Abstract: The invention pertains to the method and apparatus for the confining of a stream of fusible positive ions at values of density and high average kinetic energy, primarily of tightly looping motions, to produce nuclear fusion at a useful rate; more or less intimately mixed with the fusible ions will be lower-energy electrons at about equal density, introduced solely for the purpose of neutralizing the positive space charge of the ions.

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: This invention concerns a method and apparatus for use to exchange an O-ring interposed between an in-core housing disposed at the lower end of a guide tube for an in-core monitor for monitoring the operation of a nuclear reactor and an in-core flange attached to the housing. The apparatus comprises a drain system adapted to be connected to the lower end of the flange for draining reactor water, a split cylindrical guide member adapted to be suspended from an upper grid located in a pressure vessel after removing the in-core monitor, an operating mechanism to be inserted into the guide member, the operating member being hung down from a platform of the reactor, and a tubular repairing tool secured to the lower portion of the operating mechanism, the repairing tool being provided with a valve member which is to be water-tightly engaged with a valve seat formed for the housing when the operating mechanism is lowered into the guide member.

Abstract: A process for the insertion and exchange of the filter elements for suspended matter is performed from the clean-air-side. During the insertion of a filter element, a plastic tube (which encircles the circumference of the filter element and which exceeds in its length the layer thickness of the filter element several times) is tightly connected in its middle section with the side walls, which side walls form a border around the filter element; and then the open end of the plastic tube, which faces the frame, is connected by way of a tight fit with a ring, which is actually known and which surrounds the orifice of the frame into which the filter element is inserted. The filter element is connected with the frame by means of tightening devices, and the outer free end of the tube is turned inside out and around the filter element for the purpose of unhindered air passage through the filter layer, that during the exchange of the contaminated filter element, the outer open end of the tube is heat sealed.

Abstract: In a nuclear reactor, a drainage channel for the safety injection and spray circuits of the reactor is arranged in the bottom of the annular gap between two substantially vertical walls surrounding the pressure vessel of the reactor, the drainage channel comprising filter panels disposed vertically along each side of a central horizontal solid lower panel at the bottom of the annular gap and between two lateral horizontal solid upper panels so as to bound a central channel having vertical lateral filter walls communicating with two lateral chambers which communicate by substantially horizontal passages with a central collecting chamber disposed below the central lower panel and having an outlet for connection to the main intake of the safety circuit.

Abstract: A method and apparatus for plasma impurity control in closed flux plasma systems such as Tokamak reactors is disclosed. Local axisymmetrical injection of hydrogen gas is employed to reverse the normally inward flow of impurities into the plasma.

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: 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: A steam propulsion system for planes or vehicles, which utilizes a directional thrust, generated by nuclear heated water and air.

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: A nuclear energy installation having at least one gas collecting chamber so divided through the intermediary of separator walls that the gas conduits and/or gas distributors of each cooling gas circuit discharge into an isolated or separate gas chamber which, through one or more pressure-compensating apertures with a collective high flow resistance in comparison with the flow resistance of the remaining gas conduits and gas distributors, is connected with at least one further gas chamber of the same gas collecting chamber whereby the separator walls evidence a stiffness or rigidity enabling them to withstand the pressure differentials which are produced between the gas chambers upon the rupture of a pressure-supporting wall structure or gas conduits.

Abstract: A method and an apparatus are disclosed for measuring the neutron flux existing within a nuclear reactor. According to the method of the invention, a neutron sensitive material is inserted into a reactor and electrons emitted by this material are guided, with the aid of a magnetic field, through an evacuated tube to the exterior of the reactor. Detection of these electrons is carried out after they have reached the exterior of the reactor. The apparatus of the invention includes an evacuated tube having a neutron sensitive material adjacent one end thereof. Apparatus is provided for generating an axial magnetic field along the length of the tube for guiding electrons emitted by the neutron sensitive material. A detector is positioned at the opposite end of the tube for sensing the emitted neutron flux.

Abstract: Disclosed is a support structure consisting of several layers of prismatic graphite blocks arranged over each other. The layers are constructed as closed units without expansion gaps and the blocks of one layer are keyed together with the blocks of the adjacent layers. The upper layers are composed of a plurality of preferably hexagonal graphite blocks equipped with passages for the cooling gas, while the bottom layer is formed by a number of support structures, each consisting of several support segments fitted together preferably into a hexagonal cross section, with each support unit resting at its central section on a column head of a round column and carrying a limited number of the hexagonal graphite blocks and that cooling gas channels are provided at the locations of the bottom layer where three support units meet.

Abstract: Safety apparatus for a nuclear reactor comprising an absorbing element having a supporting head connected by a disconnectable linkage constituted by the armature of an electromagnet to the end of an axially movable vertical operating rod, said linkage being such that in the case of a disconnection the absorbing element slides by gravity in a passage bounded by an open container through the core of the reactor, wherein the operating rod is associated with a metal member having an expansion coefficient which is significantly higher than that of the armature of the electromagnet, whereby in the case of a temperature rise a separating force is exerted between the head of the absorbing element and the operating rod.

Abstract: A primary working gas is heated in a high-temperature nuclear reactor and ives at least one primary turbine set to operate an electrical generator to generate electric power. Heat is abstracted from the primary gas by recuperative heat exchange and the primary gas is compressed and heated by the recuperative heat exchange and introduced into the nuclear reactor for further heating therein. Upon the development of an increased electrical power demand, a secondary gas is heated by the recuperative heat exchange and drives an auxiliary turbine set and electric power generator to supply this peak demand.

Abstract: A nuclear reactor fuel element is described which has an outer cladding, a central core of fissionable or mixed fissionable and fertile fuel material and a layer of oxygen gettering material on the inner surface of the cladding. The gettering material reacts with oxygen released by the fissionable material during irradiation of the core thereby preventing the oxygen from reacting with and corroding the cladding. Also described is an improved method for coating the inner surface of the cladding with a layer of gettering material.

Abstract: Improved shock absorber for slowing down the descent of a control rod in a liquid cooled reactor core at a controlled rate uses a thimble tube which has a corrugated section at its lower end to distribute the control rod deceleration forces over an extended distance in a "scram" situation. In a preferred embodiment, the corrugations have a lesser internal diameter at the lower end of the thimble tube than at the top to increase the rate of deceleration as the control rod aproaches the bottom of the core. In several modifications, the corrugation pitch and/or depth is varied over the length of the corrugated surface.

Abstract: Method and apparatus for monitoring and signalling the quantity of a known gas, or gases, in a gas mixture. The monitoring system is particularly adapted to continuously sense the quantity of hydrogen or oxygen in the containment gas mixture for a nuclear reactor electrical power generator. The monitoring system utilizes thermal conductivity gas measuring cells arranged in an electrical bridge network along with a catalytic reactor for modifying the constituency of the containment gas mixture undergoing measurement to provide the signal representative of the changes in constituency of the containment gas mixture at the power generating site.

Abstract: In the detection of cracks in fuel element units using a crack detection cell, the cell includes heating means which are energized to heat the unit. The heating means form part of a pocket in which the unit is received, the pocket being received in a double-walled chamber which can be thermally insulated from the surrounding medium.