of <strong>the</strong> reactor at several distances<br />
from <strong>the</strong> mid-plane. For reflector thicknesses of<br />
118 and 8% in. <strong>the</strong> outer slab dimensions for<br />
each side reflector thickness were <strong>the</strong> same as<br />
those given above. The latitudinal variations of<br />
<strong>the</strong> fast-neutron leakage for <strong>the</strong> two reflector<br />
thicknesses are shown in Figs. 4.4.5 and 4.4.6.<br />
The curves show a slight asymmetry about <strong>the</strong><br />
center of <strong>the</strong> reactor, which is attributed to <strong>the</strong><br />
reflection of neutrons by <strong>the</strong> aluminum and steel<br />
structure on which <strong>the</strong> critical assembly rests.<br />
The area under each curve of Figs. 4.4.5 and<br />
4.4.6 is proportional to <strong>the</strong> counting rate observed<br />
at <strong>the</strong> corresponding distance from <strong>the</strong> mid-plane<br />
in <strong>the</strong> longitudinal traverses made at <strong>the</strong> top of<br />
<strong>the</strong> reactor. By integrating <strong>the</strong> results of <strong>the</strong> two<br />
longitudinal traverses over <strong>the</strong> distance from <strong>the</strong><br />
mid-plane, it was possible to determine that <strong>the</strong><br />
removal of <strong>the</strong> 2% in. layer of beryllium from <strong>the</strong><br />
top of <strong>the</strong> reactor increased <strong>the</strong> fast-neutron leak-<br />
age <strong>the</strong>re by a factor of 3.7.<br />
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PERIOD ENDfNG JUNE IO, 1956<br />
shmc<br />
<strong>ORNL</strong>-LR-DWG 44421<br />
MEASURED WITH 2- in.- DIA<br />
HORNYAK BUTTON<br />
TOP BERYLLIUM LAYER:<br />
48% x 34314 in.<br />
THE MTA AT THE TOP<br />
- OF THE REACTOR ARE<br />
PLOTTED TO A SCALE<br />
ONE-HALF THAT USE0<br />
FOR PLOT OF THE EN0<br />
Fig. 4.4.4. Polar Distribution of Fast-Neutron<br />
Leakage at Surface of 8kin.ofhick Reflector of<br />
Compact-Core Reflector-Moderated-Reactor Critical<br />
Assembly.<br />
259