ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory ORNL-1771 - Oak Ridge National Laboratory
A A Fig. 4.1. First Reflector-Moderated Reactor Critical Assembly. PERIOD ENDING SEPTEMBER 70, 7954 45
ANP QUARTERLY PROGRESS REPORT Measurements of neutron flux have been made in a vertical direction along a radius by using indium foils with and without cadmium covers. The foils are 10-mil aluminum-indium alloy, t6 in. in diameter, having an effective indium thickness of 3 x lo-' in., and the cadmium covers are 20 mils thick. The results of these measurements are given in Fig. 4.2. The values of the indium-cadmium fraction3 and the indium activation produced by neutrons having energies less than the cadmium cut-off are also plotted. A relative power, or fission-rate, JThe cadmium fraction by definition is the ratio of the difference between the bare and cadmium-covered acti- vations to the bare activation. 45 40 35 30 - 0 + 5 25 z L. 0 .- + D 0 - 20 > t 2 0 4 15 40 5, 0 0 2 4 6 distribution was made through the core along the radius that was used for the indium flux measure- ments by observing the activity of the fission fragments retained in aluminum foils placed in contact with uranium. Similar data, presented in Fig. 4.3, were obtainedwith the uranium and alumi- num enclosed in cadmium covers. The average uranium-cadmium fraction for the core is 0.33. The fission rates were measured on opposite sides of three uranium foils near the reflector, and the results are plotted. In each case - the rate was higher on the side toward the beryllium. Measurements will be made of the reactivity coefficients, as functions of the radius, of a few ORNL-LR-DWG 3017 0 8 io 12 14 16 20 22 RADIAL DISTANCE FROM CENTER OF CORE (in) Fig. 4.2. Radial Neutron Distribution at Mid-Plane of First Reflector-Moderated Reactor Critical Assembly. 46 io 08 06 z 2 4 cr LL 5 04 2 a u 02
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Fig. 4.1. First Reflector-Moderated Reactor Critical Assembly.<br />
PERIOD ENDING SEPTEMBER 70, 7954<br />
45
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