Abstract: An apparatus for cooling molten material resulting from a nuclear reactor core meltdown is disclosed. The apparatus includes a basin positioned under the reactor which is protected against excessive heat by a star-like array of heat pipes whose evaporator sections are disposed above the pan and whose condenser sections are disposed in a heat sink exterior to the containment building of the reactor. Additionally, the vertical walls of the reactor vessel chamber are similarly protected by an array of heat pipes similarly arranged and provided to intercept the radient energy of the molten core material.

Abstract: A self-actuating, self-locking flow cutoff valve particularly suited for use in a nuclear reactor of the type which utilizes a plurality of fluid support neutron absorber elements to provide for the safe shutdown of the reactor. The valve comprises a substantially vertical elongated housing and an aperture plate located in the housing for the flow of fluid therethrough, a substantially vertical elongated nozzle member located in the housing and affixed to the housing with an opening in the bottom for receiving fluid and apertures adjacent a top end for discharging fluid. The nozzle further includes two sealing means, one located above and the other below the apertures.

Abstract: A gas charging device injects hydrogen into the pressurized water that cools the core of a nuclear power reactor through nozzles provided in a pressurized water flow pump. Conduit and valve combinations also are provided to permit solid matter to be flushed from the nozzles.

Abstract: Methods and apparatus for merging of tokamak plasmas, having applications including pseudo steady-state tokamak operation, refueling, impurity removal and plasma heating. In such systems, currents of two merging tokamak plasmas are provided in the same direction so that the plasma columns attract each other, and the merging of the plasmas is carried out under the control of appropriate guiding fields.

Abstract: Method and apparatus for initially producing a sharp boundaried theta-pinch plasma, and subsequently relaxing the current sheath of the plasma to provide a diffuse-pinch plasma, in which the diffuse pinch plasma has a doublet or higher multiplet magnetic confinement configuration with one or more internal separatrices, and in which the initially formed, sharp-boundaried plasma is provided with a current sheath having a contour corresponding to a flux surface of the doublet or multiplet configuration.

Abstract: Method and apparatus for continuously driving a current in a toroidal plasma through r-f induced, asymmetric trapping or detrapping. The method and apparatus may be used to supply ohmic current over a prolonged or indefinite time period and thus provide for steady state operation of toroidal plasma apparatus such as tokamaks.

Abstract: A lighting device for producing a chasing light effect. A star connected network having three or more conductors, three or more flexible branches, and a common is disposed within a transparent tube. Each of the branches is provided with at least one miniature light source connected to the common. A coupler is secured at one end to the transparent tube and at the other end to a multiple wire cable connected to a sequencer. The multiple wire cable and the star connected network are electrically connected within the coupler. The sequencer excites the network branches in a predetermined sequence.

Abstract: An electromagnetic filter of the type provided with a magnetizable packing and placed in the water circuit of a nuclear reactor is cleaned by a method which first consists in isolating the filter from the circuit, then subjecting it to a series of washing and draining-off cycles. The washing operation consists in withdrawing a fraction of water from the circuit and introducing it substantially at the temperature and pressure of withdrawal and under such conditions as to impart turbulent flow to the water within the packing. The draining-off operation consists in discharging the wash water contained in the filter.

Abstract: A storage module or rack is disclosed for storage of nuclear fuel assemblies in a water-filled pool comprising an array of storage tubes arranged in a checkerboard pattern and attached to one another along their corners. Each tube thus forms a storage cell for a fuel assembly and the spaces between each four adjacent tubes form intermediate fuel assembly storage cells. The storage tubes are formed with spaced double walls between which is contained a layer of neutron absorbing material to assure that the array of stored fuel assemblies remains subcritical. Provision is made for free circulation of water through the storage cells to extract heat from the stored assemblies. The storage module maximizes the number of fuel assemblies that can be stored in a given space while minimizing the material used in its construction.

Abstract: A gas-cooled, and preferably helium cooled, graphite-moderated high temperature nuclear reactor of the kind having a pressure vessel containing a reactor core with fuel elements, graphite components and a primary coolant gas circuit including a steam generator and coolant gas blowers, has the steam generator disposed outside the pressure vessel and the steam generator includes a heat exchanger at least a portion of which is located above the level of the reactor core. This situation of the heat exchanger ensures that when the reactor is shut down, either intentionally or owing to a fault, a natural convection flow takes place through the coolant gas circuit and this natural convection flow is in the same direction as it is when the blowers are functioning so that the flow conducts away the decay heat from the core to the steam generator in the same way as when the blowers are in operation.

Abstract: A single filament dual function shock mounted or conventional vehicle signal lamp assembly adapted to be connected to vehicle safety light signalling circuits to serve tail and stop/turn lamp functions and the like, comprising a unitary molded rear backing housing member serving as a reflector and a lamp housing and a lens cover member sealed about its perimeter to the housing member and enclosing a single filament lamp bulb which may be shock mounted within the cavity of the housing. A generally flat annular electronic circuit board in the form of an interrupted ring shaped to encircle the housing cavity is mounted inwardly adjacent the lens cover at the perimeter of the cavity and includes a pair of unidirectionally conductive diodes and an elongated resistor element rigidly mounted on the circuit board to couple the lamp bulb to vehicle control circuits to serve tail and turn/stop signal functions.

Abstract: A car light having a variety of practical applications, for example, as a map light with its detachable plug being retained and as an illuminating or warning light for use outside of a car with the plug being detached from the body of the car light. The plug is sized to plug in the cigarette lighter socket of the car and to be retained in its receptacle when a cord is rewound on a reel within a cord chamber between a reflecting mirror and an outer casing by turning either of the mirror of the casing relative to the other.

Abstract: A nuclear energy plant with a reactor protecting container in which below the reactor core there is provided a cooled collecting container for molten core masses while cooling pipes are inserted in the wall of the collecting container. The cooling pipes are designed as heat pipes. One end of the pipes is arranged within the region of the inner wall of the collecting container. The other end of the pipes extends into the inner chamber of the cooling tank which is arranged outside the reactor protecting container or containment and is open toward the atmosphere.

Abstract: An enclosed reservoir is sized and located in relation to the steam generator of a pressurized water nuclear reactor power plant so that upon a loss of feedwater flow to the steam generator, a gravity induced supplementary flow into the steam generator is automatically initiated to dissipate the residual heat generated in the reactor. The height of the reservoir is the same as the distance between upper and lower design limits on steam generator feedwater level. The top of the steam generator is fluidly connected to the top of the reservoir to equalize the pressure therebetween. The gravity induced flow from the reservoir to the steam generator produces a water level in the steam generator that stays within the upper and lower design limits.

Abstract: According to the invention, the drive of a nuclear reactor's control element comprises an electromotor having a stator and a rotor composed lengthwise of two parts whose total length is equal to that of the active part of the stator. One part of the rotor is a solid cylinder-shaped member. The other part of the rotor comprises at least three double-arm rocking levers, the pivot axes of which are parallel to the axis of a drive screw. One arm of each of said levers is a rotor pole. The other arm of each of said levers carries a roller, the axis of rotation of which is parallel to the axis of the drive screw. Said rollers make up a detachable roller nut which interacts with the drive screw under the action of an electromagnetic field.

Abstract: For coupling pipelines in a nuclear reactor pressure vessel with a core flood line formed of a first line section extending sealingly through a housing wall of the reactor pressure vessel and secured thereto, and a second line section disposed in the interior of the pressure vessel and couplable sealingly to the first line section, the second line section extending through a cover of a core container and terminating in the core container, a device includes means for forming the second line section and the core container cover into a structural unit so that the second line section together with the core container cover is liftable out of and insertable into the pressure vessel upon opening the latter for selectively inspecting, servicing and both inspecting and servicing the same, the first and second line sections having a mutual coupling location, means defining coaxial sealing surfaces disposed at the mutual coupling location for holding the first and second line sections in mutual engagement, the coaxial s

Abstract: In a nuclear reactor installation, a steam generator's live-steam line leading through the containment, is equipped with a fast-acting shut-off valve, to shut off the steam in the event of a line break. If the steam pressure rises in the generator, the valve acts as a safety valve and releases a small amount of steam, so that there is no danger of damage to the steam generator. The invention is of interest particularly for light-water reactors, e.g., pressurized-water reactors.

Abstract: The proposed gripping means for fuel assemblies of a nuclear reactor comprises a housing, whereupon there is movably mounted a slider provided with longitudinally extending slots to receive gripping jaws whose tails are pivotably secured to the housing of the gripping means. On one side, the end faces of the longitudinally extending slots are slanted with respect to the longitudinal axis of the gripping means and come in contact with the teeth of the gripping jaws provided on the end which is opposite to the tail, whereby the jaws open as the slider and housing of the gripping means moves relative to each other so that the teeth are received in an internal groove provided in the head of the fuel assembly.

Abstract: Device for removing heat of decomposition in a steam power plant heated by nuclear energy and having a steam generator with a water-steam separating tank connected downstream of the steam generator in travel direction of the steam generated thereby includes a start-up circulatory loop for the steam power plant connected to the steam generator and including the water-steam separating tank therein, the start-up circulatory loop being formed of a feed water line and an outlet line from the water-steam separating tank and further including an externally cooled heat exchanger connected therein for removing after-heat.

Abstract: The proposed nuclear reactor comprises fuel assemblies whose heads are shaped as prisms and provided with an internal hollow for the working member of the gripping means to grip and handle the fuel assembly. The gripping means is accommodated in a guide member of a refuelling device having an end face shaped as a truncated cone whose vertex is directed towards the head of a fuel assembly being handled. Recesses are provided in the end faces of the fuel assembly heads. The number of recesses is equal to that of fuel assemblies adjacent to the fuel assembly being handled. The recesses are arranged symmetrically with respect to the face edges of the fuel assembly heads. The sides of the recesses next to the recess which is adjacent to the recess of the fuel assembly being handled and facing the fuel assembly being handled all form parts of the surface of a truncated cone whose axis is matched with the longitudinal axis of the fuel assembly being handled.