Abstract: A compressed powder composite (CPC) material for absorbing neutrons emitted from spent nuclear fuel thereby preventing the initiation of a chain reaction. The CPC material is typically provided as a substantially insoluble cylindrical pellet that is highly resistant to corrosion and is not subject to the failure modes associated with the alloy materials typically used in neutron absorption materials. The pellet preferably includes a dendritic nickel powder substantially uniformly mixed with a neutron absorber powder material, preferably boron carbide. Tubes filled with CPC materials, such tubes for replacing control roads so that a spent nuclear fuel assembly may be disposed of substantially indefinitely.

Abstract: A passive pulse generator can be connected to a line in order to activate a safety fitting in a nuclear power plant. The line can be closed by a closure element. In the event of a temperature change in the vicinity of the pulse generator, the closure element is actuated solely as a result of a thermal volume change of an actuating element, so that the line is released. The pulse generator therefore activates the fitting passively, without additional control pulses. A method for activating a fitting with a passive pulse generator is also provided.

Abstract: In a nuclear reactor installation with a small high temperature reactor (26) all of the components of the primary loop, together with the control and shutdown installations (82, 92, 114, 116; 194, 198, 200) are located inside a steel pressure vessel (16) and may be installed and dismantled from above. This makes an economical subterranean construction possible.

Abstract: A quenching element of the size and shape of a graphite nuclear fuel ball is introduced to the stacked balls of a stacked ball nuclear reactor core to release a neutron absorbing substance upon being heated to a predetermined temperature, thereby controlling the reactivity of the reactor by causing this substance, which may be a gadolinium compound, to deposit upon the graphite surfaces of the fuel element balls.

Abstract: A method of operating a gas-cooled nuclear reactor having graphite fuel elements in which, to reduce the reactor, a quenching element is introduced which takes a particle of a reaction-reducing substance in a sheath which will melt or release the substance in vapor form so that the substance can penetrate in gaseous form through the surrounding graphite body and deposit upon fuel elements.

Abstract: Device for shutting down a high-temperature nuclear reactor having a reactor core, including a reflector disposed outside the reactor core, channels being disposed in the reflector and having lower ends, storage bins being disposed above the reactor core and being in communication with the channels above the lower ends thereof, a neutron-absorbing material formed of fluidic bodies being storable in the storage bins and feedable into the channels, a plurality of lines connected between the lower ends of the channels and the storage bins, means for selectively establishing an upwardly directed fluid flow of the material in one of the plurality of lines for conveying the neutron-absorbing material at a given adequate speed from one of the channels into one of the storage bins.