Abstract: The mechanical spectral shift reactor comprises a reactive core having fuel assemblies accommodating both water displacer elements and control rods for selectively changing the volume of water-moderator in the core. The fuel assemblies are arranged in alternating fashion so that one drive mechanism may move displacer elements in more than one fuel assembly without interfering with the movement of control rods or the corresponding control rod drive mechanisms.

Abstract: A pressurized water nuclear reactor comprises a normally vertical main vessel externally duplicated by a confinement enclosure. The main vessel contains a simplified primary circuit essentially incorporationg the reactor core and an annular steam generator arranged in such a way that the circulation of water, pressurized once and for all during the sealing of the vessel, takes place by natural convection. All the auxiliary circuits, conventionally ensuring cooling on shut down of such a reactor are eliminated, said cooling being ensured by a special arrangement of the space formed between the vessel and the enclosure and by the fact that the latter is immersed in an external cooling liquid, no matter what the slope of the reactor. The shut down of fission reaction in the core is ensured by systems of absorbing elements and by the automatic displacement of part of the reflector in the case of a slope of the reactor.

Abstract: A thermally activated trigger device 10 comprises a pressurized closed vessel 11 with a piston 12 slideably mounted in it to divide it into two compartments 14 and 16. A fluid such as an inert gas is contained within the compartments at substantially the same pressure. One end of one of the compartments has venting means 24, such as a normally closed pipe which vents the fluid from the compartment once the pipe becomes open by rupture or melting at an elevated temperature. The resulting pressure difference between the compartments on venting of the fluid moves the piston which is connected to an actuator means for performing a desired control or safety shut-down function. The trigger device is useful for performing many control and safety shut-down functions, particularly for rendering a nuclear space reactor subcritical upon reentry to the earth's atmosphere.

Abstract: A method and apparatus is disclosed for reducing the exposure of pressure vessel welds to fast neutron fluxes. Localized peripheral core areas are provided with rod assemblies which may be made up of nuclear absorbing materials, nuclear reflecting materials, or any combination thereof, and of any desired length so as to reduce the exposure of the welds to such fast neutron fluxes. The rod assemblies are precisely tailored consistent with nuclear calculations to provide the desired effect without substantially reducing core ratings or adversely affecting reactor shutdown margins.

Abstract: The mechanical spectral shift reactor provides a method and apparatus for controlling a nuclear reactor comprising inserting a plurality of reactor coolant displacer members into the reactor at the beginning of the core life. The displacer members reduce the volume of reactor coolant-moderator in the core at the start-up. As the reactivity of the core declines with fuel depletion, a selected number of displacer members are withdrawn from the core at selected time intervals. The withdrawal of the displacer member allows reactor coolant water to enter the core which increases core moderation at a time when fuel reactivity is declining. Thus for a given amount of nuclear fuel the life of the core can be extended or for a given life of a core the uranium fuel requirements can be reduced.

Abstract: A method of operating a pressurized water nuclear reactor comprising determining the present core power and reactivity levels and predicting the change in such levels due to displacer rod movements. Groups or single clusters of displacer rods can be inserted or withdrawn based on the predicted core power and reactivity levels to change the core power level and power distribution thereby providing load follow capability, without changing control rod positions or coolant boron concentrations.

Abstract: An improved water displacer rod includes an elongated hollow thin-walled tube with a pair of end plugs attached to opposite ends of the tube to hermetically seal the tube and a plurality of support pellets disposed in a stacked relationship within the tube. The pellets allow the thin-walled tube to be laterally flexible while still able to resist collapse due to high external pressure. Each pellet is preferably formed of a body having a hollow annular cross-sectional shape and a pair of end webs extends across and closing opposite ends of the body. The body defines a central void and the webs seal the void. Thus, when the pellets are stacked within the tube, each void is sealed individually one from the next. A double barrier is provided in the displacer rod by the hermetically sealed tube and the individually sealed pellets.

Abstract: A non-boron moderator filled rod for a nuclear reactor fuel assembly has a tubular body with a pair of end plugs sealing the opposite ends thereof and defining a chamber within the body. A liquid moderator, such as light water, is contained witin the chamber. One of the end plugs acts as a hydride sink and a hydrogen getter sponge material is disposed adjacent the other end plug.

Abstract: A system for controlling the reactivity of a small fission reactor includes an elongated, flexible hollow tube in the general form of a helical coiled spring axially positioned around and outside of the reactor vessel in an annular space between the reactor vessel and a surrounding cylindrical-shaped neutron reflector. A neutron absorbing material is provided within the hollow tube with the rate of the reaction controlled by the extension and compression of the hollow tube, e.g., extension of the tube increases reactivity while its compression reduces reactivity, in varying the amount of neutron absorbing material disposed between the reactor vessel and the neutron reflector. Conventional mechanical displacement means may be employed to control the coil density of the hollow tube as desired.

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.

Abstract: A displacer rod for use in a mechanical spectral shift pressurized water nuclear reactor comprises a sectioned substantially hollow low neutron absorbing metal rod capable of displacing reactor coolant without absorbing a high amount of neutrons. The tubular sections can be made of stainless steel or Zircaloy tubing and may contain pellets for weighting the displacer rod.