Patent Number: 043115608
Section: claims

1. A stabilizing device for a nuclear reactor control rod, the rod being adapted for telescoping movement within a guide tube having an upward flow of liquid coolant therethrough comprising: a base section for rigidly connecting the upper end of the device to the lower end of the poison-bearing portion of the rod;  cantilevered spring means spaced about and extending longitudinally downward from the outer circumference of the base means to form an open-ended hollow inner region;  said cantilevered spring means having shoulders thereon for contacting the guide tube wall and providing an interference fit therebetween having substantially uniform radial forces distributed around the inner walls of the guide tube whereby the rod is centered within the guide tube and may longitudinally move in the tube; and  whereby at least some of the liquid coolant may bypass the shoulders through said hollow inner region.  an open-ended, hollow elongated member rigidly connected to and extending longitudinally downward from the lower end of the poison-bearing portion of the rod, the member having a transverse outer cross section smaller than that of the inside of the guide tube;  interference means projecting outwardly from the elongated member and cooperating with the member and the inside wall of the guide tube, for centering the rod within the guide tube; and  flow means formed on the elongated member for defining a flow path whereby liquid entering the hollow region within the elongated section may exit the elongated section above the interference means. 2. The device recited in claim 1 wherein the shoulders are on the lower end of each spring. 3. The device recited in claim 1 wherein each shoulder is intermediate the end of a spring, and wherein the lower ends of the springs are joined by a common ring which defines the entrance to the hollow inner region. 4. The device recited in claims 2 or 3 wherein the total shoulder area for contacting the tube is at least 1/2 the cross-sectional area of the tube. 5. The device recited in claim 4 wherein the spring constant at the shoulder of each spring is between 0.01 and 0.05 inches per pound. 6. The device recited in claim 5 wherein the spaces between the springs provide a flow path for coolant to bypass the shoulders. 7. In a nuclear reactor control rod of the type having neutron poison within a sealed container adapted for telescoping movement within a guide tube having an upward flow of liquid coolant therethrough, the improvement comprising: 8. The improved control rod of claim 7 wherein the elongated member comprises a plurality of adjacent cantilever springs and the interference means comprises a shoulder on each of the cantilever springs.