Abstract: An aneutronic magnetron energy generator that generates microwave energy from a fusion-fission reaction that produces alpha particles in response to a proton colliding with an 11B nucleus. The magnetron energy generator includes a magnetron having an anode resonator including a central chamber and a plurality of radially disposed cavities. A cathode assembly is provided at the center of the chamber and includes a cathode electrode that generates a proton plasma. A series of electrically isolated acceleration rings extend from the cathode electrode and operate to accelerate protons from the proton plasma towards an outer target ring composed of boron eleven (11B). The accelerated protons fuse with the 11B nuclei to generate the alpha particles that then interact with crossed electric and magnetic fields between the target ring and the cavities. The alpha particles resonate with the cavities and generate a current within the resonator that is collected.

Abstract: Systems and methods for operating an accelerator driven sub-critical core. In one embodiment, a fission power generator includes a sub-critical core and a plurality of proton beam generators. Each of the proton beam generators is configured to concurrently provide a proton beam into a different area of the sub-critical core. Each proton beam scatters neutrons within the sub-critical core. The plurality of proton beam generators provides aggregate power to the sub-critical core, via the proton beams, to scatter neutrons sufficient to initiate fission in the sub-critical core.

Abstract: An apparatus for the generation of neutron/gamma rays is described including a chamber which defines an ion source, said apparatus including an RF antenna positioned outside of or within the chamber. Positioned within the chamber is a target material. One or more sets of confining magnets are also provided to create a cross B magnetic field directly above the target. To generate neutrons/gamma rays, the appropriate source gas is first introduced into the chamber, the RF antenna energized and a plasma formed. A series of high voltage pulses are then applied to the target. A plasma sheath, which serves as an accelerating gap, is formed upon application of the high voltage pulse to the target. Depending upon the selected combination of source gas and target material, either neutrons or gamma rays are generated, which may be used for cargo inspection, and the like.

Abstract: An integral pressurized water nuclear reactor for the production of steam utilizing a helical coil steam generator, a plurality of internal circulation pumps, and an internal control rod drive mechanism structure.

Abstract: A top nozzle is provided. The top nozzle can include a coupling plate, a perimeter wall and a hold-down spring unit. The coupling plate can be coupled to a guide thimble of the nuclear fuel assembly. The perimeter wall can protrude upwards from the perimeter of the coupling plate. A spring clamp can be provided on the upper surface of the perimeter wall. The hold-down spring unit can be mounted to the upper surface of the perimeter wall in such a way to couple a corresponding end of the hold-down spring unit to the spring clamp. A fastening pin hole can be vertically formed through an upper surface of the spring clamp. A spring insert hole into which the hold-down spring unit can be inserted and formed by electro-discharge machining in an insert direction of the hold-down spring.

Abstract: A U-tube steam generator having a dual system for collecting loose parts and sludge. A loose parts collector having a water overflow edge is disposed between a feedwater inlet and a tube bundle of the steam generator. A sludge collector having a water outlet that is disposed downstream of the overflow edge of the loose parts collector and maintains a pressure differential between a water inlet of the sludge collector and the water outlet.

Abstract: A system and method for predicting acoustic loads expected on a boiling water reactor (BWR) may include a BWR scale model, a test fixture for generating air flow in the scale model, and one or measurement devices for monitoring system behavior to predict how acoustic loads may affect plant operation for the BWR being evaluated.

Abstract: The invention relates to the production of radiostrontium. The problem to be solved by the invention is the extraction of radiostrontium from a large pool of liquid metallic rubidium to improve the efficiency of radiostrontium production and simplify the technology. Sorption is carried out directly on the inner surface of the target shell at a temperature of 275 to 350° C., or by means of extraction of radiostrontium from circulating rubidium via sorption on the heated surface of a trap at a temperature of 220 to 350° C., or by means of filtering liquid rubidium through a filtering unit made of a porous material resistant to liquid rubidium metal.

Abstract: Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein.

Abstract: A Stirling radioisotope generator is provided. The generator includes a first and second heat source assembly, each heat source assembly comprising two General Purpose Heat Source modules, each General Purpose Heat Source module configured to generate thermal energy. The generator also includes a first and second Stirling convertor in thermal communication with the first and second heat source assembly, respectively, each Stirling convertor configured to convert the thermal energy into electrical power. The generator has a housing enclosing the first and second heat source assembly and the first and second Stirling convertor, the housing configured to dissipate excess thermal energy.

Abstract: In a nuclear reactor, a core barrel (46) is disposed in a reactor vessel (41) having an inlet nozzle (44) and an outlet nozzle (45), a core (53) is disposed in the core barrel (46), a lower plenum (58) is partitioned by the reactor vessel (41) and a bottom portion of the core barrel (46), and a downcomer portion (59) is partitioned by the reactor vessel (41) and a side wall of the core barrel (46). The lower plenum (58) includes a straightening member (61) formed of an upper ring (65) and a lower ring (69) in a ring shape, and a plurality of spokes (64 and 68) radially arranged inside the rings (65 and 69), respectively. Heat exchange efficiency is enhanced by uniformly supplying coolant introduced into a pressure vessel to the core from the lower plenum in a radial direction and a circumferential direction.

Abstract: Embodiments of systems and methods for compressing plasma are disclosed in which plasma can be compressed by impact of a projectile on a magnetized plasma in a liquid metal cavity. The projectile can melt in the liquid metal cavity, and liquid metal may be recycled to form new projectiles.

Abstract: A truss-reinforced spacer grid and a method of manufacturing the same are provided, in which truss members having a small diameter are woven to form a truss structure surrounded by an external plate, and the truss structure is joined to the external plate to thereby improve the strength of the mechanical structure. The truss-reinforced spacer grid includes a truss structure in which horizontal trusses formed by horizontally weaving a plurality of truss members are vertically disposed at regular intervals, and an external plate is joined with ends of the horizontal trusses and surrounds the truss structure.

Abstract: Methods and systems for non-intrusively detecting the existence of fissile materials in a container via the measurement of energetic prompt neutrons are disclosed. The methods and systems use the unique nature of the prompt neutron energy spectrum from neutron-induced fission arising from the emission of neutrons from almost fully accelerated fragments to unambiguously identify fissile material. These signals from neutron-induced fission are unique and allow the detection of any material in the actinide region of the nuclear periodic table.

Abstract: Disclosed herein is a high current solid target for radioisotope production at a cyclotron using a metal foam, and more specifically, a high current solid target for isotope production, which attaches a metal foam to the rear surface of the solid target plate. A high current solid target for isotope production including a metal foam according to the present invention may exhibit excellent cooling performances to increase the amount of proton beam current irradiated on the solid target compared to conventional planar-type solid targets. Because the irradiation of the increased proton beam current may increase the amount of an isotope produced per unit time and even an irradiation of proton beam in a short time may allow for production of a desired amount of an isotope, the solid target may be usefully used for production of medical cyclotron nuclides.

Abstract: A power module includes a containment vessel completely submerged in a pool of liquid, and a support structure located at or above an approximate midpoint of the containment vessel, or center of gravity of the power module. The power module is supported by the support structure in combination with a buoyancy force of the pool of liquid acting on the containment vessel.

Abstract: Radionuclides are produced with a pulsed neutron flux from a multiple repetition rate staged Z-pinch machine, the pulsed neutron flux is moderated, an activatable radionuclide precursor is exposed to the moderated pulsed neutron flux, and a corresponding radionuclide from the activatable radionuclide precursor is produced. High current pulses are passed through a target plasma of fusible material enclosed in a cylindrical liner plasma composed of a high-Z plasma to generate a magnetic field that compresses the liner plasma, and generates shock waves. The shock implodes the target plasma. The shock front propagates between an outer shock front and an axis of the target plasma so it is heated through shock dissipation and by adiabatic compression due to an imploding shock front produced in the outer liner plasma to fuse light nuclei and generate alpha particles and neutrons. Alpha particles trapped within the magnetic field further heat the target plasma.

Abstract: The invention provides a compact high energy proton source useful for medical isotope production and for other applications including transmutation of nuclear waste. The invention further provides a device that can be used to generate high fluxes of isotropic neutrons by changing fuel types. The invention further provides an apparatus for the generation of isotopes including but not limited to 18F, 11C, 15O, 63Zn, 124I, 133Xe, 111In, 125I, 131I, 99Mo, and 13N.

Abstract: This invention relates to a nuclear plant including a main power system and a fuel handling and storage system. The system is connected to a sphere inlet and a sphere outlet of a multi-pass high temperature gas cooled pebble bed reactor. The system is configured such that gas flows from the system into the reactor through both the sphere inlet and the sphere outlet thereby inhibiting the ingress of high temperature gas from the reactor into the system. Restricting indexers permit the movement of spheres between the reactor and the system and dampen out the transmission of pressure fluctuations from the power system to the system.

Abstract: A guide thimble plug for a nuclear fuel assembly is provided, in which an internal threaded hole is formed through a main body so that the main body is coupled to a bottom nozzle by a screw coupling. An upper insert part is formed in the upper end of the main body. The upper insert part is inserted into a shock absorption tube. A thermal deformation prevention part is formed on the main body below the upper insert part and is recessed inward from the outer surface of the main body such that, when the main body is coupled to the guide thimble, a gap is defined between the thermal deformation prevention part and the guide thimble. The guide thimble and the shock absorption tube can be reliably fastened to the bottom nozzle, and thermal deformation of the guide thimble can be minimized.