Abstract: A drive for positioning a control rod in a nuclear reactor core is disclosed. The drive includes a turbine rotor joined to a hollow spindle in a housing. The spindle has a piston disposed therein and a piston rod extending therefrom and through a bottom end of the spindle for being joined to the control rod. A pressurized fluid is provided into the spindle for exerting a pressure force against the piston for moving the piston for selectively gripping the control rod. Interruption of the pressurized fluid to the spindle causes ungripping of the control rod.

Abstract: A composite member which comprises at least two molding members made of different compositions each comprising a metallic powder and/or a ceramic powder and a resin material is described. The at least two molding members are fully integrated through bonding of the resin materials in the respective members. A method for fabricating the composite member is also described, in which at least one molding member is bonded with another member which is filled in molding dies in the form of a powdery mixture and heated to a temperature sufficient to melt resin materials in the respective members to integrally bond the member through bonding of the resin materials.

Abstract: The above device consists mainly of a rigid explosion tank (10) with a closed rear end (11) and a front opening (12). Said tank is mounted in the direction of the slope on which the avalanche is to be triggered. It is connected to a fuel gas supply station (19) and to an oxygen-carrying gas supply station (20). These two stations are linked by pipes (17 and 18) to injection nozzles (16) situated inside the tank (10). An ignition device (29) is mounted in the bottom of the tank and can be operated by remote control by means of a triggering device (30). An advantage of the above device is that the explosion is exponentially propagated inside the rigid explosion tank and causes a powerful high-velocity blast to be expelled from the latter.

Abstract: A reentry body nose tip constructed from materials and produced by a proc such that shape stability is maintained under ablative erosion occurring during atmospheric reentry.

Abstract: A thermoelectric material can be obtained by co-pulverizing and mixing a material containing at least bismuth and a material containing at least tellurium, without being alloyed by melting, and then molding and sintering. This thermoelectric material has high performance and can be utilized in a variety of fields such as thermoelectric power generation and thermoelectric cooling, a temperature sensor space development, marine development, and electric power generation in the remote areas. Since metal elements are used as a starting material, the starting material can be easily prepared. Moreover, in the production steps, the thermoelectric material can be produced in a high yield at a low energy consumption level by a simplified manner, without a complicated operation or special apparatus, and its production cost can be decreased.

Abstract: Selection criteria are disclosed for choosing a coreactant RX that will improve the isotope separation in laser-activated chemical reactions which may proceed by the steps:ti .sup.i MY+h.nu..sub.L .fwdarw..sup.i MY*(Laser Activation of Isotopic Materials)RX+h.nu..sub.L .fwdarw.RX*(Laser Activation of Coreactant).sup.i MY*+RX.sup.(*) .fwdarw.(.sup.i MY*:RX.sup.(*)) .fwdarw..sup.i MX+RY(Chemical Exchange Reaction)The step of coreactant activation can be important in some exchange reactions but unnecessary in others. That is for some laser-activated chemical reactions, the second step may be absent.The selection criteria are based on the relative magnitudes of the bond-energies and therefore vibrational frequencies in the molecules .sup.i MY and RX, and the requirements for forming a Vanderwaals-like attachment complex. Also, the upper and lower limit of tolerable thermal (non-laser) reaction speeds are defined.

Abstract: Disclosed are a method and apparatus for high speed, selective detection of vapors of specific compounds, particularly nitrogen-containing compounds, utilizing, a bypass branch and high speed gas chromatography for improved selectively and sensitivity of detection. A system with two gas chromatographs (GC's) alternating in series with two pyrolyzers provides two time intervals of detection in a downstream detector, with the second time interval containing signals delayed and further separated relative to signals from the first time interval. The bypass branch, in diverting a portion of the flow of gas samples from passage through the second gas chromatograph and second pyrolyzer, avoids interferences in the first time interval of detection from non-GC-retained compounds decomposed in the second pyrolyzer. Also disclosed is an arrangement for rapid, precise heating of vapor concentrator tubes in which vapors are rapidly focussed and then injected into a GC, and for rapid, precise heating of the GC's.

Abstract: A device for controlled combustion of an ignitable hydrogen/air mixture in a gas mixture of a nuclear power plant, especially in a containment thereof, includes a spark igniter for tripping an ignition process. At least one ignition source is connected to the spark igniter. The ignition source has a self-sufficient energy storage device. The ignition source has at least one first trip element connected between the spark igniter and the energy storage device for responding as a function of temperature to trip the ignition process, and at least one second trip element connected between the spark igniter and the energy storage device for responding as a function of pressure to trip the ignition process. The at least one first trip element is in thermally conductive contact and the at least one second trip element is in pressure-transmitting contact with the gas mixture to be monitored. The energy storage device discharges to the spark igniter if one of the trip elements responds.

Abstract: A system for measuring the power distribution in a reactor core includes a plurality of gamma detectors disposed outside of the reactor vessel which houses the reactor core. The gamma detectors correspond in number to the number of instrumentation tubes in the fuel assemblies in the reactor core to be sampled. A first plurality of separate flow branches connect the instrumentation tubes with the gamma detectors for routing the flow of coolant from the instrumentation tubes to the gamma detectors so that the gamma detectors can measure the .sup.16 N decay gamma activity in the respective instrumentation tubes of the fuel assemblies. A second plurality of separate flow branches connect a cold leg of the reactor coolant system with the gamma detectors for routing the flow of coolant from the cold leg to the gamma detectors so that the gamma detectors can measure the background gamma activity in the respective instrumentation tubes of the fuel assemblies.

Abstract: In a method and a device for introducing granular or pulverulent explosive into drill holes the introduction is suitably carried out by means of a hose like or tube like conduit (2) introducable into the drill hole, the explosive being transported through the conduit, e.g. with pressurized air. To obtain an explosive power reduced in relation to that obtained by complete filling of the drill holes with the explosive, only partial filling of the drill holes is carried out by eithera) providing the conduit (2) with a tool (12), which on withdrawal of the conduit out of the drill hole leaves an air filled cavity in the drill hole, orb) arranging in the drill hole elongated filler means (24) and carrying out feeding of the explosive while said means is located within the drill hole.

Abstract: A lightweight three sector reactor for use in space. The three sectors provide redundancy for safety and operation assurance. The reactor can be launched empty or fueled and can be fueled, emptied, and refueled while in space. The reactor can be used to power manned space platforms.

Abstract: A method for generating a beam of negatively charged hydrogen ions is described which comprises the steps of providing a source of metal hydride, heating the hydride to extract either atomic hydrogen or negative hydrogen ions directly therefrom, directing an electron beam onto the hydride or applying electrical charge to the hydride in order to ionize the hydrogen atoms or to prevent the ions from losing charge, and electrically accelerating the negative hydrogen ions so produced as a directed beam.

Abstract: A steam separator for a boiling water reactor includes a pressure vessel and a chimney spaced radiallly inwardly therefrom to define a downcomer therebetween for recirculating water, the chimney being disposed above a reactor core for channeling upwardly therefrom steam voids and water flow. An annular partition wall is spaced radially between the vessel and he chimney to define an annular collection chamber having an inlet for receiving a portion of the steam voids and water flow from the chimney, a steam outlet for discharging the steam voids from the chamber, and a flow outlet for discharging the water flow from the chamber into the downcomer.

Abstract: A method of controlling the power used and the ozone generated by an ozone generator. The rate of gas flow through the generator (and/or also the temperature or pressure) is used to either adjust or to limit the output of the power supply. A control signal derived from the gas flow rate is fed to the power supply, influencing its output and thereby affecting the power drawn by the ozone generator. This method enables the concentration or the total quantity of the ozone generated to remain relatively constant with varying gas flow rate, or it can continuously regulate the power level so as to automatically generate the highest possible ozone concentration at any flow rate. In addition, this method allows a single power supply and ozone generator to feed ozone to multiple users with different and/or varying demands, while holding the ozone concentration constant as the users go on and off independently of each other.

Abstract: A nuclear steam generator 10 with economizer 32 adjacent secondary side feedwater inlets 38a and 38b includes a secondary side divider plate 36 and handholes 40 at opposing 180.degree. locations in alignment with the ends of the plate 36. Notches 42 in the ends of the plate 36 adjacent the aligned handholes 40 facilitate inspection and maintenance access on the secondary side above tubesheet 22. To prevent bypass flow from one side of the divider plate 36 to the other, a novel flow blocker 50 of cylindrical shape is provided for mounting in handholes 40 and notches 42. The flow blocker 50 is defined by telescopically assembled member 52 and 62 which are biased in opposite directions by pre-loaded spring 64 therein to insure stability against vibration and flow induced loads. The flow blocker 50 fits sungly in notch 42 and handhole 40 and is bolted to the inside of closure plate 74 of handhole 40.

Abstract: Apparatus for separating molten salt by-product phase from molten uranium or molten uranium alloy product phase using a barrier which passes molten salt but retains molten uranium or molten uranium alloy. The operation of the barrier relies on the differences in the physical behavior of said molten salt from the behavior of said molten uranium or molten uranium alloy as they interact with each other and with said barrier.

Abstract: A fuel handling system for nuclear reactor plants comprising an improved underwater grapple means for transferring fuel units while submerged within a water containing reactor vessel. Wherein a novel structure is provided which allows for direct viewing downward for operating the grapple hooks.

Abstract: An aluminum alloy is prepared from an aluminum alloy powder having a composition of:lubricating componentPb: 3 to 15 Wt %;hardening componentSi: 1 to 12 Wt %;rainforcement componentone or more selected among Cu, Cr, Mg, Mn, NiZn, Fe and: 0.2 to 5.0 Wt %;and remainder of aluminum as principal material or matrix.To the aluminum alloy powder set forth above, powder state Pb in 3 to 12 Wt % is added. With the mixture of the aluminium alloy powder and Pb powder, a billet is formed. For the billet, extrustion process is performed in a extrusion ratio greater than or equal to 40. In the extruded block, Si particle dispersed in the aluminum matrix is in a grain size smaller than or equal to 12 .mu.m. Furthermore, at least of half of added Pb power particle is dispersed to have greater than or equal to 0.74 of circularity coefficient.

Abstract: A radial brake assembly is disclosed for selectively preventing rotation of a shaft, such as a shaft used in a control rod drive for a nuclear reactor. The brake assembly includes a stationary housing, a rotor disc fixedly connected to the shaft for rotation therewith, and a brake member disposed adjacent to the perimeter of the rotor disc. The rotor disc includes at least one rotor tooth and the brake member includes at least one braking tooth. The brake member is selectively positioned in a deployed position for allowing the braking tooth to contact the rotor tooth for preventing rotation of the shaft in a first direction, and in a retracted position for allowing the rotor disc and shaft to rotate without restraint from the brake member.

Abstract: An improved method of disposing of radioactive or hazardous liquid hydrocarbon compositions comprises placing the liquid hydrocarbons in a container and adding an organic ammonium montmorillonite in ratios of between about 1:2 and 3:1, by volume, respectively. The organic ammonium montmorillonite has at least 10 carbon atoms. A polar organic compound having between 1 and about 10 carbon atoms is also preferably added with the montmorillonite. Where the liquid waste material includes 5% or more of water in addition to the liquid hydrocarbon a minus 200 mesh sodium montmorillonite is also preferably added.