In a WJP execution method for a reactor vessel lid, WJP is executed on the inner surface of the reactor vessel lid in a state in which an underwater environment is formed on the inner surface of the reactor vessel lid and an aerial environment is formed on the outer surface thereof. In addition, the reactor vessel lid with a waterproof jig attached thereto is arranged in water, the waterproof jig having a cylindrical shape extending to the side of the outer surface of the reactor vessel lid and constituting a vessel with the reactor vessel lid as the bottom portion thereof. Moreover, the reactor vessel lid is arranged on a base installed in the water.

In a WJP execution method for a reactor vessel lid, WJP is executed on the inner surface of the reactor vessel lid in a state in which an underwater environment is formed on the inner surface of the reactor vessel lid and an aerial environment is formed on the outer surface thereof. In addition, the reactor vessel lid with a waterproof jig attached thereto is arranged in water, the waterproof jig having a cylindrical shape extending to the side of the outer surface of the reactor vessel lid and constituting a vessel with the reactor vessel lid as the bottom portion thereof. Moreover, the reactor vessel lid is arranged on a base installed in the water.

A safety system for a nuclear reactor includes a first containment structure and a second containment structure. The double containment configuration is designed and configured to meet all design basis accidents and beyond design basis events with independent redundancy. The remaining systems that control reactivity, decay heat removal, and fission product retention may be categorized and designed as business systems, structures, and components, and can therefore be designed and licensed according to an appropriate quality grade for business systems.

A method for heat treating a metal tube or pipe is provided to perform heat treatment in such a manner that metal tubes or pipes (1) to be accommodated in a heat treatment furnace are laid down on a plurality of cross beams (22) arranged along a longitudinal direction of the metal tubes or pipes with the distance between adjacent cross beams being in a range of 200 to 2500 mm. This makes it possible to inhibit bending and scratches of the metal tubes or pipes without causing discoloration and deterioration of the manufacturing efficiency for the metal tubes or pipes. When the metal tubes or pipes (1) are laid down on the cross beams (22), spacers may be interposed between the metal tubes or pipes (1) and the cross beams (22) on which they are laid down.

A device may determine a lead vehicle identifier and a follow vehicle identifier associated with navigating to a destination. The device may determine a plurality of device identifiers associated with the lead vehicle identifier or the follow vehicle identifier, identifying a plurality of devices. The device may determine navigation information. The device may provide the navigation information to a navigation device associated with a vehicle identifier. The device may receive a request to modify the navigation information. The device may determine a modification option. The device may provide the modification option to the plurality of devices for voting. The device may receive one or more voting responses. The device may determine a result of the voting based on the one or more voting responses. The device may provide, to the navigation device, an instruction associated with navigating to the destination based on the result of the voting.

For autonomous data evacuation, a compartment is motivated by a propulsion device. A navigation module guides the compartment to a disaster recovery target using the propulsion device in response to an evacuation signal. At least a portion of the navigation module comprises one or more of hardware and executable code, the executable code stored on one or more computer readable storage media.

An electric melting method for forming a cylinder of a pressure vessel of nuclear power station, in which an electric melting head and a base material are connected to the anode and cathode of a power supply respectively. During the forming of a metal component, the raw metal wire is sent to a surface of the base material by a feeder and the electric melting head to create the electric arc between the raw wire and the base material, wherein the electric arc melts certain of deposited auxiliary material and crates a molten slag pool; a current creates the resistance heat and the electroslag heat; the raw wire is molten under the high-energy heat resource composed of the electric arc heat, the resistance heat and the electroslag heat, and creates a molten pool on partial surface of the base material.

An electric melting method for forming a cylinder of a pressure vessel of nuclear power station, in which an electric melting head and a base material are connected to the anode and cathode of a power supply respectively. During the forming of a metal component, the raw metal wire is sent to a surface of the base material by a feeder and the electric melting head to create the electric arc between the raw wire and the base material, wherein the electric arc melts certain of deposited auxiliary material and crates a molten slag pool; a current creates the resistance heat and the electroslag heat; the raw wire is molten under the high-energy heat resource composed of the electric arc heat, the resistance heat and the electroslag heat, and creates a molten pool on partial surface of the base material.

A method for converting uranium hexafluoride to uranium dioxide includes steps of hydrolysis of UF.sub.6 to uranium oxyfluoride (UO.sub.2F.sub.2) in a hydrolysis reactor (4) by reaction between gaseous UF.sub.6 and dry water vapour injected into the reactor (4), and pyrohydrolysis of UO.sub.2F.sub.2 to UO.sub.2 in a pyrohydrolysis furnace (6) by reaction of UO.sub.2F.sub.2 with dry water vapour and hydrogen gas (H.sub.2) injected into the furnace (6). The hourly mass flowrate of gaseous UF.sub.6 supplied to the reactor (4) is between 75 and 130 kg/h, the hourly mass flowrate of dry water vapour supplied to the reactor (4) for hydrolysis is between 15 and 30 kg/h, and the temperature inside the reactor (4) is between 150 and 250° C.

A transportable nuclear power generator assembly includes a first modular nuclear power generator unit and a second nuclear power generator unit. The first modular nuclear power generator unit includes a first transport container, a first nuclear power module positioned inside the first transport container, and a first supporting mechanism movably supports the first nuclear power module inside the first transport container. The second modular nuclear power generator unit includes a second transport container, a second nuclear power module positioned inside the second transport container, and a second supporting mechanism configured to support the second nuclear power module inside the second transport container. At least one of the first supporting mechanism and the second supporting mechanism is configured to move at least one of the first nuclear power module and the second nuclear power module relative to one another to result in an at least critical state or a subcritical state.