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 />
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DISTANCE FROM SHIELD SURFACE (crn)<br />
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Fig. 15.3. Fast-Neutron Dose Rate Measure-<br />
ments in Water Near GE-ANP R-1 Mockup.<br />
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DISTANCE FROM SHIELD SURFACE (cm)<br />
Fig. 15.4. Gamma-Ray Dose Rate Measurements<br />
in Water Near GE-ANP R-1 Mockup.<br />
mockup emits neutrons in a direction more favorable<br />
for ground scattering. The intensity from <strong>the</strong> G-E<br />
shield peaks at about 55 and 120 deg from <strong>the</strong><br />
reactor-detector center line and is symmetrical<br />
about <strong>the</strong> reactor-detector axis.<br />
Measurements were also made of <strong>the</strong> <strong>the</strong>rmal-<br />
neutron flux and <strong>the</strong> gamma-ray dose rates within<br />
<strong>the</strong> detector tank at an altitude of 195 ft. The<br />
G-E reactor shield was a horizontal distance of<br />
64 ft from <strong>the</strong> detector tank, and, for <strong>the</strong>se meas-<br />
urements, five 1-in.-thick lead slabs were installed<br />
1 ft from <strong>the</strong> rear face (reactor side) of <strong>the</strong> tank.<br />
The lead slabs simulated <strong>the</strong> shielding in <strong>the</strong> crew<br />
compartment.<br />
A knowledge of <strong>the</strong> <strong>the</strong>rmal-neutron flux di stri-<br />
bution in <strong>the</strong> detector tank is useful in extending<br />
<strong>the</strong> fast-neutron dose rate measurements into<br />
regions where <strong>the</strong> intensity is too low to be meas-<br />
ured with <strong>the</strong> dosimeter. This distribution is also<br />
necessary for predicting <strong>the</strong> capture gamma-ray<br />
intensity to be expected in <strong>the</strong> crew shield. The<br />
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