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ORNL-1816 - the Molten Salt Energy Technologies Web Site

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L<br />

.<br />

PERIOD ENDING DECEMBER 70, 7954<br />

where R, is <strong>the</strong> island radius, R, s <strong>the</strong> outer and this curve is also shown in Fig. 2.3. The<br />

radius of <strong>the</strong> fuel region, and 7is <strong>the</strong> <strong>the</strong>rmal age. "<br />

<strong>the</strong>rmal absorption rate" plotted is CI direct<br />

Evidently <strong>the</strong> absorption rate depends only on two measure of <strong>the</strong> neutron leakage - <strong>the</strong> higher this<br />

parameters: R,/R and 7/R:. rate <strong>the</strong> lower <strong>the</strong> leakage.<br />

For <strong>the</strong> source located at R,, <strong>the</strong> result is<br />

2<br />

A =-<br />

2 T 7<br />

For a uniform source throughout <strong>the</strong> fuel region, <strong>the</strong> Eesult is<br />

(3)<br />

Equations 1, 2, and 3 were evaluated by numerical<br />

t integration for R2/Rl = 1.67 and 7/R: = 0.33,<br />

0.44, and 0.55. The plots are shown in Fig. 2.3.<br />

For <strong>the</strong> case R, = 0, Eq. 1 reduces to<br />

c<br />

-<br />

-T/Rf 71 /2<br />

e erfc - ,<br />

R2<br />

ertrrn<br />

<strong>ORNL</strong>-LR-DWG 4499<br />

0.222 0 222 0.333 0.444 0.555 0.666<br />

0.9 I , , I I I I I I<br />

(; /]<br />

2<br />

[l + - 1) x cot<br />

PROPOSED ART INSTALLATIONS<br />

A. P. Fraas F. R. McQuilkin<br />

Aircraft Reactor Eng i neer i ng Div i s ion<br />

A study has been made of <strong>the</strong> various types of<br />

facilities suitable for <strong>the</strong> operation of <strong>the</strong> Aircraft<br />

Reactor Test. In addition to <strong>the</strong> obvious require-<br />

ments for shielding, heat dumps, and auxiliary<br />

equipment, it is essential from <strong>the</strong> hazards stand-<br />

point that provision be made to contlclin <strong>the</strong><br />

products resulting from a nuclear accideni and/or<br />

chemical reaction of all combustibles in <strong>the</strong><br />

installation, minimize <strong>the</strong> likelihood of serious<br />

damage from an explosion caused by sabotage or<br />

bombing, and remove and dispose of volatile<br />

fission products evolved during <strong>the</strong> course of<br />

operation. With <strong>the</strong>se criteria in mind, CI series<br />

of four basic reactor installations was considered;<br />

each differed in some fundamental characieristics<br />

from <strong>the</strong> o<strong>the</strong>rs. The four installations are as<br />

follows: (1) an open test unit mounted over a<br />

water-cooled pan at <strong>the</strong> National Reactor Testing<br />

Station (NRTS), (2) a circular Quonset type of<br />

hemispherical building, (3) a water-walled tank,<br />

and (4) a reactor submerged in a pool of water.<br />

Fig. 2.3. Thermal Absorption Rate in Ma<strong>the</strong>- ators, blowers, a control system, and a .FiIl-and- Fill-andmatical<br />

Model of Reflector-Moderated Reactors. drain system. These components would operate<br />

..<br />

29

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