Abstract: A maximal modifiable modular capacitor-generator (CAPGEN) architecture, dielectrics and electrodes may be modified and retain substantially all of the starting activated carbon powder surface area by encapsulating the activated carbon powder in a modifiable gaseous medium and pressure. The capacitor electrical conductivity may be further increased and resistance reduced by electrically reticulating the electrodes and/or modifying the carbon electrode with rarefied or pressurized gases, conventional electrolytes, radioisotopes, stratified radiation emitting materials such as gases, liquids, solids, or modified photovoltaic carbon powder, thereby the capacitor becomes self charging and the surface area, mass, voltage, capacitance, energy density, power density and working temperature are maximized so that the same capacitor base architecture may be maximally modified from a capacitor to a CAPGEN, to a photovoltaic-thermionic CAPGEN and helium generator.

Abstract: The invention provides for a method for producing isotopes using a beam of particles from an accelerator, whereby the beam is maintained at between about 70 to 2000 MeV; and contacting a thorium-containing target with the particles. The medically important isotope 225Ac is produced via the nuclear reaction (p,2p6n), whereby an energetic proton causes the ejection of 2 protons and 6 neutrons from a 232Th target nucleus. Another medically important isotope 213Bi is then available as a decay product. The production of highly purified 211At is also provided.

Abstract: A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.

Abstract: An apparatus and method for the production of radioisotopes utilizing an energy recovery linac. The ERL system is composed of an electron beam source, multiple superconducting radio frequency cavities operating at 4.5 K, a thin radiator, a target material, and a beam dump. The accompanying method discloses the use of the ERL system to generate desired radioisotopes via target interaction with bremsstrahlung photons while allowing recovery of a substantial portion of the electron beam energy before the beam is extracted to the beam dump.

Abstract: The present invention relates to passive cooling systems and methods for cooling a spent fuel pool in a nuclear power plant in the absence of onsite and offsite power, e.g., in a station blackout event. The systems include a gap formed along the periphery of the spent fuel pool, a heat sink, one or more thermal conductive members, a water supply system for delivering water to at least partially fill the gap and conduct heat generated from the spent fuel pool through the gap to at least one thermal conductive member for transporting heat to the heat sink, and a thermal switch mechanism for activating and deactivating the water supply system. In particular, the passive spent fuel pool cooling systems and methods of the invention are useful when the active spent fuel pool cooling system is unavailable or inoperable.

Abstract: In general, the present invention is directed to novel nuclear fuel rod claddings that have better performance characteristics compared to current claddings, particularly during a severe accident, such as a loss of coolant accident. The present invention provides a duplex cladding having two layers, an inner Mo or Mo-alloy layer and a protective layer disposed on the outside of the Mo or Mo-alloy layer. Optionally, the Mo or Mo-alloy layer may have a coating disposed on its inner surface to provide additional capability with the fuel pellets, thereby creating a triplex cladding.

Abstract: A method for creating isotopes using laser beams, including the steps: 1) placing a target under plasma conditions, 2) bombarding the target under plasma conditions with particles generated using a bundle of laser beams, the bundle of laser beams being synchronized with the development of the plasma conditions, the fuel and the particles being selected in such a way that the interaction between the target under plasma conditions and the particles generates nuclear reactions, and 3) recovering the isotopes generated by the nuclear reactions.

Abstract: A system and a method for a commercial nuclear repository that turns heat and gamma radiation from spent nuclear fuel into a valuable revenue stream. Gamma radiation from the spent nuclear fuel of the repository may be used to irradiate and sterilize food and other substances. Gamma radiation may also be used to improve the properties of target substances. Additionally, heat decay from the spent nuclear fuel of the repository may be harnessed to heat materials or fluids. The heated fluids may be used, for instance, to produce steam that may make electricity. The heating of working fluids for use in processes, such as heated fluid streams for fermentation or industrial heating, may be transported out of the repository and co-mingled with other heat input, or other fluids.

Abstract: Fuel pellets for use as targets in thermonuclear fusion by inertial confinement are manufactured from a solid palladium core that contains deuterium tritium gases. The palladium core is covered with a tamper-ablator shell of heavy metal selected from the group including gold, platinum, and tungsten.

Abstract: An improved tool for delivery of a testing element to a limited access location within a nuclear containment includes a rotation apparatus having a connection element that is configured to have an aperture that is formed generally centrally therein. The aperture is structured to receive therein a cable that extends from a testing element, which that avoids the need to use slip rings or similar devices to permit the testing element to carried on a pivotable and rotatable structure. Moreover, an improved submersible machine is structured to carry the tool to a limited access location within a nuclear containment.

Abstract: Various embodiments include apparatus and methods of using the apparatus having a neutron generator. The neutron generator can include a neutron generator tube having a cylindrical inner surface that bounds a cylindrical cavity, a field ionization array cylindrically distributed on the cylindrical inner surface, and a target rod positioned in the cylindrical cavity. Additional apparatus, systems, and methods are disclosed.

Abstract: A system configured to passively filter radioactive materials from a flow may include one or more particulate removal devices; one or more water removal devices; and/or one or more radionuclide removal devices. At least one of the one or more particulate removal devices may mechanically remove particulates of the radioactive materials from the flow. At least one of the one or more water removal devices mechanically may remove water from the flow. At least one of the one or more radionuclide removal devices may remove radioactive aerosols, reactive radioactive gases, or radioactive aerosols and reactive radioactive gases from the flow using engineered filter media. A filter may include a body, including an inlet and an outlet. The body may be configured to store filter media, to contain pressure from gas explosions, and/or to allow the stored filter media to move toward the outlet when pressure at the inlet increases.

Abstract: A system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) may include a heating subsystem for heating feedwater flowing into an annulus of the NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system may include a temperature sensor operable to sense the temperature of the feedwater flowing into the annulus. The temperature sensor is communicatively connected to a temperature controller operable to command the heating subsystem to increase the temperature of the feedwater flowing into the annulus to a requested temperature above a predetermined operating temperature of the feedwater flowing into the annulus.

Abstract: A nuclear reactor includes a pressure vessel and a nuclear reactor core comprising fissile material disposed inside the pressure vessel at the bottom of the pressure vessel. A secondary core containment structure includes a containment basket comprising insulation with a maximum stable temperature of at least 2200K cladded by steel. The bottom of the pressure vessel and the nuclear reactor core are disposed inside the containment basket with the containment basket spaced apart from the bottom of the pressure vessel by a clearance gap. The containment basket may comprise zirconia insulation cladded by steel. In some embodiments the clearance gap between the containment basket and the bottom of the pressure vessel is no larger than one meter. The secondary core containment structure may further comprise conduits arranged to inject water into the clearance gap between the containment basket and the bottom of the pressure vessel.

Abstract: A reactor pressure vessel assembly may include a housing surrounding a reactor core, steam separators, and a chimney. Inner surfaces of the chimney and reactor core define a conduit for transporting a two phase flow stream from the reactor core through the chimney to the steam separators. The housing defines an opening. An inner surface of the housing and outer surfaces of the chimney and reactor core define an annulus in fluid communication with the opening and conduit. A feedwater sparger in the housing is connected to the at least one opening and configured to deliver a sub-cooled feedwater into the annulus. A flow barrier structure between the chimney and the steam separators may force mixing between the sub-cooled feedwater and a downcomer fluid from the steam separators. An outer steam separator may be vertically over a portion of the flow barrier structure in a plan view.

Abstract: Disclosed embodiments include nuclear fission reactors, nuclear fission fuel pins, methods of operating a nuclear fission reactor, methods of fueling a nuclear fission reactor, and methods of fabricating a nuclear fission fuel pin.

Abstract: The present invention provides a method for producing Cu67 radioisotope suitable for use in medical applications. The method comprises irradiating a metallic zinc-68 (Zn68) target within a sealed ceramic capsule with a high energy gamma ray beam. After irradiation, the Cu67 is isolated from the Zn68 by any suitable method (e.g. chemical and or physical separation). In a preferred embodiment, the Cu67 is isolated by sublimation of the zinc in a ceramic sublimation tube to afford a copper residue containing Cu67. The Cu67 can be further purified by chemical means.

Abstract: The invention relates to an apparatus and methods for operation in relatively high radiation fields to remotely switch signal devices through a shared single main umbilical signal cable. The invention is particularly suitable for use in a nuclear reactor, such as a boiling water reactor, and in difficult to access areas in the reactor pressure vessel. One or more main umbilical cables connect a control station to an enclosure housing a signal switching device. The signal switching device allows several signal generating/receiving devices, such as cameras and ultrasonic probes, to be controlled by the one or more main umbilical cables.

Abstract: A first system for producing a high flux of neutrons for non-destructive testing includes a dense plasma focus device neutronically coupled to a subcritical or sub-prompt critical fission assembly. The dense plasma focus device is a source of initiating neutrons for the fission assembly, and the fission assembly is configured to multiply a number of the initiating neutrons via inducing fission. A second system for producing a high flux of neutrons includes a gas-target neutron generator neutronically coupled to a subcritical or sub-prompt critical fission assembly. The gas-target neutron generator is a source of initiating neutrons for the fission assembly, and the fission assembly is configured to multiply a number of the initiating neutrons via inducing fission.

Abstract: A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulic-ally interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in tun extracts heat from and cools the primary coolant.