Abstract: A method and a device depressurize a nuclear power plant. A depressurization flow is conducted out of a containment shell into the atmosphere via a depressurization line having a filter system. The filter system contains a filter chamber having an inlet, an outlet, and a sorbent filter. The depressurization flow is first conducted in a high-pressure section, then is depressurized by expansion at a throttle device, then conducted through the filter chamber having the sorbent filter, and finally blown out. To enable an effective retention of activity carriers contained in the depressurization flow, including organic compounds containing iodine, the depressurization flow depressurized by the throttle device is conducted through a superheating section before the depressurization flow enters the filter chamber, in which superheating section the depressurization flow is heated from the not yet depressurized depressurization flow to a temperature that is at least 10° C. above the dew point temperature.

Abstract: The object of the present invention is a method for establishing so-called “mixed IN-CORE mappings”. Its essential purpose is to compensate a loss of density of a reference instrumentation, called “RIC instrumentation” (or “RIC system”), when a significant number of locations, initially used by the sensors of the RIC system, are occupied by fixed collectron-type rods. An obvious physical interest lies in the increase of the measurement density, and thus of the level of confidence, associated with the operating results deduced from the processing of these measurements. One application of the method according to the invention concerns a collectron-type detector calibration method placed inside a nuclear reactor core.

Abstract: A wind turbine is provided. The wind turbine includes a tower, the tower having an upper part, a middle part and a lower part, the lower and the middle part of the tower forming the base of the tower, waste heat generating equipment located in the middle part of the tower, and a cooling device with at least one cooling device inlet formed in the tower for introducing outside air surrounding the tower into the tower, wherein the cooling device is adapted to guide the outside air from the or each cooling device inlet into the lower part of the tower such that the outside air can ascend towards the middle part and upper part of the tower while cooling the waste heat generating equipment, characterised in that the or each cooling device inlet is located in the upper part of the tower.

Abstract: A method with which uranium from a natural uranium concentrate may be purified, including a) extracting the uranium present as uranyl nitrate in an aqueous phase A1 resulting from the dissolution of the natural uranium concentrate in nitric acid, by means of an organic phase which contains an extractant in an organic diluent; b) washing the organic phase obtained at the end of step a), with an aqueous phase A2; and c) stripping the uranyl nitrate of the organic phase obtained at the end of step b), by circulating this organic phase in an apparatus, as a counter current against an aqueous phase A3. The extractant is an N,N-dialkylamide and the ratio between the flow rate at which the organic phase obtained at the end of step b) and the aqueous phase A3 circulate in the apparatus where step c) occurs, is greater than 1.

Abstract: A method of operating a power generator is provided. The method includes determining an amount of oxides on a heat transfer surface of the power generator as a function of a concentration of a noble metal substance in the oxides; and altering operation of the power generator when the amount of oxides on the heat transfer surface reaches a predetermined value. A method of operating a nuclear reactor is also provided.

Abstract: A conveyor device has a sequence of two vibrating screens vertically separated (d) from each other and supplying an alignment bowl, to eliminate chips and residue from nuclear fuel pellets stored in bulk in a boat and to align them in order to fill fuel rods. Due to these two screens, pellets are set aside and turned over, and chips are efficiently separated in a pot, without any congestion of the system.

Abstract: This bottom end-piece includes nozzles for directing the flow of water of the reactor along the lower ends of the fuel rods, the nozzles being arranged at nodes of the substantially regular network of the fuel rods, and an anti-debris device which delimits water flow channels. At least some of the water flow channels are arranged at nodes of the substantially regular network. Direction nozzles are arranged at least partially in the channels in order to delimit water passages therewith, and at least one water passage includes a first section and a second section which are mutually offset radially relative to the corresponding node of the network in order to form a baffle.

Abstract: A stabilized foam formed from a foaming aqueous solution comprising from 0.1 to 7 mol of one or more decontamination, stripping and/or degreasing reactants per liter of solution and from 0.01 to 15% by weight of a solid stabilizing agent of solid particles type, with respect to the total weight of the solution, and a process for the preparation of said stabilized foam, to its use in decontaminating, stripping and/or degreasing a surface and to a process for decontaminating, stripping and/or degreasing a surface.

Abstract: A nuclear power plant is provided including a BWR, a reactor cooling system cooling the BWR, an HWC hydrogen injection system connected to the reactor cooling system and an alcohol injection system connected to the reactor cooling system. Methods for providing methanol and hydrogen are also provided.

Abstract: This invention applies optical tracking technology with an ultrasound inspection system to associate recorded position data with the inspection data. The reference targets of the optical tracking system can be attached to the inspection assembly to allow fully recorded position information to be associated with the ultrasonic, eddy current, or other nondestructive examination data without substantially impacting the overall envelope of the NDE inspection equipment. Moreover, the optical tracking system can be used to monitor skew or twist of the inspection equipment with respect to the normal rectilinear transducer orientation. The inspection equipment position information is then coupled to the inspection data to provide outputs equivalent to fully encoded multi-axis manipulator automated scans, but with less setup burden and equipment expense.

Abstract: This invention applies optical sensing technology with an ultrasound inspection system to associate encoded position data with the inspection data. The compact electronics of the optical system can be attached to the inspection assembly to allow fully encoded position information to be associated with the ultrasonic, eddy current, or other nondestructive examination data without substantially impacting the overall envelope of the NDE inspection equipment. Moreover, because of the small size, the optical system can be used in tandem to monitor skew or twist of the inspection equipment with respect to the normal rectilinear transducer orientation. The inspection equipment position information is then coupled to the inspection data to provide data outputs equivalent to fully encoded multi-axis manipulator automated scans, but with less setup burden and equipment expense.

Abstract: The invention relates to a method and an arrangement for avoiding stray currents in a wind power plant. There is an insulating power source having a galvanic decoupled secondary side, an electrical load coupled to the secondary side of the insulating power source through an electrical conductor and a stray current sensitive mechanical component of the wind power plant. The insulating power source is located at a first side of the stray current sensitive mechanical component and the load is located at a second side of the stray sensitive mechanical component. The electrical conductor is coupled to a common ground potential at the second side.

Abstract: A method is provided for operating a nuclear reactor. The method includes operating the nuclear reactor for an initial cycle during which a core contains initial nuclear fuel assemblies; then operating the nuclear reactor for transition cycles, at least some of the initial nuclear fuel assemblies being progressively replaced, during the replacement steps preceding the transition cycles, with transition nuclear fuel assemblies or with plutonium-equilibrium nuclear fuel assemblies; and then operating the nuclear reactor for at least one plutonium equilibrium cycle during which the core contains only plutonium-equilibrium nuclear fuel assemblies.

Abstract: A method of evaluating at least one quantity relating to the distortion of a nuclear fuel assembly, the method including the following steps: the nuclear fuel assembly is placed in a volume of water bounded by an upper free surface; a camera is placed outside the volume of water, above the free surface; at least one image of at least one lateral face of the nuclear fuel assembly is taken; the at least one image is analyzed graphically and the at least one quantity relating to the distortion of the nuclear fuel assembly is deduced therefrom.

Abstract: A boiling water reactor assembly includes a bayonet plate closure between a control rod guide tube and a drive housing pipe. The bayonet plate closure has a bayonet plate constructed in two parts including a central bayonet ring mounted rotatably about its longitudinal axis and an outer ring completely surrounding the bayonet ring. The outer ring is mounted on the periphery of the bayonet ring and reaches inwards under the bayonet ring periphery. The ring is furthermore permanently supported in the axial direction on the drive housing pipe by spring pressure acting on the control rod guide tube, in order to produce a frictional connection. The spring pressure can be released unhindered from the reactor side by tools.

Abstract: Angular sectors of a cylindrical wall of a crucible for vitrification of waste, built in steel and subject to high temperatures, are coated with a mixture of mainly glass and ceramic, the coating being subject to a heat treatment comprising a step between 650° C. and 850° C. so as to perform surface melting of the mixture filling the open porosity, improving dielectric strength and the cohesion of the coating, but without producing any excessive thermal expansion or oxidation of the substrate which would lead to fast flaking of the coating.

Abstract: The method comprises the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, splitting the cubes into a first category and a second category, each cube of the first category being adjacent only to cubes from the second category so that the first category and second category of cubes constitute a checkerboard-like pattern, ordering the cubes of the first category and then the cubes of the second category, calculating neutron flux and/or thermohydraulics parameters by using an iterative solving procedure of at least one linear system and/or an eigensystem, the components of an iterant of the linear system and/or the eigensystem constituting the neutron flux and/or thermohydraulics parameters to be calculated, wherein, during the iterative solving procedure, calculations are conducted on the cubes of the first category then on the cubes of the second category.

Abstract: A method with which americium may be selectively recovered from a nitric aqueous phase containing americium, curium and fission products including lanthanides and yttrium, but which is free of uranium, plutonium and neptunium or which only contains these three last elements in trace amounts. The method is applicable for treatment and recycling of irradiated nuclear fuels, in particular for removing americium from raffinates stemming from methods for extracting and purifying uranium and plutonium such as the PUREX and COEX™ methods.

Abstract: A computer implemented method for modelizing a nuclear reactor core, including the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated. A control parameter is varied to impact a neutron eigenvalue ? through a perturbed interface current equation and drive the neutron eigenvalue ? towards 1.

Abstract: Combined cycle power plants and related methods are disclosed here. In the plants, a mediating thermal energy storage unit is used to store waste or residual thermal energy recovered from a heat engine employing a top thermodynamic cycle of the combined cycle power plant, so that the stored residual thermal energy may be used as an energy source in a bottom thermodynamic cycle of the power plant. In the combined cycle power plants described here, the heat engine employing a top cycle may comprise a Brayton cycle heat engine and the heat engine employing the bottom thermodynamic cycle may be a Rankine cycle heat engine.