Abstract: A system is directed for remotely securing a canopy seal about a broken omega seal site between the control drive mechanism and the adapter tube of a nuclear reactor vessel so as to contain any radioactive leakage therebetween. The system includes a stalk measuring device for initially measuring the diameter of the adapter tube, a split canopy installation fixture which is adjusted according to the measurement detected by the stalk measuring device to position a two-piece canopy seal about the omega seal site, and a robotic weld arm for performing the upper and lower radial welds about the canopy seal as well as C-shaped vertical welds between the two-piece canopy seal.

Abstract: A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling.

Abstract: A method for preventing or reducing the formation of Co-60 contaminated material on the surfaces of a cooling water circuit of a nuclear reactor. The method is carried out during shutdown of the reactor. First, Co-60 contaminated material formed on the surfaces of the cooling water circuit is chemically removed. Then at least one iron compound is added to the cooling water in an amount sufficient to scavenge cobalt from the cooling water. Thereafter, oxygen is injected into the cooling water to provide a dissolved oxygen concentration sufficient to form an oxide film on the surfaces of the cooling water circuit. The oxide film so formed is substantially free of Co-60 isotope. This treatment reduces the radiation hazard to nuclear reactor personnel.

Abstract: A safety system grade dropped rod detection system for a pressurized water reactor (PWR) utilizes core exit thermocouples arranged in multiple trains and hot and cold leg RTDs to generate a safety system grade rod stop signal. The system generates from the temperature signals a relative power deviation (RD) and a curvature index (CI), which is the spatial second derivative of RD for each fuel assembly. The CI signatures not only provide rapid, reliable detection of dropped control rods, but also clearly identify failed and failing thermocouples.

Abstract: The invention relates to a process for the separation of at least one element such as Nb, Sb, Ce+Pr, actinides and elements from groups VIIb and VIII of the Periodic Classification of Elements from aqueous solutions resulting from the reprocessing of spent nuclear fuels.This process consists of contacting said aqueous solution with a solid resin based on a vinyl pyridine polymer or copolymer and separating from said solution the resin used for fixing said element or elements.The resin is in particular a poly(vinyl-4-pyridine) powder in crosslinked from and the separated elements are e.g. ruthenium, rhodium, palladium, technetium, manganese, cobalt, iron, nickel, cerium and praseodymium.

Abstract: System for the detection of substances and in particular explosives, by neutron irradiation thereof.It comprises means (4) for the irradiating, by neutrons, of an object (6) which may contain a substance, means (14) for detecting the gamma radiation which can be emitted by the object and means (18) for processing the signals supplied by the detection means. These processing means count the gamma photons of each line of a plurality of characteristic lines of at least one chemical element of the substance, determining for each line a probability of false detection of the chemical element associated with said line, determine the product of these probabilities, compare said product with a threshold fixed by users and notify the latter if the product is below the threshold, the object then being assumed to contain the substance.

Abstract: Radioactive metal is recovered from solid oxides of the metal by exposing the oxide to a cocurrent flow of a first acid solution in a first contactor to form partially reacted oxides and a solution containing the metal. The first solution containing the metal is drawn off and the partially reacted oxides are passed through a countercurrent flow of a second acid solution in a second contactor to form reaction residues and a second solution containing the metal. The second solution containing the metal is drawn off and the reaction residues are passed through a countercurrent flow of wash water in a third contactor. The reaction residues are then separated from the wash water and dried.

Abstract: A testing device for load-testing of specimens (3) in a nuclear reactor environment is attached to one of the pipes (1) of the reactor for conveying a first medium under pressure and provides a first space (14) in open communication with the pipe (1). In the first space (14) a movable pull rod (15) is arranged, one end of which is attached to one half (16) of a specimen (3) arranged in the space (14). The other end of the pull rod (15) is joined to a tensile force device capable of being influenced by the first medium for achieving a tensile stress in the specimen (3).

Abstract: A mercury-free dissolution process for aluminum involves placing the aluminum in a dissolver vessel in contact with nitric acid-fluoboric acid mixture at an elevated temperature. By maintaining a continuous flow of the acid mixture through the dissolver vessel, an effluent containing aluminum nitrate, nitric acid, fluoboric acid and other dissolved components are removed.

Abstract: A method of manufacturing fuel channels made of zirconium-based alloy by combining heat treatment, warm forming and thermal sizing. Fuel channel strip material is heated to a temperature which initiates the transformation from a hexagonal close-packed to a body-centered cubic crystallographic phase and then quenched at a rate which initiates transformation to a hexagonal close-packed crystallographic phase having a texture factor f.sub.L =0.28-0.38. The heat-treated strips are formed into fuel channel components by bending at an elevated temperature sufficient to increase the ductility of the strip material. After the fuel channel components are welded together, the fuel channel is annealed by thermal sizing.

Abstract: A reactor core for a boiling water nuclear reactor comprises a plurality of vertical fuel assemblies (40), each one containing a plurality of fuel rods (10, 10a, 10b) with enriched nuclear fuel material, which are arranged between a bottom tie plate (11) and a top tie plate (12) in a surrounding vertical fuel channel (1). Each fuel assembly is designed with an inlet (3) for water for conducting water in through the bottom tie plate, through the vertical fuel channel, and out through the top tie plate. Further, each fuel assembly is arranged with intermediate gaps (37a, 37b) with respect to adjacent fuel assemblies and possibly with a channel (32, 50) arranged internally in the fuel assembly for conducting water through the gaps and through the internal channel (if any) in a vertical direction from below and upwards through the core.

Abstract: A removable feedwater sparger assembly includes a sparger having an inlet pipe disposed in flow communication with the outlet end of a supply pipe. A tubular coupling includes an annular band fixedly joined to the sparger inlet pipe and a plurality of fingers extending from the band which are removably joined to a retention flange extending from the supply pipe for maintaining the sparger inlet pipe in flow communication with the supply pipe. The fingers are elastically deflectable for allowing engagement of the sparger inlet pipe with the supply pipe and for disengagement therewith.

Abstract: A method of constructing the top slab of a nuclear reactor container in which a flange for mounting the top head of the container is prepared separately from the sleeve of the container. When the outside diameter of the flange is greater than the inside diameter of a doughnut-shaped steel; reinforcement structure assembled on the container, the steel reinforcement structure is situated in place and then the flange is welded to the sleeve, thus shortening the construction period. Disclosed also is a nuclear reactor container constructed by this method.

Abstract: A method of encapsulating radioactive materials inside fullerenes for stable long-term storage. Fullerenes provide a safe and efficient means of disposing of nuclear waste which is extremely stable with respect to the environment. After encapsulation, a radioactive ion is essentially chemically isolated from its external environment.

Abstract: A fuel assembly for a light water reactor comprising a plurality of fuel rods which contain plutonium as a primary fissile material when exposure is zero, and a light water reactor including such fuel assemblies. The fuel assembly has a structure in which at least one of moderator rods is provided at least in one of each corner portion of an arrangement of the fuel rods and a position adjacent to the corner portion in such a manner that the moderator rods are located in rotation symmetry, each of the moderator rods being filled with water or a solid coolant over a length at least corresponding to a fuel effective length, and the fuel rods are provided at positions in the second layer from the outermost periphery which are adjacent to those positions at which the moderator rods are located.

Abstract: A tool for remotely installing a plug in a steam line of a reactor vessel. The tool has a strongback assembly on which a plug is securely mounted, a collapsible structure (e.g., a scissors jack assembly) which supports the strongback assembly and is movable between an extended state and a collapsed state, a hanging bracket assembly for hanging the collapsible structure inside the reactor vessel, and a rotatable actuating screw coupled to the collapsible structure. The collapsible structure moves between the extended and collapsed states in response to rotation of the actuating screw. During this operation, the plug is carried from a retracted position outside and aligned with the steam line nozzle to an inserted position inside the nozzle.

Abstract: In a fuel assembly, lower end pieces of fuel rods, guide tubes and coolant pipes, etc., are inserted and/or screwed into a base plate and secured against lifting by a bolt. In the case of fuel rods, in particular fuel rods which do not extend over the entire length of normal rods, the bolt is screwed onto connecting parts in such a way that a releasable bayonet closure is produced. In the case of coolant pipes of boiling water reactors, there is provided in particular a screw connection which is irreleasably secured against torsion by the bolt.

Abstract: An apparatus decontaminates a radioactively contaminated surface region of a pipe, connector or vessel being open at one end, with a dry mechanical blasting medium. The apparatus includes a processing bell to be mounted on the open end of the pipe, connector or vessel. A flexible dustproof duct is connected to the processing bell. A retaining device protrudes into the duct and is movable from outside in the interior of the pipe, connector or vessel. A blasting head is disposed on the retaining device. A blasting system is connected to the blasting head and has a continuous circulation of the blasting medium.

Abstract: The invention is a process for selectively extracting strontium values from aqueous nitric acid waste solutions containing these and other fission product values. The extractant solution is a macrocyclic polyether in an aliphatic hydrocarbon diluent containing a phase modifier. The process will selectively extract strontium values from nitric acid solutions which are up to 6 molar in nitric acid.

Abstract: The present invention provides a cladding having an outer circumferential substrate, a zirconium barrier layer metallurgically bonded to the inside surface of the substrate and an inner circumferential liner metallurgically bonded to the zirconium barrier. The inner circumferential liner is more ductile than conventional Zircaloy. The low ductility of the inner circumferential liner is obtained, for example, by using a zirconium alloy containing a low tin content (e.g. less than 1.2% by weight) and/or a low oxygen content (e.g. less than 1000 ppm). The inner circumferential liner is less than about 25 micrometers thick.