A system for attenuating seismic forces includes a reactor pressure vessel containing nuclear fuel and a containment vessel that houses the reactor pressure vessel. Both the reactor pressure vessel and the containment vessel may include a bottom head. Additionally, the system may include a base support that is configured to contact a support surface on which the containment vessel is positioned in a substantially vertical orientation. An attenuation device may be located between the bottom head of the reactor pressure vessel and the bottom head of the containment vessel. Seismic forces that travel from the base support to the reactor pressure vessel via the containment vessel may be attenuated by the attenuation device in a direction that is substantially lateral to the vertical orientation of the containment vessel.

Disclosed herein is an aerosol generating and mixing system operating at a high temperature and a high pressure which includes an aerosol generating device; and an aerosol mixing device, wherein the aerosol generating device includes a pre-mixing tank and a mixing tank, and the mixing tank and the pre-mixing tank include a wing configured to rotate about a central shaft of the tank so as to agitate an inside aerosol, and an agitating motor configured to rotate the wing, and a filling nozzle of the mixing tank and the pre-mixing tank is configured to inject any of an aerosol aqueous solution and an aerosol particle.

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.

A monitoring and controlling system includes a non-safety system and a safety system. The non-safety system includes operation switches for operating a safety protection device which is a monitoring-and-control target. The safety system includes operation switches for operating the safety protection device, a parameter generation circuit which generates a parameter to be transmitted to the non-safety system, and a coincidence determination circuit which determines whether or not a parameter returned from the non-safety system and the parameter transmitted from the parameter generation circuit coincide with each other. If the coincidence determination circuit determines that the parameters do not coincide with each other, the safety system blocks an output signal from the operation switches of the non-safety system.

A monitoring and controlling system includes a non-safety system and a safety system. The non-safety system includes operation switches for operating a safety protection device which is a monitoring-and-control target. The safety system includes operation switches for operating the safety protection device, a parameter generation circuit which generates a parameter to be transmitted to the non-safety system, and a coincidence determination circuit which determines whether or not a parameter returned from the non-safety system and the parameter transmitted from the parameter generation circuit coincide with each other. If the coincidence determination circuit determines that the parameters do not coincide with each other, the safety system blocks an output signal from the operation switches of the non-safety system.

An underground nuclear power reactor system has a hollow blast tunnel which extends from one end of a containment member. The system includes a nuclear reactor vessel and other components that may be positioned on a movable support member or on a bottom wall of the containment member. A blast tunnel, which defines a blast chamber, has a plurality of spaced-apart debris deflectors positioned therein. The blast chamber has an upper wall with a roof opening formed therein which is selectively closed by a roof portion. If the reactor needs to be repaired or replaced, the roof portion is opened so that the reactor vessel can through the roof opening. If the reactor vessel explodes, a blast therefrom drives debris therefrom through a blast door and into the blast chamber where the deflectors reduce blast force as the debris passes through the blast chamber.

Apparatuses for reducing or eliminating Type 1 LOCAs in a nuclear reactor vessel. A nuclear reactor including a nuclear reactor core comprising a fissile material, a pressure vessel containing the nuclear reactor core immersed in primary coolant disposed in the pressure vessel, and an isolation valve assembly including, an isolation valve vessel having a single open end with a flange, a spool piece having a first flange secured to a wall of the pressure vessel and a second flange secured to the flange of the isolation valve vessel, a fluid flow line passing through the spool piece to conduct fluid flow into or out of the first flange wherein a portion of the fluid flow line is disposed in the isolation valve vessel, and at least one valve disposed in the isolation valve vessel and operatively connected with the fluid flow line.

Apparatuses for reducing or eliminating Type 1 LOCAs in a nuclear reactor vessel. A nuclear reactor including a nuclear reactor core comprising a fissile material, a pressure vessel containing the nuclear reactor core immersed in primary coolant disposed in the pressure vessel, and an isolation valve assembly including, an isolation valve vessel having a single open end with a flange, a spool piece having a first flange secured to a wall of the pressure vessel and a second flange secured to the flange of the isolation valve vessel, a fluid flow line passing through the spool piece to conduct fluid flow into or out of the first flange wherein a portion of the fluid flow line is disposed in the isolation valve vessel, and at least one valve disposed in the isolation valve vessel and operatively connected with the fluid flow line.

A method and system for the thermoelectric conversion of nuclear reactor generated heat including upon a nuclear reactor system shutdown event, thermoelectrically converting nuclear reactor generated heat to electrical energy and supplying the electrical energy to a mechanical pump of the nuclear reactor system.

An underwater electricity production module includes an elongated cylindrical casing, which includes an integrated electricity generation unit having a nuclear boiler. The generator is connected to an external electricity distribution station by electrical cables. The nuclear boiler is placed in a dry chamber of a reactor compartment associated with a chamber forming a safety water storage reservoir of the reactor. At least a radial wall of the reservoir chamber is in a direct heat exchange relationship with a marine environment that surrounds the underwater electricity production module in which the underwater electricity production module is submerged.