Abstract: A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has an improved composite cladding comprised of a moderate purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube. The metal barrier forms a shield between the alloy tube and a core of nuclear fuel material enclosed in the composite cladding. There is a gap between the cladding and the core. The metal barrier forms about 1 to about 30 percent of the thickness of the composite cladding and has low neutron absorption characteristics. The metal barrier serves as a preferential reaction site for gaseous impurities and fission products and protects the alloy tube from contact and reaction with such impurities and fission products. Methods of manufacturing the composite cladding are also disclosed.

Abstract: In order to map the power distribution of a nuclear fuel element, a passive detector is laid along the fuel element in situ to record the residual radiation of the fuel element. The detector spatially records the residual radiation as an image in a radioactive reaction product. In the preferred embodiment, the detector comprises a cylindrical casing or wand enshrouding a material which converts incident gamma radiation having an energy level exceeding a preselected threshold to a correspondingly distributed neutron radiation field. The sheath encases a neutron field-sensitive activant, such as gold in the form of a filament longitudinally disposed in the casing. The image of the low-level radiation field can thereafter be analyzed according to relatively risk-free techniques to map the power distribution of the fuel element.

Abstract: The disclosure relates to energy production by generating an ion stream by laser energy and injecting the ions within a closed loop accelerator. Numerous nodes about the path of the accelerator densify the ions at minimum cross-sections causing substantial kinetic pressure from particles which are accelerated into the nodes together with injected electrons to form a plasma. The accelerator path contains the ions preventing their escape into the atmosphere. The accelerator recycles the ions continuously within the closed loop path for repeated fusion reaction at the nodes.

Abstract: A method and an apparatus for the separation of isotopes from an atomic or molecular paramagnetic or polar beam of isotopic mixtures, by the utilization of the isotopic differences of said atoms as well as molecules, in the Electron Spin Resonance (E.S.R.) spectra and in other magnetic or electric resonances such as in the Nuclear Magnetic Resonance (N.M.R.) or Stark Resonance, is disclosed. The apparatus comprises means for producing a paramagnetic or polar particle beam of an isotopic mixture; means for changing the distribution of the m.sub.j values in said particle beam to at least one beam having a discrete m.sub.j value or values, where m.sub.

Abstract: The reactor core is carried from the base region of the primary vessel by a strongback. An annular foot is attached to the inside surface of the leak jacket leaving a clearance of 6 mm between the foot and the outer surface of the base region of the primary vessel. In the event of deflection of the primary vessel, downward displacement of the core relative to the control rods is limited thereby avoiding serious reactivity instability.

Abstract: A segmented manipulator arm for a nuclear reactor vessel inspection device is disclosed. The several segments of the arm are linked in a manner which permits independent movement of each segment in a different plane of motion. The transducer array which is utilized to conduct the examination of any appropriate point in the reactor vessel is cooperably linked to the final or most forward segment of the manipulator arm.The first segment of the manipulator arm is appropriately coupled to the main column of the inspection device for independent movement in one of three planes relative to the main column. Additional segments are employed and cooperatively linked to the first segment to yield a total of nine planes of movement for one or more of the segments. In addition, brackets are used to constrain segment movement in parallel or predetermined planes as desired.

Abstract: Remotely manipulatable probe and apparatus for positioning a corrosion thickness sensing transducer over selected areas of the internal surface of a tubular radioactive component submerged in a pool of water for radiation shielding.

Abstract: A secure information broadcasting system including a central transmitting station for encoding data in binary form utilizing a keyword and transmitting a FM-SCA signal phase shift modulated by the encoded data. Each of a plurality of portable receiving terminals has an identification number stored therein. When a subscriber desires to display the broadcast information on his terminal, he enters a unique password which is combined with the identification number to generate the keyword. The keyword is utilized to decode the received binary data.

Abstract: The invention is an electronic fuel control system for an internal combustion engine having a first capacitance which is charged to a value indicative of the engine's speed during a first rotational interval of the engine. At the end of the rotational interval the charge on the first capacitance is transferred to a second capacitance which is further charged at a predetermined rate during a second rotational interval. A comparator compares the value of the charge on the second capacitance with a signal indicative of the engine's load. The comparator generates a pulse width signal indicative of the engine's fuel requirements during the interval the charge on the second capacitance is less than the value of the load signal.

Abstract: Defects in the fuel rods of nuclear fuel assemblies are ascertained and located by ultrasonic means. The fuel assemblies are subjected to ultrasonic waves. Differences in fuel rod resonance is indicative of defective rods.

Abstract: This invention consists of a system for generating clean controllable inexpensive electrical power by nuclear fusion (not fission) of light weight atoms and/or isotopes of hydrogen such as deuterium. Fusionable ions are accelerated head-on from many directions through the middle of a reaction chamber. Such ions are produced by especially designed cyclotrons aimed at one another. Since the orbital motion and escape velocity of an ion is controlled by the magnetic field of its originating cyclotron, said ion cannot hit the outer wall of the opposite magnet (which is of equal strength). Hence the system's plasma is operationally contained. The system can produce plasmas of practically any desired average velocity hence temperature; and in densities approaching 10.sup.20's per cc at the center of the reaction chamber. These conditions are abundantly ample for practical production of fusion.

Abstract: In a reactor vessel for pebble beds at high and varying temperatures having a side wall and a base formed of a multiplicity of stacked blocks of heat-resistant material and held together by an outer cylindrical or polygonal ring and supported on a foundation, the base and the side wall, respectively, being formed of a plurality of sectors having substantially vertical, radial parting lines therebetween, the sectors being supported with slight friction on the foundation and being braced against the outer ring, the sectors having boundary surfaces with a pebble bed, support surfaces on the foundation and abutment surfaces against the outer ring, the respective surfaces of the boundary surfaces, the support surfaces and the abutment surfaces having a convex mutual inclination whereby each of the sectors is held together in itself by external forces and is forced by its own weight and the weight of the pebble bed into a definite position.

Abstract: Circuitry is described for use with a fuel mixture control system of an internal combustion engine in which an oxygen sensor is located in the exhaust system and generates a generally bi-valued signal which is compared with a set-point voltage to indicate rich or lean mixtures. In order to permit control loop operation even when the sensor signal changes due to decreasing temperatures, the set point voltage is adjusted to remain between the two values of the sensor signal. This adjustment is effective only when the lower sensor signal exceeds a given limit.

Abstract: A poison bundle release mechanism within a safety assembly of a liquid metal nuclear reactor. A baffle consisting of a plate with recesses in fluid communication with low pressure coolant is formed in the upper portion of the safety assembly. A plug attached to the upper end of the poison bundle fits snugly against the recesses and is held up against the plate by the coolant pressure difference acting on the lower and upper sides of the plug. A conduit and valve arrangement is provided within the plug whereby the actuation of the valve permits high pressure coolant to enter the recessed region, reducing the pressure difference across the plug and producing rapid disengagement thereof from the plate.

Abstract: A neutron flux monitoring system is described for a nuclear reactor which enables the monitoring of very low levels of neutron flux such as may exist during the shutdown condition of the reactor. The pulses produced in the flux detectors distributed around the reactor core and ordinarily used for power range monitoring are conveyed, by isolation means, to summing means which provide a count rate output corresponding to the total number of pulses produced by all of the neutron flux detectors.

Abstract: Disclosed is a nuclear reactor plant, comprising:a prestressed concrete pressure vessel;a high temperature reactor arranged in a central cavity within the vessel;a closed gas cooling circuit including at least one housed gas turbo unit arranged in a turbine duct in the wall of the vessel, said unit including a turbine and a compressor and having detachable bearings; means for exchanging heat and means for transporting gas in the cooling circuit including hot gas from the reactor to the turbine, said heat exchange means and said gas transport means being arranged in recesses in the wall of the vessel;means for forming a detachable plug-in type connection between the hot gas transport means and each turbo unit;means, positioned at the edge of the turbine duct, for connecting all remaining gas transport means to the turbo unit;means, including peripheral sealing members positioned between the inside wall of the turbine duct and the outer housing of the turbo unit, for separating each of the remaining gas transpo

Abstract: A liquid metal cooled fast breeder nuclear reactor has power setback means for use in an emergency. On initiation of a trip-signal a control rod is injected into the core in two stages, firstly, by free fall to effect an immediate power-set back to a safe level and, secondly, by controlled insertion. Total shut-down of the reactor under all emergencies is avoided.

Abstract: Additional air is supplied through an additional air passage having a bypass valve into the main air passage of an internal combustion engine downstream of the throttle valve, and the amount of the additional air is controlled in accordance with the opening of the bypass valve. The direction of rotation of a bypass valve driving pulse motor is controlled in accordance with the output signal of an air-fuel mixture ratio sensor mounted in the exhaust system of the engine. Also the rotational speed of the pulse motor is varied in accordance with the operating conditions of the engine during warm-up operation.

Abstract: Positioning means for locating inspection apparatus used to volumetrically examine a nuclear reactor vessel is disclosed. The positioning means is provided with a support ring having an annular key positioned longitudinally about its periphery. Three support legs are attached to the support ring by brackets adapted to fit the annular key. In addition, the support ring also carries three guide stud bushings which are movably mounted thereon by clamps adapted to engage the support ring key. Prior to lowering the inspection apparatus into the vessel, the guide stud bushings are each moved to a point of alignment with one of three guide studs extending upwardly from the vessel. After alignment has been verified, the guide stud bushings are clamped in position.The inspection apparatus is now lowered towards its fully seated position within the vessel and is coarsely circumferentially positioned with respect thereto by the engagement of the guide studs within the guide stud bushings.

Abstract: An illustrative embodiment of the invention discloses a technique for disassembling a nuclear reactor fuel element without destroying the individual fuel pins and other structural components from which the element is assembled. A traveling bridge and trolley that span a water-filled spent fuel storage pool support a strongback. The strongback is under water and provides a working surface on which the spent fuel element is placed for inspection and for the manipulation that is associated with disassembly and assembly. To remove, in a non-destructive manner, the grids that hold the fuel pins in the proper relative positions within the element, bars are inserted through apertures in the grids with the aid of special tools. These bars are rotated to flex the adjacent grid walls and, in this way relax the physical engagement between protruding portions of the grid walls and the associated fuel pins.