Abstract: A nuclear reactor includes a vessel incorporating at least one primary power heat exchanger for cooling the primary liquid of the nuclear reactor during the normal operation of the reactor and at least one primary passive safety heat exchanger for cooling the primary liquid of the nuclear reactor in the event of a malfunction in the normal cooling of the primary liquid of the reactor. The vessel includes a compartment arranged in the thickness thereof, wherein the primary passive safety heat exchanger is at least partially contained inside the compartment.

Abstract: Apparatus for salt separation (2) under supercritical water conditions, comprising a heat exchanger (4) and a fluidized bed reactor (6). The fluidized bed reactor comprising a supercritical water pressure containing wall (8) defining therein a fluidized bed chamber (10) connected to an inlet system (16) at one end thereof and an outlet system (18) configured to separate solids from supercritical fluid at another end thereof. The fluidized bed chamber receives a fluidized bed (12) therein and is configured to receive through the inlet system (16) a liquefied aqueous substance (14) for treatment in the fluidized bed chamber. The inlet system (16) comprises an inlet chamber (20) and a fluidization plate (22) positioned between the inlet chamber (20) and the fluidized bed chamber (10).

Abstract: A mobile heat pipe cooled fast nuclear reactor may be configured for transportation to remote locations and may be able to provide 0.5 to 2 megawatts of power. The mobile heat pipe cooled fast reactor may contain a plurality of heat pipes that are proximate to a plurality of fuel pins inside the reactor. The plurality of heat pipes may extend out of the reactor. The reactor may be configured to be placed in a standard shipping container, and may further be configured to be contained within a cask and attached to a skid for easier transportation.

Abstract: A cooling unit cooling a coil assembly that generates electromagnetic force for driving a nuclear reactor control rod, and including a coil surrounding a driving shaft of the nuclear reactor control rod so as to generate the electromagnetic force; a coil housing surrounding the coil so as to enclose the coil; a cooling shroud-shell forming a cooling flow path between the cooling shroud-shell and the coil housing, whereby a cooling fluid for cooling heat that is generated in the coil passes through the cooling flow path; and a plurality of cooling fins disposed on the cooling flow path in a radial direction so as to allow heat to be effectively exchanged between the coil and the cooling fluid that flows through the cooling flow path.

Abstract: A reactor vessel includes a plenum and a reactor core with first and second sets of channels. A blanket salt flows through the first set of channels, and a fuel salt flows through the second set of channels. The plenum receives the blanket salt from the first set of channels. The blanket salt provides a breed-stock for a fission reaction in the fuel salt and transfers heat generated by the fission reaction without mixing with the fuel salt.

Abstract: The present invention related to a novel process for accelerating the breeding and conversion of fissile fuel in various types of nuclear reactors. In said process a movable nuclear fuel ball bed filled with a coolant creeps through the reactor core. The said process could provide higher specific power per unit fuel volume inside the reactor core and proceed on-line refueling, thus requires much less initial fissile fuel inventory per unit power output as compared with the traditional breeding or conversion reactors. The said process has full inherent safety characteristics and could follow the external power demand with the inherent negative temperature coefficient of reactivity. The said process, therefore, is a more efficient and economic approach to meeting the enormous demand of fissile fuel for the forthcoming “second nuclear era”.

Abstract: A method and apparatus for optimizing the production of Pu-238 in a nuclear reactor during normal reactor operation is disclosed wherein the production of Pu-238 is confined to one or more selectively replaced fuel cells with target cells located in the inside of the active volume of the reactor core to maximize the neutron flux for target irradiation. The target cells are modified existing nuclear fuel assembly cells having some fuel rods replaced with target rods of Np-237 forming a cluster array and having rings of water filled rods surrounding the target cluster to produce the desired optimal Pu-238 production.

Abstract: A subcritical reactor-like apparatus for treating nuclear wastes, the apparatus comprising a vessel having a shell and an internal volume, the internal volume housing graphite. The apparatus having means for introducing a fluid medium comprising molten salts and plutonium and minor actinide waste and/or fission products. The apparatus also having means for introducing neutrons into the internal volume wherein absorption of the neutrons after thermalization forms a processed fluid medium through fission chain events averaging approximately 10 fission events to approximately 100 fission events. The apparatus having additional means for removing the processed fluid medium from the internal volume. The processed fluid medium typically has no usefulness for production of nuclear weapons.

Abstract: A reactor core of a fast breeder reactor is supported by a core support within a reactor vessel. The reactor vessel is provided with a first or lower sodium chamber for accommodating low temperature sodium, a second or intermediate sodium chamber for accommodating low temperature sodium and a third or upper sodium chamber for accommodating high temperature sodium heated by passage of the low temperature sodium through the reactor core into the third sodium chamber. Low temperature sodium is introduced into the second sodium chamber arranged between the first and third sodium chamber for cooling the core support.

Abstract: A self-contained modular nuclear reactor which can be prefabricated at a factory location, nuclear-certified at the factory, transported to a field location for final assembly and connection to a large-scale electric-power generating facility. The modular reactor includes a prefabricated nuclear heat supply module and a plurality of shell segments which can be assembled about the heat supply module and which provide a form for the pouring and curing of a cementatious biological shield about the heat supply module. The modular reactor includes passive shutdown heat removal systems sufficient to render the reactor safe in an emergency. A large-scale power plant arrangement is disclosed which incorporates a plurality of the modular reactors.