G21B1/13

First wall conditioning in a fusion reactor vessel

An apparatus for protecting an interior surface of a fusion reactor vessel. The apparatus comprises a power supply operably connected to an electrode for insertion into the vessel. The apparatus supports a solid material within the vessel, and is configured such that power supplied to the electrode within the vessel causes a plasma located in proximity to the solid material to sputter the solid material in order to deposit a protective material on said interior surface.

First wall conditioning in a fusion reactor vessel

An apparatus for protecting an interior surface of a fusion reactor vessel. The apparatus comprises a power supply operably connected to an electrode for insertion into the vessel. The apparatus supports a solid material within the vessel, and is configured such that power supplied to the electrode within the vessel causes a plasma located in proximity to the solid material to sputter the solid material in order to deposit a protective material on said interior surface.

Composite for heat transfer with high-temperature resistance

Composite for the transfer of the heat between the hot and cooled surface, whereby the composite is resistant to high temperatures, includes at least two components, one of the components is produced by longitudinal segments (1) with the melting temperature that is higher than 1300 C. and which are separated from each other by the filling (2) with the higher heat conductivity and thermal expansivity, which is in the direct contact with the cooling medium in the channel (3). Both components are in the direct contact with the hot environment surrounding the composite, whereby the overall surface formed by the segments (1) is 50 to 95% of the overall hot surface of the composite. The longitudinal axis of the segment (1) is primarily oriented in the direction of the shortest line connecting the hot surface with the cooled surface of the composite with the allowed deviation of 45 at maximum, whereby in the direction from the hot to the cooled surface it can cross one boundary between the components at maximum. The material for the segments can be tungsten, preferably tungsten with the admixtures of oxides La.sub.2O.sub.3 and/or Y.sub.2O.sub.3 and/or CeO.sub.2 and/or ThO.sub.2 and/or ZrO.sub.2. The matrix, that is, the filling (2) can be copper or silver or their alloys.

Composite for heat transfer with high-temperature resistance

Composite for the transfer of the heat between the hot and cooled surface, whereby the composite is resistant to high temperatures, includes at least two components, one of the components is produced by longitudinal segments (1) with the melting temperature that is higher than 1300 C. and which are separated from each other by the filling (2) with the higher heat conductivity and thermal expansivity, which is in the direct contact with the cooling medium in the channel (3). Both components are in the direct contact with the hot environment surrounding the composite, whereby the overall surface formed by the segments (1) is 50 to 95% of the overall hot surface of the composite. The longitudinal axis of the segment (1) is primarily oriented in the direction of the shortest line connecting the hot surface with the cooled surface of the composite with the allowed deviation of 45 at maximum, whereby in the direction from the hot to the cooled surface it can cross one boundary between the components at maximum. The material for the segments can be tungsten, preferably tungsten with the admixtures of oxides La.sub.2O.sub.3 and/or Y.sub.2O.sub.3 and/or CeO.sub.2 and/or ThO.sub.2 and/or ZrO.sub.2. The matrix, that is, the filling (2) can be copper or silver or their alloys.

Complex shape structure for liquid lithium first walls of fusion power reactor environments
10734120 · 2020-08-04 · ·

A method, system, and apparatus are disclosed for a complex shape structure for liquid lithium first walls of fusion power reactor environments. In particular, the method involves installing at least one tile on the surface area of the internal walls of the reactor chamber. The tile(s) is manufactured from a high-temperature resistant, porous open-cell material. The method further involves flowing liquid lithium into the tile(s). Further, the method involves circulating the liquid lithium throughout the interior network of the tile(s) to allow for the liquid lithium to reach the external surface of the tile(s) that faces the interior of the reactor chamber. In addition, the method involves outputting the circulated liquid lithium from the tile(s). In one or more embodiments, the reactor chamber is employed in a fusion reactor. In some embodiments, the tile is manufactured from a ceramic material or a metallic foam.

Complex shape structure for liquid lithium first walls of fusion power reactor environments
10734120 · 2020-08-04 · ·

A method, system, and apparatus are disclosed for a complex shape structure for liquid lithium first walls of fusion power reactor environments. In particular, the method involves installing at least one tile on the surface area of the internal walls of the reactor chamber. The tile(s) is manufactured from a high-temperature resistant, porous open-cell material. The method further involves flowing liquid lithium into the tile(s). Further, the method involves circulating the liquid lithium throughout the interior network of the tile(s) to allow for the liquid lithium to reach the external surface of the tile(s) that faces the interior of the reactor chamber. In addition, the method involves outputting the circulated liquid lithium from the tile(s). In one or more embodiments, the reactor chamber is employed in a fusion reactor. In some embodiments, the tile is manufactured from a ceramic material or a metallic foam.

Electrical connection of elements inside the chamber of a nuclear fusion reactor to the reactor vessel

The invention relates to the field of thermonuclear fusion and can be used in devices for electrically connecting internal elements of the reactor chamber to the vacuum vessel of the nuclear fusion reactor. The present device for electrically connecting elements inside the chamber of a reactor to the vacuum vessel of the nuclear fusion reactor comprises lamellar electrically conductive elements with surface portions oriented in different directions, said elements being stacked between flanges. The device is made as an integral unit, where profiled slots are formed with connecting walls therebetween. The connecting walls constitute the electrically conductive elements and have profiled sections of an increased thickness between the differently oriented surface portions at transition areas to the flanges provided at the end parts of the integral unit. The technical effect of the present invention is an increase in the cyclic strength of the electrically conductive elements at the transition areas between the elements and the flanges and between the differently oriented surface portions (at bends) of the elements. The invention also provides that the electrically conductive elements have similar technical characteristics.

Electrical connection of elements inside the chamber of a nuclear fusion reactor to the reactor vessel

The invention relates to the field of thermonuclear fusion and can be used in devices for electrically connecting internal elements of the reactor chamber to the vacuum vessel of the nuclear fusion reactor. The present device for electrically connecting elements inside the chamber of a reactor to the vacuum vessel of the nuclear fusion reactor comprises lamellar electrically conductive elements with surface portions oriented in different directions, said elements being stacked between flanges. The device is made as an integral unit, where profiled slots are formed with connecting walls therebetween. The connecting walls constitute the electrically conductive elements and have profiled sections of an increased thickness between the differently oriented surface portions at transition areas to the flanges provided at the end parts of the integral unit. The technical effect of the present invention is an increase in the cyclic strength of the electrically conductive elements at the transition areas between the elements and the flanges and between the differently oriented surface portions (at bends) of the elements. The invention also provides that the electrically conductive elements have similar technical characteristics.

Shielding materials for fusion reactors
20200176132 · 2020-06-04 ·

There is described neutron shielding for a nuclear fusion reactor. The neutron shielding includes a cemented carbide or boride comprising a binder and an aggregate, the aggregate comprising particles of a carbide or boride compound.

Shielding materials for fusion reactors
20200176132 · 2020-06-04 ·

There is described neutron shielding for a nuclear fusion reactor. The neutron shielding includes a cemented carbide or boride comprising a binder and an aggregate, the aggregate comprising particles of a carbide or boride compound.