Patent classifications
F22B37/007
METHOD OF DISASSEMBLING STEAM GENERATOR
A method of disassembling a steam generator including a body portion, a water chamber, a tube plate and a plurality of heat transfer tubes, the method includes: a step of obtaining a disassembly target including the tube plate and a part of the heat transfer tubes; a step of specifying the heat transfer tube fixed to the tube plate; a step of releasing fixation between the part of the heat transfer tube and the tube plate; and a step of pulling out the part of the heat transfer tube from the through-hole, in the step of releasing the fixation, the TIG heating head is inserted from the primary region side, and in the step of releasing the fixation, the TIG heating head is moved to a plurality of streaks only in a direction from the primary region side to the secondary region side.
Method for heat treating a metal tube or pipe, metal tube or pipe, and heat treatment furnace
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.
SYSTEM AND METHOD FOR DECOMISSIONING A STEAM GENERATOR
A system for decommissioning a steam generator, comprising a structure defining a chamber for receiving the steam generator; and a mechanical assembly within the chamber for dismantling the steam generator.
Method of disassembling steam generator
A method of disassembling a steam generator including a body portion, a water chamber, a tube plate and a plurality of heat transfer tubes, the method includes: a step of obtaining a disassembly target including the tube plate and a part of the heat transfer tubes; a step of specifying the heat transfer tube fixed to the tube plate; a step of releasing fixation between the part of the heat transfer tube and the tube plate; and a step of pulling out the part of the heat transfer tube from the through-hole, in the step of releasing the fixation, the TIG heating head is inserted from the primary region side, and in the step of releasing the fixation, the TIG heating head is moved to a plurality of streaks only in a direction from the primary region side to the secondary region side.
SYSTEMS AND METHODS FOR STEAM SEPARATOR TIE BAR REPAIR OR REPLACEMENT
Systems enhance stand pipe alignment and security with braces docking to the stand pipes. A link connects pairs of braces so the braces and stand pipes docked thereby cannot move relative to each other when fully secured. Partially securing braces allows adjustment of the braces and distance between the same and thus stand pipe position. Fully securing the braces makes the entire system rigid without need for a tie bar. Braces and links can be installed and secured to the stand pipes and among each other at an axial position from above the stand pipes, so that overhead, simple tooling may be used. A crimp nut or other resilient connector may be used to secure the systems from that single dimension with simple tooling. Any number of braces, joining to any number of other braces, may be used in the system, and several systems may be used at various levels.
Modular transportable nuclear generator
The present invention relates generally to electric power and process heat generation using a modular, compact, transportable, hardened nuclear generator rapidly deployable and retrievable, comprising power conversion and electric generation equipment fully integrated within a single pressure vessel housing a nuclear core. The resulting transportable nuclear generator does not require costly site-preparation, and can be transported fully operational. The transportable nuclear generator requires an emergency evacuation area substantially reduced with respect to other nuclear generators as it may be configured for operation with a melt-proof conductive ceramic core which allows decay heat removal even under total loss of coolant scenarios.
Systems and methods for steam separator tie bar repair or replacement
Systems enhance stand pipe alignment and security with braces docking to the stand pipes. A link connects pairs of braces so the braces and stand pipes docked thereby cannot move relative to each other when fully secured. Partially securing braces allows adjustment of the braces and distance between the same and thus stand pipe position. Fully securing the braces makes the entire system rigid without need for a tie bar. Braces and links can be installed and secured to the stand pipes and among each other at an axial position from above the stand pipes, so that overhead, simple tooling may be used. A crimp nut or other resilient connector may be used to secure the systems from that single dimension with simple tooling. Any number of braces, joining to any number of other braces, may be used in the system, and several systems may be used at various levels.