Abstract:
The present invention relates to an integrated nuclear reactor system including a double containment structure using liquid nitrogen, the nuclear reactor system comprising: a reactor vessel; a reactor core disposed in the reactor vessel; a steam generator disposed in the reactor vessel and located above the reactor core; a first containment vessel surrounding the reactor vessel with a first space interposed therebetween; a second containment vessel surrounding the first containment vessel with a second space interposed therebetween; and a liquid nitrogen supply unit supplying liquid nitrogen into the second space.
Abstract:
A method for the innercontour passivation of steel surfaces of a nuclear reactor consists in filling a first contour of a nuclear reactor with a liquid metal coolant, introducing a reagent into the liquid metal coolant, said reagent interacting with the material of elements of the first contour, forming a protective film, and heating the liquid metal coolant, having the reagent introduced therein, to a temperature allowing for conditions for forming the protective film. The liquid metal coolant having the reagent introduced therein is kept at said temperature until a continuous protective film is formed on the surface of the material of the elements of the first contour. The liquid metal coolant having reagent introduced therein is heated by means of the friction thereof against rotating vanes of a vane pump, which is submerged in the liquid metal coolant. The present invention thus provides for a simpler passivation process, a more reliable passivation mode, an increase in the safety thereof and a simpler control over the process of passivation of steel surfaces.
Abstract:
The vessel (1) comprises a side wall (2) and an end wall (3), and is characterized in that: a) said end wall (3) is a domed end wall (3'); b) said domed end wall (3') of thickness EI comprises: b1) a layer (4) called the inner layer C1 providing corrosion resistance and b2) a layer (5) called the outer layer CE of thickness EE at least equal to the thickness EI of said inner layer CI (4); c) said inner CI (4) and outer CE (5) layers are rigidly joined by a so-called first assembly means (30); and d) said inner layer CI (4) is formed from a multilayer material comprising an internal layer CIC (40) for providing corrosion resistance and what is called an external layer CIS (41), said internal CIC (40) and external CIS (41) layers being rigidly joined by a so-called second assembly means (42). Advantages: possibility of manufacturing large vessels inexpensively.
Abstract:
Apparatus (18) suitable for annealing the interior walls of a nuclear reactor (2) which comprises a nuclear reactor shell (4), a cap (6) securely attached to the nuclear reactor shell (4), wherein the cap (6) has an inlet line (8) for the introduction of a hot gas under high pressure and an outlet line (10) for removing low pressure gas from the interior of the apparatus (18), means, such as a cylindrical shell (12,14), that helps define an annular space (16) adjacent to the vertical walls of the reactor through which gas can flow and means for directing low pressure gas to the outlet line.
Abstract:
A system for annealing a vessel (14) in situ by heating the vessel (14) to a defined temperature, composed of: an electrically operated heater assembly (10) insertable into the vessel (14) for heating the vessel (14) to the defined temperature; temperature monitoring components positioned relative to the heater assembly (10) for monitoring the temperature of the vessel (14); a controllable electric power supply unit for supplying electric power required by the heater assembly (10); a control unit for controlling the power supplied by the power supply unit; a first vehicle (2) containing the power supply unit; a second vehicle (4) containing the control unit; power conductors (22) connectable between the power supply unit and the heater unit (10) for delivering the power supplied by the power supply unit to the heater assembly (10); signal conductors (20,24) connectable between the temperature monitoring components and the control unit for delivering temperature indicating signals from the temperature monitoring components to the control unit; and control conductors (8) connectable between the control unit and the power supply unit for delivering to the power supply unit control signals for controlling the level of power supplied by the power supply unit to the heater assembly (10). At least one of the vehicles is constructed to support comparatively heavy loads while being capable of being loaded and unloaded from essentially any location along either side of the vehicle. At least one vehicle is provided with a capable connecting unit which provides a stress-relief support for at least one set of cables. The system further includes apparatus for maintaining the interior of the vessel at subatmospheric pressure during annealing.
Abstract:
The invention relates to a method for reducing the corrosion of a component in a water-guiding conduction system of a nuclear facility. A protective layer is produced according to a sol-gel method. Before, water moistening the component is removed from the conduction system and the component is optionally dried in a separate step. After the sol-gel method has been carried out, the conduction system is again filled with water. A liquid sol film that is produced on the component is dried, especially by means of hot air. A component in the primary system of a boiling water reactor can especially be coated with a highly corrosion-resistant zirconium oxide protective layer according to said sol-gel method.
Abstract:
The invention relates to a method for reducing the corrosion of a component in a water-guiding conduction system of a nuclear facility. A protective layer is produced according to a sol-gel method. Before, water moistening the component is removed from the conduction system and the component is optionally dried in a separate step. After the sol-gel method has been carried out, the conduction system is again filled with water. A liquid sol film that is produced on the component is dried, especially by means of hot air. A component in the primary system of a boiling water reactor can especially be coated with a highly corrosion-resistant zirconium oxide protective layer according to said sol-gel method.
Abstract:
An austenitic stainless steel with the resistance to deterioration by neutron irradiation, which is obtained by subjecting a stainless steel comprising up to 0.08 wt.% carbon, up to 2.0 wt.% manganese, up to 1.5 wt.% silicon, up to 0.045 wt.% phosphorus, up to 0.030 wt.% sulfur, 8.0-22.0 wt.% nickel, 16.0-26.0 wt.% chromium, and iron substantially as the remainder to solution treatment at 1,000 to 1,180 DEG C and then to aging at 600 to 750 DEG C .