Systems and methods position tools about a flooded nuclear reactor during maintenance outages without overhead support or alignment structures being necessary. systems may include annular clamps for support from a reactor steam dam, a telescoping mast, a motor or other drive to extend or retract the mast, and/or an articulator to hold the payload and move the same about any degree of freedom. The telescoping mast may include several nested sections joined to a drive motor. Several different articulators are useable, including those with separate gearings for rotation about perpendicular axes and self-leveling wrists to orient tools in confirmed positions. Systems can be locally or remotely powered and controlled through powered and communicative connections to move about any position in a reactor annulus or core.

Systems and methods position tools about a flooded nuclear reactor during maintenance outages without overhead support or alignment structures being necessary. systems may include annular clamps for support from a reactor steam dam, a telescoping mast, a motor or other drive to extend or retract the mast, and/or an articulator to hold the payload and move the same about any degree of freedom. The telescoping mast may include several nested sections joined to a drive motor. Several different articulators are useable, including those with separate gearings for rotation about perpendicular axes and self-leveling wrists to orient tools in confirmed positions. Systems can be locally or remotely powered and controlled through powered and communicative connections to move about any position in a reactor annulus or core.

Packaging structures and systems are used for handling components for use in a nuclear reactor. The packaging protects the component during transport and handling and then dissolves in liquid in the nuclear reactor or fuel pool. The packaging need not be removed, as so can block flow paths or otherwise interfere with operability were it not for its dissolution. The packaging may include shock absorbers in a fuel assembly or a seal on a water rod in the assembly. Mechanical, frictional, or chemical retaining materials may be used to secure the packaging and may also dissolve in the liquid. For a light water reactor, polymers, protein gels, and plastics can all be used where they will dissolve in the water and are otherwise compatible with reactor chemistry and neutronics. Materials with higher temperatures for solubility may be used because they will dissolve when reactor operations commence.

The present invention relates to a centering pin for a nuclear plant core, in a reactor vessel characterised in that it has a hydrodynamic profile (120, 130) on at least one of the front or downstream faces of the pin (110), so as to reduce instability when coolant fluid is circulating around the pin (110).

The present invention relates to a centering pin for a nuclear plant core, in a reactor vessel characterised in that it has a hydrodynamic profile (120, 130) on at least one of the front or downstream faces of the pin (110), so as to reduce instability when coolant fluid is circulating around the pin (110).

A system for refueling a nuclear reactor is provided. The system includes a lower reactor vessel with a plurality of fuel rods and a plurality of control rods disposed therein, the lower reactor vessel further comprising an upper flange. An upper reactor vessel is provided which encloses a steam generator and a pressurizer, the upper reactor vessel further comprising a lower flange that matingly engages the upper flange of the lower reactor vessel. A transporter surrounds an outer surface of the upper reactor vessel, wherein the transporter is configured to translate the upper reactor vessel vertically toward and away from the lower reactor vessel and also to translate the upper reactor vessel horizontally toward or away from alignment with the lower reactor vessel.

A system for refueling a nuclear reactor is provided. The system includes a lower reactor vessel with a plurality of fuel rods and a plurality of control rods disposed therein, the lower reactor vessel further comprising an upper flange. An upper reactor vessel is provided which encloses a steam generator and a pressurizer, the upper reactor vessel further comprising a lower flange that matingly engages the upper flange of the lower reactor vessel. A transporter surrounds an outer surface of the upper reactor vessel, wherein the transporter is configured to translate the upper reactor vessel vertically toward and away from the lower reactor vessel and also to translate the upper reactor vessel horizontally toward or away from alignment with the lower reactor vessel.

A system for refueling a nuclear reactor is provided. The system includes a lower reactor vessel with a plurality of fuel rods and a plurality of control rods disposed therein, the lower reactor vessel further comprising an upper flange. An upper reactor vessel is provided which encloses a steam generator and a pressurizer, the upper reactor vessel further comprising a lower flange that matingly engages the upper flange of the lower reactor vessel. A transporter surrounds an outer surface of the upper reactor vessel, wherein the transporter is configured to translate the upper reactor vessel vertically toward and away from the lower reactor vessel and also to translate the upper reactor vessel horizontally toward or away from alignment with the lower reactor vessel.

Systems and methods for providing and using molten salt reactors are described. While the systems can include any suitable component, in some cases, they include a graphite reactor core defining an internal space that houses one or more fuel wedges, where each wedge defines one or more fuel channels that extend from a first end to a second end of the wedge. In some cases, one or more of the fuel wedges comprise multiple wedge sections that are coupled together end to end and/or in any other suitable manner. In some cases, one or more alignment pins also extend between two sections of a fuel wedge to align the sections. In some cases, one or more seals are also disposed between two sections of a fuel wedge. Thus, in some cases, the reactor core can be relatively long (e.g., to be a pipeline reactor). Other implementations are also described.

Systems and methods for providing and using molten salt reactors are described. While the systems can include any suitable component, in some cases, they include a graphite reactor core defining an internal space that houses one or more fuel wedges, where each wedge defines one or more fuel channels that extend from a first end to a second end of the wedge. In some cases, one or more of the fuel wedges comprise multiple wedge sections that are coupled together end to end and/or in any other suitable manner. In some cases, one or more alignment pins also extend between two sections of a fuel wedge to align the sections. In some cases, one or more seals are also disposed between two sections of a fuel wedge. Thus, in some cases, the reactor core can be relatively long (e.g., to be a pipeline reactor). Other implementations are also described.