A fusion drive magnetically confining a plasma in a stable plectonemic minimum-energy Taylor states formed from the merging of a plurality of plectonemic Taylor states. Magnetic reconnection converts magnetic energy into ion heating to attain high temperatures before compression. The plasma configuration is then compressed to net gain in a peristaltic magnetic nozzle arrangement. The fusion drive supports generation of electrical power with inductive direct electric or thermal conversion methods.

A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.

Provided are apparatuses and methods for providing power to a fission-type nuclear power plant by a reactor with a confining wall at least partially enclosing a confinement region within which charged particles and neutrals can rotate. A plurality of electrodes is adjacent or proximate to the confinement region. A control system having a voltage source applies an electric potential between the plurality of electrodes to generate an electric field within the confinement region to induce rotational movement of the charged particles and the neutrals therein. A reactant is disposed in the confinement region. Repeated collisions between the neutrals and the reactant produce energy and a product having a nuclear mass that is different from a nuclear mass of the nuclei of the neutrals and the reactant. The energy dissipates from the reactor to provide power to the fission-type nuclear power plant.

A platform for a nuclear power plant is configured to span a pool (4) of a nuclear power plant by being movable along two parallel rails (6) arranged on either side of the pool (4). The platform comprises at least one platform module (16) having a module floor (18) defining at least part of a platform floor (14) and two guide assemblies (20) for mating with rails (6) to guide the platform along said rails (6). Each platform module is expandable to vary the spacing between the two guide assemblies (20) of the platform module (16), the two guide assemblies (20) being close together in a storage configuration and far apart in a service configuration.

To reduce size and mass of a nuclear reactor system, an integrated in-vessel shield separates the role of a neutron reflector and a neutron shield. Nuclear reactor system includes a pressure vessel including an interior wall and a nuclear reactor core located within the interior wall of the pressure vessel. Nuclear reactor core includes a plurality of fuel elements and at least one moderator element. Nuclear reactor system includes a reflector located inside the pressure vessel that includes a plurality of reflector blocks laterally surrounding the plurality of fuel elements and the at least one moderator element. Nuclear reactor system includes the in-vessel shield located on the interior wall of the pressure vessel to surround the reflector blocks. In-vessel shield is formed of two or more neutron absorbing materials. The two more neutron absorbing materials include a near black neutron absorbing material and a gray neutron absorbing material.

According to an embodiment, a nuclear plant has: an outer well; an in-Containment Atmosphere Dilution System to inject a gas that has a low concentration of oxygen in the outer well into a containment vessel; an accumulator containing pressurized oxygen therein; and a passive containment cooling system including: a scrubbing pool arranged in the outer well; a cooling water pool installed above a dry well and the outer well; a heat exchanger partly submerged in a cooling water; a wet well gas supply pipe that is connected to an inlet plenum of the heat exchanger at one end and connected to a wet well gas phase at the other end; and a gas vent pipe that is connected to an outlet plenum of the heat exchanger at one end and is submerged in the scrubbing pool at the other end.

An energy production device may include a core and a heat exchanger positioned over the core. The core may include one or more fuel rods. The core may further include a heat transmission fluid configured to flow through natural convection upwards through the one or more fuel rods and collect heat therefrom. The core may also include a reaction control device including a neutron-absorbing material. The heat exchanger may be configured to receive the heat transmission fluid and transfer the heat to an energy harnessing device positioned on an opposite side of the heat exchanger from the core.

A control rod assembly for a nuclear reactor having a reactor core and a pressurized fluid source, including a control rod disposed within a control rod sleeve, a lead screw that is selectively secured to the control rod, a trip latch that is secured to a bottom end of the lead screw, the trip latch being selectively securable to a top end of the control rod, a control rod drive motor that is operably connected to the lead screw, and a valve that is in fluid communication with the pressurized fluid source of the nuclear reactor and is movable between a first position and a second position, wherein in the second position of the gas valve the trip latch is in an open position.

A fuel movement simulator system includes a virtual reality (VR) system configured to generate a virtual refuel floor environment; and a fuel movement simulator assembly configured to provide a physical interface to the virtual refuel floor environment, the fuel movement simulator assembly including a replica mast, a replica control console connected to the replica mast, and a support structure configured to support the replica mast and replica control console.

A power conversion system for converting thermal energy from a heat source to electricity is provided. The system includes a chamber including an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The chamber also includes an outer shroud substantially surrounding the inner shroud. The chamber includes a source heat exchanger disposed in the internal passageway, the source heat exchanger being configured to receive a heat transmitting element associated with the heat source external to the chamber, and to transfer heat energy from the heat transmitting element to the working fluid. The system also includes a compressor disposed adjacent the inlet of the inner shroud and configured to transfer energy from the compressor to the working fluid, and an expander disposed adjacent the outlet of the inner shroud.