The present disclosure provides an integrated head package for a nuclear power generation system, the integrated head package comprising a closure head, and a control rod drive mechanism housed within a shroud. The control rod drive mechanism comprises at least one drive rod extending through the closure head and having a coupling element for releasably coupling to a control rod assembly within a reactor core. The at least one drive rod is movable to a maintenance/refuelling position in which the at least one drive rod is uncoupled from the control rod assembly and at least partially retracted into the integrated head package. The integrated head package further comprises at least one engagement feature for securing the at least one drive rod in the maintenance/refuelling position.

The present disclosure provides an integrated head package for a nuclear power generation system, the integrated head package comprising a closure head, and a control rod drive mechanism housed within a shroud. The control rod drive mechanism comprises at least one drive rod extending through the closure head and having a coupling element for releasably coupling to a control rod assembly within a reactor core. The at least one drive rod is movable to a maintenance/refuelling position in which the at least one drive rod is uncoupled from the control rod assembly and at least partially retracted into the integrated head package. The integrated head package further comprises at least one engagement feature for securing the at least one drive rod in the maintenance/refuelling position.

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 stand for hosting a Multiple Stud Tensioning Machine (MSTM) for tensioning working studs, the stand comprising a first assembly designed to lie on a floor, and a second assembly designed to receive the MSTM and movable in translation with respect to the first assembly thanks to a translation system.

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 method for heating primary coolant in a nuclear reactor system during system start-up. A primary coolant loop fluidly couples together a reactor vessel and a steam generating vessel. The primary coolant loop is filled with primary coolant. A portion of the primary coolant is taken from the primary coolant loop and placed into a start-up sub-system. The portion is heated while in the sub-system to form a heated portion of the primary coolant. The heated portion is returned into the primary coolant loop. The method allows for the primary coolant to be heated to a no-load operating temperature.

In some embodiments, a nuclear reactor vessel comprises a containment vessel for a reactor pressure vessel (RPV); a control rod drive mechanism (CRDM) located in the containment vessel, the CRDM including drive motors configured to move control rods into and out of a nuclear reactor core located in the RPV; and a partition extending across a portion of the containment vessel configured to retain the drive motors in a separate fluid-tight barrier region within the containment vessel. Other embodiments may be disclosed and/or claimed.

Embodiments described in this specification are generally directed to a bolted hinge assembly for a waterbox cover (a waterbox hinge assembly). The waterbox hinge assembly generally does not require welding on the waterbox cover or the heat exchanger in an HVAC system (HVAC unit hereinafter). Further, the waterbox hinge assembly may be installable to the HVAC unit without removing the heat exchange fluids (e.g., water, refrigerant, etc.) from the HVAC unit. In some embodiments, the waterbox hinge assembly can be installed on an HVAC unit without removing any bolts from the waterbox cover. Once installed, the waterbox hinge assembly can be left in place so that it can be reused anytime the HVAC unit is serviced.

Embodiments described in this specification are generally directed to a bolted hinge assembly for a waterbox cover (a waterbox hinge assembly). The waterbox hinge assembly generally does not require welding on the waterbox cover or the heat exchanger in an HVAC system (HVAC unit hereinafter). Further, the waterbox hinge assembly may be installable to the HVAC unit without removing the heat exchange fluids (e.g., water, refrigerant, etc.) from the HVAC unit. In some embodiments, the waterbox hinge assembly can be installed on an HVAC unit without removing any bolts from the waterbox cover. Once installed, the waterbox hinge assembly can be left in place so that it can be reused anytime the HVAC unit is serviced.

A nuclear steam supply system having a start-up sub-system for heating a primary coolant. The nuclear steam supply system comprises a reactor vessel with core comprising nuclear fuel, and steam generating vessel fluidly coupled to the reactor vessel. A primary coolant loop formed within the reactor vessel and the steam generating vessel circulates primary coolant through the loop. A steam supply start-up sub-system is fluidly coupled to the primary coolant loop. The start-up sub-system is configured and operable to: (1) extract and receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant back into the primary coolant loop.