Abstract: The crane operated lifting apparatus for safely gripping and holding obje (11) includes a plurality of movable pawls (3) which enter into a groove, aperture, or bore (14) of an object (11) which is to be transported. To move the pawls (3), a driving member (4) is provided which is displaceable in a basic body (1). The lifting apparatus also includes comprises two holding members (2,5) the first of which is firmly attached to the basic body (1) while the second one is connected to the driving member (4) for a tilting or pivoting motion. Thus, the hook of a crane may selectively grasp either one of the two holding members (2,5) or both of them (2,5) together, and it may also selectively swing the second holding member, (5). In this manner it is possible to have all the functions, such as locking, unlocking, and conveying, accomplished by the hook of a crane alone.

Abstract: The invention is directed to an apparatus for performing the remotely-manlated installation and removal of a pass-through conduit unit into and out of a channel formed in a partition wall. A feed assembly is part of the apparatus and includes a plurality of parts assembled to form an elongated body in the channel. An articulated coupling such as a ball joint couples the conduit unit to the elongated body. A drive is operatively connected to the elongated body for displacing the latter in the channel. A crane has a holder for holding and remotely manipulating the conduit unit as the latter is installed or removed from the channel.

Abstract: The remote control and remote handling accessory is of such design that an xchange part (7) contains all elements subject to wear of the accessory, while the anti-wear elements, in particular the accessory case (2) remain firmly connected to the pipeline (1). The exchange part (7) and the accessory case (2) are mutually fixed by a clamping bracket (9). The exchange part (7) comprises a central bolt (16) which is displaceable with respect to the other components of the exchange part (7) and is supported in both axial directions by the clamping bracket (9) which is adapted to be swung open. In this manner the exchange part can be pressed into and pulled out of the anti-wear part (accessory case 2). The other components of the exchange part (7) are connected to a cover (15) with respect to which the central bolt (16) is rotatable, the cover (15) being secured to a slide shoe (8) of a stationary guide rail (4).

Abstract: The invention is directed to a method of washing a solvent in the reprocessing of irradiated nuclear fuel. The solvent is washed with an aqueous solution in a mixer-settler having at least one stage which includes a mixing chamber and a settling chamber. The pH of the dispersion in the mixing chamber is measured and an amount of washing solution is added which influences the pH toward the desired operational value. An apparatus for carrying out the method is also disclosed.

Abstract: The invention relates to a method for handling a fuel element skeleton of an irradiated nuclear reactor fuel element from which the fuel rods have been removed. The fuel element skeleton is placed horizontally in a compacting shaft of a ram-type press in order to obtain a simple and reliable compaction of the skeleton. After the compacting shaft is closed, the fuel element skeleton is compacted against a press base. The compacted fuel element skeleton is pushed out of the compacting shaft and into a transportable transfer shaft. The loaded transfer shaft is removed from the ram-type press and transported away to a transfer loading location.

Abstract: Apparatus and method for treating and conveying feed sludge to a vitrification device in which sludge in suspension is dried in a fluid bed of preheated glass frit suspended in nitrogen gas. The mixture of dried glass frit and sludge is conveyed pneumatically in a stream of nitrogen gas to the vitrification device. The dried mixture flows through conduits without causing blockage which characterized the prior art.

Abstract: To determine the quantity of filling and/or loading of the drum of a clarifying centrifuge loaded with radioactive fluids from nuclear power plants, and to determine the burn-off, the gamma rays from the fluids are measured spectroscopically. From the gamma spectrum for one or several nuclides present in said fluids, the gamma line is evaluated to quantitatively determine the filling and/or loading quantity. The amount of the fluid supplied is preferably determined by means of the gamma spectrum of cesium 137/134. The sedimented solid portions, are preferably determined by means of the gamma spectrum of rhodium 106. To measure the burn-off, the gamma radiation of cesium and/or cerium is spectroscopically measured during the initial filling phase of the drum, the measuring phase lying between the beginning of the filling and the beginning of sedimentation.

Abstract: The invention relates to an ejector to be placed in rooms which are inaccible to human beings. It comprises a casing with a diffuser bore, a head chamber, and a space for a working fluid including a lateral working fluid connection. The working fluid nozzle comprises a working fluid chamber which is connected through bores with the working fluid space and, inside the casing, it seals the head chamber from the working fluid space. The nozzle of the working fluid chamber opens into the head chamber and faces the diffuser bore. The invention is characterized in that the ends of the casing and of the working fluid nozzle each are embodied as a radial flange which flanges are held together by bolts adapted to be operated by a manipulator. At the end of the working fluid nozzle flange there is a handle which is operable by a manipulator to pull the working fluid nozzle out of the casing and to reintroduce it, respectively.

Abstract: The invention is directed to a method for electrochemically decomposing iganic material contained in an aqueous radioactive waste solution. The solution is concentrated by evaporation in order to reduce its volume for further treatment as a waste solution. In order to achieve a more effective decomposition of inorganic compounds in the aqueous radioactive solution, an electrolytic process is performed during evaporation of the waste solution with the electrolytic process effecting the electrochemical decompostion. An apparatus for carrying out the method includes an evaporator for accommodating the waste solution and the evaporator is configured as an electrolytic cell.

Abstract: A method of continuous measurement of the depth of fill of a radioactive ss melt flowing from a melting furnace or from a storage container into a chill mold (special steel receiver) consists in measuring the electrical resistance of the flowing jet stream. From the measured electrical resistance, which is proportional to the length of the jet of molten glass, the length of the stream of molten glass is determined. The length is a measure of the depth of fill. It decreases with increasing depth of fill. In an apparatus for the performance of the method the jet of molten glass is part of an electrical circuit which includes a current measuring instrument connected to an evaluator unit. The method and the apparatus enable the measurement of the depth of fill with the lowest outlay and the possibility of performing redundant diversionary measurements, whereby a high degree of availability may be achieved. Work of operation by hand on the chill mold is not impeded.

Abstract: The invention is directed to an apparatus for pulling a plurality of fuel ds out of a fuel element structure and has a gripping device which is capable of clamping the fuel rods. To reliably pull the fuel rods from an irradiated nuclear reactor fuel element, the apparatus includes an upper guide rod and a lower tension rod which lie horizontally and are arranged one above the other. The rods extend through a plurality of clamping plates in a direction perpendicular to the latter. The clamping plates are mounted so as to be parallel to each other and spacers are arranged between each two mutually adjacent ones of the clamping plates. The spacers are arranged on both rods with the width of the spacers on the lower rod beign slightly less than the diameter of a fuel rod. The clamping plates are pressable together by means of a tensioning device. The apparatus of the invention enables the gripping device to be placed on the fuel element in a simple manner.

Abstract: The invention is directed to a coupling arrangement for changing a compon on a block of a hoist which is fitted with a rotary drive. The coupling arrangement has an upper part which remains on the block and which has a latching mechanism for accommodating a lower part. Each tool or component which is to be coupled to the block has a lower part which can be coupled and latched together with the upper part so that by changing the lower part, it is possible to change the component. In order to achieve a reliable and rapid remote exchange of a component on a hoist, the upper part is configured as a hollow cylindrical part which is provided with a bottom wall. The bottom wall has a central aperture from which extend two radial slots. The hollow cylinder and the lower wall conjointly define a housing for the latching mechanisms which are disposed at about 90.degree. in relation to corresponding ones of the radial slots.

Abstract: A method and apparatus for separating the fuel rods (15) in a fuel element 8), whereby the former are retained in a bird cage arrangement (16, 18) between a head piece (19) and a foot piece (19'). The fuel elements (8) is located on a support table (6) with the help of a clamping arrangement (10). Before the fuel rods can be separated, the head piece and the foot piece are removed. In order to simplify removal of the fuel rods from the fuel element, to save space, and to minimize any risk of breakage after removal of the head piece (19) and the foot piece (19'), the bird cage arrangement (16,18) is progressively stripped from one layer of fuel rods to the next and from around the fuel rods. The exposed fuel rods are then lifted out of the fuel element (8) layer by layer and reshuffled in a more compact arrangement. A cutting tool (24), provided with a cutting disk head (26), is used to strip and separate the fuel rods with the help of a grappler (28).

Abstract: The invention is directed to a method for electrochemically decomposing inorganic material contained in an aqueous radioactive waste solution. The solution is concentrated by evaporation in order to reduce its volume for further treatment as a waste solution. In order to achieve a more effective decomposition of inorganic compounds in the aqueous radioactive solution, an electrolytic prosess is performed during evaporation of the waste solution with the electrolytic process effecting the electrochemical decomposition. An apparatus for carrying out the method includes an evaporator for accommodating the waste solution and the evaporator is configured as an electrolytic cell.

Abstract: A method is disclosed for loading and sealing a double container for tranrt and storage of radioactive material in which an inner cover is screwed into the inner container while said inner container is in a hot cell, and welding a second cover on the inner container outside the hot cell.

Abstract: The invention is directed to a method for producing a cement product for terminal storage of tritium water wherein activated bentonite capable of swelling is dispersingly mixed with the tritium water and the suspension obtained thereby is subjected to a swelling operation. The swollen suspension is dispersingly mixed with cement. The cured product has a water content of over 75% by weight.

Abstract: The invention is directed to a double-container unit for transporting and oring radioactive waste such as irradiated nuclear reactor materials. The double-container unit includes an outer shielding container and an inner storage container made of steel for the gas-tight inclusion of the radioactive materials to be stored. The outer shielding container provides the required shielding and mechanical security during handling and transport of the unit. In order to simplify the assembly and manipulation of such a double-container unit, an intermediate ring is seated in the loading opening of the shielding container and is joinable with this container. A shielding cover is attachable to the intermediate ring for closing the shielding container.

Abstract: The invention is directed to an apparatus for withdrawing a sample from a ass melting furnace. The apparatus includes a gripper for taking the sample and can be introduced through an opening in the furnace into the interior thereof. The apparatus includes a rectangular vertically upright open guide frame provided with vertical inner guides mounted on the sides of the frame. A carrier frame is mounted on the inner guides and is displaceable relative to the guide frame. The base of the guide frame is penetrated by a guide tube. A pull rod is coaxially and displaceably mounted in the guide tube and is fixedly attached to the base of the carrier frame. Two pairs of articulated lever units for pivoting two cooperating gripper half shells are mounted at the end of the guide tube and at the end of the pull rod. When pivoted together, the gripper half shells conjointly form a closed space to accommodate the sample.

Abstract: The seal for turning valve bodies, in particular for valves in radioactive lants, is composed of a molded element of flexible graphite which is coated with a thin, flexible tantalum layer. The tantalum enclosure surrounds the graphite molded element, preferably all around. The tantalum layer is sufficiently thin so that it remains flexible.

Abstract: A double container system for transporting and storing radioactive waste erials includes an inner storage container of steel for enclosing the radioactive material to be stored in a gas-tight manner and an outer shielding container which provides for the necessary shielding effect and mechanical security with regard to handling and transportation. A neutron moderator layer is disposed in an annular gap between the outer shielding container and the inner storage container. The neutron moderate layer is made of hydrogen-bearing material, preferably polyethylene. In order to provide a good shielding effect while at the same time providing very good conduction of heat from the inside to the outside, the moderator layer includes individual rings of polyethylene which are stacked one above the other. Arranged between each two mutually adjacent ones of the polyethylene rings is a ring of a heat-conducting metal material having an H-profile when viewed in radial section.