Abstract
A detailed study was made of the thermal neutron flux distribution in the Oak Ridge Research Reactor. Results indicated that rather large flux gradients exist radially across the MTR type fuel element employed in this reactor and that these gradients are strongly dependent on the fuel concentration in the element being investigated as well as that of the adjacent elements. The technique used to measure flux consists of measuring the induced activity in a 20- mll cobalt wire. It was concluded that when a heavily burned element is placed next to a new element, the flux will peak in the burned element and show a depression in the new element. The placing of large water gaps such as that which exists between the fuel and the cadmium sections in the shim rod appeared to cause large peaks in the adjacent elements. (M.C.G.)
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