Nuclear reactors include isolation condenser systems that can be selectively connected with the reactor to provide desired cooling and pressure relief. Isolation condensers are immersed in a separate chamber holding coolant to which the condenser can transfer heat from the nuclear reactor. The chamber may selectively connect to an adjacent coolant reservoir for multiple isolation condensers. A check valve may permit coolant to flow only from the reservoir to the isolation condenser. A passive switch can operate the check valve and other isolating components. Isolation condensers can be activated by opening an inlet and outlet to/from the reactor for coolant flow. Fluidic controls and/or a pressure pulse transmitter may monitor reactor conditions and selectively activate individual isolation condensers by opening such flows. Isolation condenser systems may be positioned outside of containment in an underground silo with the containment, which may not have any other coolant source.

An offshore energy generation system (OEGS), is described. The offshore energy generation system delivers clean energy in the form of electricity and/or ammonia (NH3) and freshwater to offshore or onshore consumers. By deploying this offshore energy generation system, the net zero emissions targets from IPCC can be achieved and the water scarcity crisis mitigated. The offshore energy generation system enables better safety of the population served, optimal use of land, eliminate land use conflicts and enables the protection of the world cultural heritage. The offshore energy generation system comprises of an electric power generation system based on nuclear or hydrogen (H2) fuel cells, ammonia generation, freshwater generation, offshore cranes, data processing centers, blockchain, helideck, telecommunications system, automation and control system, nitrogen and hydrogen generation systems.

An offshore energy generation system (OEGS), is described. The offshore energy generation system delivers clean energy in the form of electricity and/or ammonia (NH3) and freshwater to offshore or onshore consumers. By deploying this offshore energy generation system, the net zero emissions targets from IPCC can be achieved and the water scarcity crisis mitigated. The offshore energy generation system enables better safety of the population served, optimal use of land, eliminate land use conflicts and enables the protection of the world cultural heritage. The offshore energy generation system comprises of an electric power generation system based on nuclear or hydrogen (H2) fuel cells, ammonia generation, freshwater generation, offshore cranes, data processing centers, blockchain, helideck, telecommunications system, automation and control system, nitrogen and hydrogen generation systems.

There are provided a nuclear power plant dismantling method and apparatus. The nuclear power plant dismantling method includes: selecting a nuclear reactor to be dismantled; and performing nuclear power plant dismantling work on the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus includes: a frame unit shielding the nuclear reactor to prevent contaminants in the nuclear reactor from being released to the outside; a cutting module provided on the frame unit and performing cutting work on the nuclear reactor; a link fixing module having a hollow area formed therein, entering an internal space of the nuclear reactor to link the frame unit and the nuclear reactor with each other, and having a bar shape; and a purging module entering the hollow area of the link fixing module and performing purging on the inside of the nuclear reactor in order to secure safety in the cutting work.

There are provided a nuclear power plant dismantling method and apparatus. The nuclear power plant dismantling method includes: selecting a nuclear reactor to be dismantled; and performing nuclear power plant dismantling work on the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus includes: a frame unit shielding the nuclear reactor to prevent contaminants in the nuclear reactor from being released to the outside; a cutting module provided on the frame unit and performing cutting work on the nuclear reactor; a link fixing module having a hollow area formed therein, entering an internal space of the nuclear reactor to link the frame unit and the nuclear reactor with each other, and having a bar shape; and a purging module entering the hollow area of the link fixing module and performing purging on the inside of the nuclear reactor in order to secure safety in the cutting work.

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. Thus, any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core. This arrangement reduces the opportunity for differential movement between the control elements and the reactor core.

A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.

A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.