Abstract: This invention provides a method of operating a nuclear reactor having a negative reactivity moderator temperature coefficient with the object of maintaining a uniform and symmetric Xenon distribution above and below substantially the center of the core over a substantial axial length of the core during normal reactor operation including load follow. In one embodiment variations in the Xenon distribution are controlled by maintaining a substantially symmetric axial power distribution. The axial offset, which is employed as an indication of the axial power distribution, is maintained substantially equal to a target value, which is modified periodically to account for core burnup.

Abstract: A fuel injection control circuit includes a monostable multivibrator for generating injection valve control pulses. The circuit includes a trigger sub-circuit which controls the switching characteristics of the monostable multivibrator in a well-defined manner which is immune to electrical noise and to voltage fluctuation in the supply lines of the vehicle.

Abstract: A driving apparatus for raising and lowering an absorber rod within a nuclear reactor pressure vessel. The apparatus comprises a driving system which includes a motor-driven flexible support member that is connected to the absorber rod through both a coupling element and a connecting element, and a storage means for storing any excess length of flexible support member. Both the driving system and the storage means are detachably enclosed within a desired gaseous environment that is isolated from the interior of the pressure vessel by a screening plug having a passageway therein through which the connecting element is disposed for movement between an upper end position and a lower end position.

Abstract: A frequency generator is enabled when an ignition event is to occur, to provide a sequence of current pulses to an ignition coil, so that multiple sparks will be commanded for any one single ignition event. To compensate for changes in operating parameters, particularly low-voltage condition of supply current, the frequency generator is controllable to change the pulse width, or the frequency thereof. To simply compensate for voltage variations, the frequency generator is a voltage controlled oscillator (VCO), controlled by the electrical supply network, typically the battery of a vehicle.

Abstract: A typical embodiment of the invention combines a novel cellular end fitting for a nuclear reactor fuel assembly with a new design for a fuel rod end cap and a radiation sensing device probe to provide a means for swiftly and accurately distinguishing sound fuel rods from those rods that have developed leaks. For example, a somewhat thinner than usual fuel rod end cap is accessible through the open cellular structure of the end fitting to permit a hollow metal probe to contact the fuel rod end cap. This direct contact excludes most of the water, metal and other shielding materials from the volume between the interior of the fuel rod and the radiation detector, thereby improving the quality of the fuel rod examination. A bridge and trolley structure for accurately positioning the probe also is described.

Abstract: Nuclear fuel rods are manufactured utilizing a graphite flour-pitch matrix formulation containing an additive. The matrix formulation has a decreased viscosity at fabrication temperatures which permits manufacture of the fuel rods with lower fabrication pressures. Also, the matrix formulation does not cause the fuel rod to adhere or bond to the fuel element during heat treatment of the fuel rod in the fuel element. The nuclear fuel rods are suitable for use in high temperature gas cooled nuclear reactors.

Abstract: A circuit is provided in an electronic closed loop air-fuel ratio control system for starting and terminating the operation of the system at different voltages from an exhaust gas sensor.

Abstract: A large inertial confinement breeder reactor wherein neutron bursts produced by fusion, fission or combined fission and fusion are contained seriatim in a large chamber. Each burst results from interception of a large, sub-critical free-falling mass by a smaller upward accelerated slug such that the combined assembly is more than prompt-critical. The resulting thermal energy is absorbed by a spray which generally fills the chamber. The innermost portion of the spray comprises a dense slurry of actinides in molten sodium while the outer portions of spray comprise a very dilute slurry of actinides in molten sodium. The collected heated spray also contains the debris of the explosion and travels through a heat exchanger-precipitator means wherefrom dense slurry, lean slurry, precipitate, and thermal energy may be extracted.

Abstract: An improved containment for radiation shielding and pressure suppression is presented. The arrangement, which is particularly suited for marine propulsion application, includes, in a preferred embodiment, a double wall containment shell including water as a biological shield, a divided wet well arrangement and means for precluding discontinuity of the radiation shielding effect due to shifting of the liquid in the wet well at various ship attitudes.

Abstract: The operation of an electronic closed loop air-fuel ratio control system is inhibited while exhaust gas temperature is low, and a rich air-fuel mixture is intermittently fed to an internal combustion engine in order to properly initiate the operation of the system.

Abstract: An improved neutron monitoring and startup source for a thermal nuclear reactor including a fast neutron emitting material encapsulated within a cladding substantially black to thermal neutrons. In another embodiment the inventive source, or any source, is advantageously affixed to movable control elements so as to reside out of the reactor core for periods of high neutron flux.

Abstract: A fuel mixture control apparatus for an electronic fuel injection system for internal combustion engines. In a warm-up controller, the fuel injection control pulses are lengthened for enrichment of the fuel-air mixture during engine warm-up on the basis of signals supplied by a temperature transducer. In order to make the warm-up enrichment dependent on prevailing engine states, for example on the conditions of idling and partial or full load, circuitry is provided to sense these conditions and to suitably alter the enrichment factor. A further circuit suppresses the dependence or enrichment on engine status during engine starting. Various embodiments are presented.

Abstract: A single point fuel injection system for an internal combustion engine including a throttle body having first and second air intake throats corresponding to first and second intake manifold planes of the engine, the air flow through each throat being controlled by throttle plates positioned within each throat. The throttle body further includes a fuel accumulating bowl which is integrally formed with the throttle body, the bowl being enclosed by a diaphragm and cover member. Within the enclosure of the fuel bowl are positioned a pair of injectors which are adapted to inject pulsed portions of fuel through a sonic nozzle and into the air intake throat of the throttle body. The injection of pulses of fuel into the throat is timed in accordance with the sensing of the crankshaft reaching a position of 15.degree. before top dead center to enhance the distribution of fuel charge from cylinder to cylinder.

Abstract: A method of identifying leaky components of a multi-component system in wh the individual components contain a charge. Additional substances having different element or isotope compositions are added to these charges to code them. If leaks occur, element or isotope analysis of the escaping charges then allows identification of the leaky component. If the multi-component system includes a nuclear reactor, different element or isotope combinations of krypton and xenon may be added to the individual fuel rods during production, and optical saturation spectroscopy may be used to analyze the leaking gases.

Abstract: This invention consists of a system which generates clean inexpensive electrical power by fusing isotopes of hydrogen or other lightweight material. Not unlike a cyclotron "turned wrong-side out" ions are accelerated each time they cross a gap between two perforated "bowls" across which is placed high frequency-high voltage. Accelerated ions leave the bowls and go into magnetic gaps or mirror-tubes arranged radially thereon and are generally reflected back through the center of the system between the bowls. By controlled leakage highly energetic ions go out the ends of the mirror tubes and into Return Tubes surrounded by sector or other magnets. Ions are recirculated rapidly and repeatedly through the center of the system. Densities are anticipated to be at least 10.sup.15 and perhaps 10.sup.20's ions per cc. Probabilities of head-on collision are greatly enhanced by converging the beams of ions or jets of plasma head-on.

Abstract: The deposition of radionuclides manganese-54, cobalt-58 and cobalt-60 from liquid sodium coolant is controlled by providing surfaces of nickel or high nickel alloys to extract the radionuclides from the liquid sodium, and by providing surfaces of tungsten, molybdenum or tantalum to prevent or retard radionuclide deposition.

Abstract: In a blow-off device for limiting excess pressure in nuclear power plants, a condensation tube disposed so that a lower outlet end thereof is immersed in a volume of water in a condensation chamber having a gas cushion located in a space above the volume of water, and an upper inlet end of the condensation tube extends out of the volume of water and is connectible to a source of steam that is to be condensed or a steam-air mixture, the outlet end of the tube, for stabilizing the condensation, being provided with a base member at the mouth of the tube for limiting steam flows discharging in axial direction of the tube and being formed with lateral outlet openings for subdividing the steam flow and the bubbles produced in the volume of water, the base member at the tube mouth being formed at a conical insert member having a base fastened to the condensation tube in vicinity of the mouth thereof and having an apex extending into the tube mouth, the lateral outlet openings being disposed at least within the axial

Abstract: A gas-cooled nuclear reactor, having a tight connection with an intentionally provided leak site between a fission-gas discharge channel formed in a reactor core carrying plate as well as in a head portion of encased fuel elements that are suspended in receiving bores formed in the core carrying plate, the tight connection being formed by an annular member having a sealing surface engaging the core carrying plate at a region thereof in which an opening to the fission-gas discharge channel formed in the core carrying plate is located, a gas-tight, elastic and substantially cylindrical member, variable in length, connecting the annular member to the fission-gas discharge channel formed in the head portion of the fuel element, compression spring means biasing the annular member in a direction away from the fission gas discharge channel formed in the fuel-element head portion, and a sealing abutment plate secured to a central pin and limiting clearance for play of the annular member with respect to an annular zon

Abstract: The angle through which the crankshaft of an engine rotates within any given time is proportional to the rotational speed of the engine. Consequently, where the ignition system is of the type in which the integrated value of an integrator circuit or the count value of a counter circuit is varied so as to control the spark advance, if the rate of increase or decrease of the integrated value or the count value within a portion of the increasing or decreasing time is made different from that within the remaining portion of the time, the integrated value or the count value is directly affected by the engine rotational speed. In other words, the spark advance is directly controlled by the factor of the engine rotational speed, thus ensuring satisfactory response characteristic and accuracy for the ignition system.

Abstract: A method of detecting and monitoring leaks in the piping of a nuclear reactor senses the acoustic energy from the leak and analyzes its frequency spectrum versus acoustic amplitude. A choke flow condition will exist where the leak flows at sonic velocity; here the acoustic energy is directly proportional to the area of the crack producing the leak. This is utilized to provide an indication of crack enlargement.