Abstract: A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

Abstract: A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.

Abstract: An igniter apparatus which generates a high speed buoyancy induced vortex to funnel hydrogen and air from the surrounding onto the “igniter core” where an “igniter core” heats up to the auto ignition temperature by the exothermic catalytic oxidation of hydrogen on its surface. Water (vapor) is formed as the product, which inhibits the oxidation reaction, if not stripped away from the catalyst surface. The high velocity of the vortex ensures the stripping of the boundary layer of steam that is formed by the reaction, thus ensuring more active sites are available for hydrogen oxidation. The vortex is formed by channeling an upward draft into a vortex by guided fins. The upward draft is formed by a plate, which is also coated with a hydrogen recombination catalyst. The plate becomes hot by the same catalytic oxidation reaction in the presence of air containing hydrogen.

Abstract: A spring apparatus in accordance with the disclosed and claimed concept is usable in a nuclear installation. In one embodiment, the spring apparatus includes a plurality of springs that are in a compressed state and that are compressively engaged with an upper core plate of a nuclear reactor when the reactor is in a cold condition. However, when the reactor is in a hot condition, a spring of the plurality of springs is in a free state wherein a free end of the spring is in an uncompressed state and is disengaged from the upper core plate. In another embodiment, the spring apparatus employs a support apparatus that is also in accordance with the disclosed and claimed concept and that includes one or more bumpers that engage the springs of a spring pack from the underside.

Abstract: A system and method for fueling a fusion reactor. The system includes a reactor chamber containing a stable plasma including a fusion fuel; a heating system configured to heat the plasma and increase an ion energy of the plasma to a level sufficient for producing net power from fusion reactions in the stable plasma; a plurality of magnets coaxial to the reactor chamber, the plurality of magnets producing a magnetic field sufficient to confine the stable plasma and promote rapid loss of fusion products into a scrape off layer; and a neutral beam injection system configured to inject additional quantities of the fusion fuel to sustain the power output of the fusion reaction.

Abstract: A passive natural circulation cooling system according to the present invention can comprise: a passive condensation tank formed to accommodate cooling water; and a condensate water recirculation device provided at the inner part or upper part of the passive condensation tank, and condensing the cooling water such that the cooling water circulates inside the passive condensation tank. The condense water recirculation device can include: a duct extending upwards from the upper part of the passive condensation tank; and a plurality of partition plates provided inside the passive condensation tank or the duct.

Abstract: The present invention provides a passive residual heat removal system and an atomic power plant comprising the same, the passive heat removal system comprising: a plate-type heat exchanger for causing heat exchange between a primary system fluid or a secondary system fluid which, in order to remove sensible heat from an atomic reactor cooling material system and residual heat from a reactor core, has received the sensible heat and the residual heat, and a cooling fluid which has been introduced from outside of a containment unit; and circulation piping for connecting the atomic reactor cooling material system to the plate-type heat exchanger, thereby forming a circulation channel of the primary system fluid, or connecting a steam generator, which is arranged at the boundary between the primary and secondary systems, to the plate-type heat exchanger, thereby forming a circulation channel of the secondary system fluid.

Abstract: The application provides a self-diagnosis and accident-handling unmanned nuclear reactor, which: can passively cool down excessively generated heat without an operation of an operator when a malfunction of the nuclear reactor has occurred, wherein a cooling operation for safety measures can be carried out in a completely passive manner without a separate control command by a change in environmental conditions such as the structure and pressure of the nuclear reactor; and has a simpler structure compared to that of a conventional nuclear reactor safety system. It also provides a self-diagnosis and accident-handling unmanned nuclear reactor, which performs heat exchange by using a two-phase heat transfer mechanism, wherein heat exchange performance is maximized by introducing a spray-type heat exchanger having an optimized structure in which channels are three-dimensionally arranged, and can also easily and passively control heat exchange without a separate control means by using saturated steam pressure.

Abstract: The invention is for a startup system for nuclear fusion engines in space. The combustion of hydrogen and oxygen produces heat that is used by a heat engine to produce electricity. This can be supplemented by electricity from other operating engines. The exhaust from the combustion is condensed and electrolyzed to produce hydrogen and oxygen once the engine is in operation. This provides a constant source of energy for future startups. The engine is started up at partial power in electricity generation mode and this power replaces the power from the combustion as it grows. The combustor uses the same heat engine as the nuclear engine uses for power generation.

Abstract: A remotely operated vehicle (ROV) for inspecting a core shroud having an outer surface may include: a body configured to be operatively connected to a tether; and/or a sensor, configured to be operatively connected to the body, and configured to provide inspection information of the shroud. The tether may be configured to provide vertical position information for the ROV relative to the outer surface. A system for inspecting a core shroud may include: a trolley; an arm; the tether; and/or the ROV. The arm may be configured to be operatively connected to the trolley. The ROV may be configured to be operatively connected to the arm via the tether. A method for inspecting a core shroud may include: installing a system for inspecting the shroud on the shroud; driving the system horizontally around the shroud; and/or using a sensor of the system to inspect the shroud.

Abstract: Examples of a system for generating and compressing magnetized plasma are disclosed. The system comprises a plasma generator with a first closed end and an outlet, and a flux conserving chamber that is in tight fluid communication with the outlet of the plasma generator such that the generated plasma is injected into an inner cavity of the flux conserving chamber. An elongated central axial shaft is also provided such that the central shaft extends through the outlet of the plasma generator into the flux conserver. The end of the central shaft in connected to the flux conserver. A power source that comprises a formation power circuit and a shaft power circuit is provided to provide a formation power pulse to the plasma generator to generate magnetized plasma, and a shaft power pulse to the central axial shaft to generate a toroidal magnetic field into the plasma generator and the flux conserving chamber.

Abstract: A containment seal seals a cable or tube to an opening accessing a containment vessel. The containment seal includes a lower body that attaches over the opening into the containment vessel. The cable or tube is inserted through a hole that extends axially through an upper body of the containment seal. Compression fittings are attached to the top and bottom ends of the upper body sealing the cable inside of the upper body. The cable sealed inside of the upper body in inserted through the lower body and into the opening accessing the containment vessel and a lower portion of the upper body is seated into the opening formed in the lower body. A retaining device compresses the upper body down against the lower body forming a seal between the upper body and lower body.

Abstract: The present disclosure generally relates to a new process for generating germanium-68 from an irradiated target body. The process includes irradiation of the target body followed by various extraction techniques to generate the germanium-68.

Abstract: A rotation apparatus is usable with a control drum in a nuclear environment. The control drum is situated on a shaft that is rotatable about a horizontal axis of rotation, and the control drum includes an absorber portion and a reflector portion. The rotation apparatus includes a rotation mechanism that is structured to apply to the shaft in an operational position a force that biases the shaft to rotate toward a shutdown position, with the force being resisted by a motor to retain the shaft in the operational position when the motor is powered. The force is not resisted when the motor is unpowered. The rotation apparatus further includes a rotation management system that controls the rotation of the shaft.

Abstract: Processes for producing germanium-68 from a gallium target body are disclosed. In some embodiments, germanium-68 and gallium are precipitated to remove metal impurities. Germanium-68 and gallium are re-dissolved and loaded onto an ion exchange column to separate germanium-68 from gallium.

Abstract: An electromagnet comprises a plurality of nested freestanding electrically insulating former layers, and electrically conductive wire wrapped around the outsides of the freestanding electrically insulating former layers to define a multilayer electrical coil in which adjacent layers of the multilayer electrical coil are spaced apart by intervening freestanding electrically insulating former layers. Electrically energizing the multilayer electrical coil generates a magnetic field inside the multilayer electrical coil. In some embodiments the electrically conductive wire is bare wire not having electrical insulation. In some embodiments the former layers comprise a ceramic material. In some such embodiments the electromagnet further comprises a ferromagnetic core disposed inside the multilayer electrical coil. An electric motor employing such an electromagnet as a stator pole is also disclosed.

Abstract: The present disclosure provides a stopped cooling system including: a steam line connecting portion connected to a steam line so as to receive cooling water through the steam line connected to an outlet of a steam generator; a stopped cooling heat exchanger for receiving cooling water that enters the stopped cooling system through the steam line connecting portion, and discharging same through a passage of the heat exchanger; a stopped cooling pump activated to perform stopped cooling of the nuclear reactor upon normal stoppage of the nuclear reactor after primary cooling of the nuclear reactor cooling system or when an accident occurs, and for forming a circulating flow of cooling water that circulates between the steam generator and the stopped cooling heat exchanger; and a water supplying pipe connecting portion connected to the heat exchanger passage and a water supplying pipe, which is connected to the inlet of the steam generator, so as to supply the cooling water cooled in the stopped cooling heat exch

Abstract: Controlled-debris elements inhibit the formation of a fibrous/particulate debris bed that unduly increases the pressure head loss through the perforated plates of strainers in a nuclear power plant emergency core cooling system. In a loss of cooling accident, pumps draw cooling water through the plates, which retain on their surfaces fibrous material in the circulating water to prevent it from reaching the pumps while permitting entrained particulate matter to pass through the perforations. The controlled-debris elements have a specific gravity substantially the same as the circulating water so they are entrained in the cooling water that is drawn toward the strainers and intimately intermix with the fibrous and particulate matter in the cooling water. The elements are configured to provide open structures in the bed formed on the plate surfaces to distribute fibers in the flow away from the surface and maintain cavities between the elements for the particulates.

Abstract: Systems and methods determine locations of moving equipment in an area holding components to be moved. Moving equipment can relocate relative to the holding area to pick up components in the holding area from an origin and deliver them to a desired location or orientation. The moving equipment includes a device emitting a signal that is detectable where it hits components or other structures in a straight line or known path from the moving equipment. A human or computer can determine a position the moving equipment in the holding area from such signals. Devices can operate with visible light generators including LEDs, incandescent or fluorescent bulbs, and lasers and including lenses or reflectors to shape the light into detectable and high fidelity configurations. Automation components including a hardware processor, controller, and detector can operate moving equipment based on detected light, without human interaction or as a verification in human operations.

Abstract: The present invention provides a porous cooling block for cooling corium, comprising: a base part that includes a plurality of pores; a plurality of porous cooling blocks that include a channel part that communicates with some of the plurality of pores of the base part; a sacrificial part that covers the exposed upper surfaces of the porous cooling blocks; and a cooling-water supply unit that supplies cooling water to the porous cooling blocks. Corium is cooled by using steam or cooling water discharged from the porous cooling blocks. Therefore, the corium can be cooled and solidified in the shape of a porous form. Further, the cooling water is uniformly supplied to one surface formed by the cooling block on the whole, thereby easily cooling the corium.