ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
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0 20 40 60 80 IO0 120 140 160<br />
I, DiSrANCE FROM SO?IRCC (cm)<br />
Fig. 12.1. Thermal-Neutron Flux in Sugar Solu-<br />
tion.<br />
12.3, respectively. Plain water curves are also<br />
shown for comparison. The gamma-ray water curve<br />
is higher than the normal LTSF water curve because<br />
of ihe high-energy capture gamma ray from the<br />
lnconel window of the tank (see preceding discus-<br />
s ion).<br />
Since the medium contained almost as much hy-<br />
drogen and oxygen as does plain water and con-<br />
tained them in the same ratio, nogeometric correction<br />
was made in calculating the effective removal cross<br />
section, ur. The average uT for the range of 90 to<br />
140 cm from the source was 0.750 barn. This com-<br />
pares with a value of 0.81 i 0.05 barn from an LTSF<br />
measurement behind a slab of graphite that con-<br />
tained 51.3 g/cm2 of carbon, which corresponds to<br />
PERIOD EMDlNG SEPTEMBER 70, 7954<br />
10-3 L 1 ............... ! .... I 1 ______.._.....<br />
70 80 90 100 1.10 (20 430<br />
I, DISTANCE FROM SOURCE (cm)<br />
Fig. 12.2. Fast-Neutron Dose in Sugar Solution.<br />
the sugar-water solution at 145 cm,<br />
In order to observe the neutron attenuation in a<br />
medium removed from the source, the sugar-water<br />
solution is being placed in a 36-in.-long aluminum<br />
tank located 48.2 cm from the source. Thermal-<br />
neutron, fast-neutron, and gamma-ray measurements<br />
will be made in the tank. The measurements at<br />
the interface will indicate the difference in neutron<br />
age between water and the sugar solution for the<br />
more penetrating of the fission neutrons.<br />
165