Method and device for flattening the axial neutron flux of a nuclear reactor.

摘要

980,943. Fuel elements. EUROPEAN ATOMIC ENERGY COMMUNITY (EURATOM). Aug. 20, 1963 [Aug. 31,1962], No. 32969/63. Heading G6C. In a nuclear reactor comprising parallel channels containing fuel elements, the fuel crosssection in some but not all of the channels is varied along the length of the fuel element to obtain a more even lengthwise distribution of neutron flux. In one arrangement, Fig. 1, the fuel element is similar to that used in the Belgian BR2 reactor except that the fuel plates 4 do not extend for the full length of the frame 1; a gap 5 of several centimetres length in the centre of frame 1 is not occupied by fuel plates. In another arrangement, Fig. 2 (not shown), the frame is rectangular with cambered fuel plates extending from one side of the frame to the opposite side; again the centre portion of the length of the frame is not occupied by fuel plates. This construction is similar to that used in the U.S. MTR reactor.