Abstract:
A nuclear power installation with a nuclear reactor tank (10) that is surrounded by an insulated shell (20), forming an intermediate space (22), whereby a flow path (34) for steam is arranged inside the insulated shell (20). The flow path (34) is released exclusively in an unauthorized operating state, allowing steam to be removed from the intermediate space (22). Release occurs, for instance, when the reactor tank (10) floods outwards. Preferably, the flow path (34) is embodied as a U-shaped duct (36) that is connected to a flood basin (28) by means of a compensation line (38) and is partially filled with coolant (F) in order to partially close the flow path (34).
Abstract:
Sealing device (2) for a device for measuring the fill level (4) in a fluid container, particularly in a pressure vessel (6) of a nuclear facility, comprising at least one thermal element (8) which is connected to the pressure vessel (6) by means of a pressure pipe (10) and to an evaluation unit (14) by means of a pipeline (12) connected to the pressure pipe (10), wherein the pressure pipe (10) and the pipeline (12) are connected to each other by means of a threaded pipe connection (16) comprising a center part (31) having two threaded sections (20, 22), wherein one threaded section (20) is connected to a pipe sleeve (26) by means of a screw connection (34), and the other threaded section (22) is connected to the pressure pipe (10) by means of a further screw connection (36).
Abstract:
The invention concerns a guide tube (3) comprising a cylindrical body (3a) passing through the cover and a head (3b) provided with an external thread (3c). The device comprises a housing (20) adaptable on the head (3b) of the guide tube (3) and provided with means (24) sealing it with said head (3b), and clamping means (40) independent of the housing (20) and exerting a force pressing the housing on the guide tube (3) head.
Abstract:
A permanent annular ring seal and refueling deck assembly providing an effective water barrier over the annular space between a nuclear reactor vessel flange and a surrounding annular ledge includes annular platform, a support and a joint seal. The joint seal has an upper cylindrical section and a lower flexible coil or arcuate shaped section which provides for greater accommodation of vessel radial, axial and rotational movements, and reduces joint stress.
Abstract:
In one implementation, a passive core decay heat transport system comprising of a device in the reactor core and an assembly of heat dissipating fins is disclosed. The device comprises at least one coolant channel 2 containing the fuel assembly 3; at least one collect joint 4 5 connecting the fuel in the assembly to shield plug 6; at least one liquid metal thermo-siphon 5 for transporting of decay heat from fuel; at least one other liquid metal thermo-siphon 7 for transport of heat from thermo-siphon 5; and at least an assembly of heat dissipating fins 10 for transport of heat from thermo-siphon 7 to ultimate sink. The thermal expansion of the liquid metal by melting establishes the conductive and convective heat transfer paths and 10 transfers the heat from the fuel assembly 3 to the thermo-siphon 5, which transports the heat to other thermo-siphon 7 and then to the assembly of fin 10, which dissipates the heat by natural circulation of air to atmospheric air.
Abstract:
Colmatage de fissure dans une piscine d'installation nucléaire, utilisant un robot L'invention concerne le colmatage notamment de fissure dans une paroi de piscine d'une installation nucléaire. En particulier, l'invention met en ouvre un robot mobile portant un dévideur (DIS) de ruban adhésif. On prévoit alors au moins : - une commande d'une pluralité de systèmes d'aspiration (V11-V14; V21-V24), le dévideur étant solidaire mécaniquement d'un premier système d'aspiration (V21-V24), et - une étape de commande de déplacement du premier système (V21-V24) par rapport aux autres systèmes (V11-V14) de ladite pluralité de systèmes
Abstract:
A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.
Abstract:
A method for assembling and installing a steel containment vessel for a nuclear power station comprising a lower head (1), an N-ring section (2), and a upper head (3). The assembling of the three components comprises joining and welding, and the installation comprises transportation, lifting, and installation in position. The assembling sequence, welding sequence, measurement method, transportation and lifting mode, and installation precision are controlled during the assembling. The mothod of assembling each components independently in sequence,then transporting, lifting, and installing in position in sequence allows the concurrent construction of the project, and greatly reduces the construction period.
Abstract:
A multi-layered cladding material including a ceramic matrix composite and a metallic material, and a tube formed from the cladding material. The metallic material forms an inner liner of the tube and enables hermetic sealing of thereof. The metallic material at ends of the tube may be exposed and have an increased thickness enabling end cap welding. The metallic material may, optionally, be formed to infiltrate voids in the ceramic matrix composite, the ceramic matrix composite encapsulated by the metallic material. The ceramic matrix composite includes a fiber reinforcement and provides increased mechanical strength, stiffness, thermal shock resistance and high temperature load capacity to the metallic material of the inner liner. The tube may be used as a containment vessel for nuclear fuel used in a nuclear power plant or other reactor. Methods for forming the tube comprising the ceramic matrix composite and the metallic material are also disclosed.