A method of repairing a divertor or first wall surface in a tokamak plasma vessel. The divertor or first wall surface comprises a refractory metal having a melting point of at least 2000 C. A pressure of less than 25 mbar is maintained within the plasma vessel following the end of operation of the plasma vessel. The refractory metal is deposited onto the divertor or first wall surface within the plasma vessel via a deposition process which is one of: additive manufacturing; physical vapour deposition; thermal spray; arc ion plating; diode laser cladding; and chemical vapour deposition.

A method of repairing a divertor or first wall surface in a tokamak plasma vessel. The divertor or first wall surface comprises a refractory metal having a melting point of at least 2000 C. A pressure of less than 25 mbar is maintained within the plasma vessel following the end of operation of the plasma vessel. The refractory metal is deposited onto the divertor or first wall surface within the plasma vessel via a deposition process which is one of: additive manufacturing; physical vapour deposition; thermal spray; arc ion plating; diode laser cladding; and chemical vapour deposition.

A controlled fusion process is provided that can produce a sustained series of fusion reactions: a process that (i) uses a substantially higher reactant density of the deuterium and tritium gases by converging cationic reactants into the higher reaction density at a target cathode rather than relying on random collisions, the converging producing a substantially higher rate of fusion and energy production; (ii) uses a substantially lower input of energy to initiate the fusion; (iii) can be cycled at a substantially higher cycle frequency; (iv) has a practical heat exchange method; (v) is substantially less costly to manufacture, operate, and maintain; and, (vi) has a substantially improved reaction efficiency as a result of not mixing reactants with products.

Techniques are described for automatically removing and replacing components, including a vacuum vessel, from a tokamak. The inventors have recognized that schemes for automatically removing and replacing components from a tokamak should preferably be simple (e.g., using proven equipment to perform a series of non-mechanically complex tasks) and have a very low risk of damaging components. Techniques described herein may include splitting a tokamak into multiple pieces, separating the pieces, and removing the now separate pieces of the vacuum vessel from within the pieces of the tokamak. A new vacuum vessel can be inserted in multiple pieces and the tokamak rejoined to complete the replacement process.

Techniques are described for automatically removing and replacing components, including a vacuum vessel, from a tokamak. The inventors have recognized that schemes for automatically removing and replacing components from a tokamak should preferably be simple (e.g., using proven equipment to perform a series of non-mechanically complex tasks) and have a very low risk of damaging components. Techniques described herein may include splitting a tokamak into multiple pieces, separating the pieces, and removing the now separate pieces of the vacuum vessel from within the pieces of the tokamak. A new vacuum vessel can be inserted in multiple pieces and the tokamak rejoined to complete the replacement process.

Techniques are described for automatically removing and replacing components, including a vacuum vessel, from a tokamak. The inventors have recognized that schemes for automatically removing and replacing components from a tokamak should preferably be simple (e.g., using proven equipment to perform a series of non-mechanically complex tasks) and have a very low risk of damaging components. Techniques described herein may include splitting a tokamak into multiple pieces, separating the pieces, and removing the now separate pieces of the vacuum vessel from within the pieces of the tokamak. A new vacuum vessel can be inserted in multiple pieces and the tokamak rejoined to complete the replacement process.

Techniques are described for automatically removing and replacing components, including a vacuum vessel, from a tokamak. The inventors have recognized that schemes for automatically removing and replacing components from a tokamak should preferably be simple (e.g., using proven equipment to perform a series of non-mechanically complex tasks) and have a very low risk of damaging components. Techniques described herein may include splitting a tokamak into multiple pieces, separating the pieces, and removing the now separate pieces of the vacuum vessel from within the pieces of the tokamak. A new vacuum vessel can be inserted in multiple pieces and the tokamak rejoined to complete the replacement process.

An assembly method for a silicon cooling arm that connects a cool source to an aluminum sleeve of a cryogenic target includes a bulb of a strut (2) preset in an arc-shaped groove (5-3) of a rotary table (5). Additionally, a first section (3-1) of a connecting shaft (3) is inserted into a center insertion hole (5-2) of the rotary table (5). A second section of the connecting shaft (3) is attached to an upper surface of a disk body (5-1). A coaxial connector (4) and a strut stop (1) are sheathed on the connecting shaft (3). A recessing (2-2) of the strut (2) is fitted onto a boss (1-2) of the groove in the strut stop (1). Finally, a fifth section (3-5) of the connecting shaft (3) is inserted into a hollow part in a hollow disk body (1-1) of the strut stop (1).

An assembly method for a silicon cooling arm that connects a cool source to an aluminum sleeve of a cryogenic target includes a bulb of a strut (2) preset in an arc-shaped groove (5-3) of a rotary table (5). Additionally, a first section (3-1) of a connecting shaft (3) is inserted into a center insertion hole (5-2) of the rotary table (5). A second section of the connecting shaft (3) is attached to an upper surface of a disk body (5-1). A coaxial connector (4) and a strut stop (1) are sheathed on the connecting shaft (3). A recessing (2-2) of the strut (2) is fitted onto a boss (1-2) of the groove in the strut stop (1). Finally, a fifth section (3-5) of the connecting shaft (3) is inserted into a hollow part in a hollow disk body (1-1) of the strut stop (1).

An apparatus and method are disclosed for machine-replaceable plasma-facing tiles for fusion power reactor environments. The apparatus and method involve a tile that is fish scale shaped, and a tile support tube that is attached to the back portion of the tile. The tile support tube includes at least one coolant channel and at least one guard vacuum channel. In one or more embodiments, the method for removing the tile comprises providing a tile that is installed in a manifold channel of a first wall of a fusion power reactor, rotating the tile such that it is in an install/removal orientation, inserting two tines of a removal tool between the outer edges of the tile and the first wall of the fusion power reactor, rotating the removal tool such that the two tines grasp the tile support tube, and lifting the tile away from the wall with the removal tool.