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the Molten Salt Energy Technologies Web Site

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ANP PROJECT QUARTERLY PROGRESS REPORT<br />

DWG. 17448<br />

Fig. 5. 2. Vertical Section Along Axis of Reflector-Moderated Reactor Assembly.<br />

Some measurements have been made<br />

that indicate <strong>the</strong> neutron flux and<br />

power distributions in various parts<br />

of <strong>the</strong> array. The flux was measured<br />

in <strong>the</strong> usual manner with base- and<br />

cadmium-covered- indium foils and <strong>the</strong><br />

power or fission-rate data were derived<br />

froin fission fragments collected on<br />

aluminum foils placed in contact with<br />

<strong>the</strong> uranium.<br />

so<br />

In Fig. 5.3 are shown neutron-flux<br />

t 1- avers es me a su re d h o r i zon t a 1 1 y a 1 ong<br />

row 12 in <strong>the</strong> mid-plane of <strong>the</strong> reactor,<br />

and in Fig. 5.4 are <strong>the</strong> data obtained<br />

along a central traverse of cell 0-12,<br />

perpendicular to <strong>the</strong> mid-plane. In<br />

both cases, <strong>the</strong> activations of bare-<br />

and cadmium-covered- indium foils and<br />

<strong>the</strong>ir difference are shown. These<br />

results are typical of t,hose obtained

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