A fluidic self-actuating control assembly for use in a reactor wherein no external control inputs are required to actuate (scram) the system. The assembly is constructed to scram upon sensing either a sudden depressurization of reactor inlet flow or a sudden increase in core neutron flux. A fluidic control system senses abnormal flow or neutron flux transients and actuates the system, whereupon assembly coolant flow reverses, forcing absorber balls into the reactor core region.

A fast reactor core in which a coolant flows comprises a plurality of fuel assemblies each loaded with a fissionable material and a plurality of gas sealed assemblies disposed between the fuel assemblies and sealed with a gas, wherein a surface level of the coolant in the gas sealed assembly changes from an axially upper portion including a core top level to an axially lower portion at a time of core power increase or a core coolant flow quantity decrease. Each of the gas sealed assemblies includes an inner cylindrical member for reducing a horizontal cross sectional area of the flow of the coolant at a portion in height corresponding to an axial central portion of the core and the cylindrical member includes a member for generating heat by radiation.

A control rod having a spring device on its lower end for eliminating oscillatory contact of the rod against its adjacent guide tube wall. The base of the device is connected to the lower tip of the rod. A plurality of elongated extensions are cantilevered downward from the base. Each extension has a shoulder for contacting the guide tube, and the plurality of shoulders as a group has a transverse dimension that is preset to be larger than the inner diameter of the guide tube such that an interference fit is obtained when the control rod is inserted in the tube. The elongated extensions form an open-ended, substantially hollow member through which most of the liquid coolant flows, and the spaces between adjacent extensions allow the flow to bypass the shoulders without experiencing a significant pressure drop.

The reactor has a pressure vessel receiving a coolant and a reactor core. The core has vertically movable control rods to which absorber rods are secured. Each tubular control rod extends, with the interposition of an annular gap, around an immobile guide rod which is also tubular and which is longer than the control rod. To move the control rods, coolant is supplied from the pressure vessel under pressure to the interior of the guide rods. The annular chamber communicates by way of communicating bores with the interior of the associated guide rod and, by way of at least two annular restrictions providing different restrictors with the pressure vessel interior. One restrictor is disposed at the top end of the associated control rod and the other restrictor at the bottom end thereof. The control rods move axially upwards in response to an increasing quantity of coolant in the guide rod interiors and downwards in response to a decreasing quantity of coolant in the guide rod interiors.

A control rod suspended to reciprocate in a guide tube of a nuclear fuel assembly has a hydraulic bearing formed at its lower tip. The bearing includes a plurality of discrete pockets on its outer surface into which a flow of liquid is continuously provided. In one embodiment the flow is induced by the pressure head in a downward facing chamber at the end of the bearing. In another embodiment the flow originates outside the guide tube. In both embodiments the flow into the pockets produces pressure differences across the bearing which counteract forces tending to drive the rod against the guide tube wall. Thus contact of the rod against the guide tube is avoided.