A nuclear reactor is positioned on a barge which is floating in a water tank. A plurality of counter weight assemblies interconnect the barge with the tank to create a lifting force to the barge and to maintain the barge in a level position. Structure is also included for limiting horizontal movement of the counter weight of the counter weight assemblies.

The power plant system includes a molten salt reactor assembly, a thermocline unit, phase change heat exchangers, and process heat systems. The thermocline unit includes an insulated tank, an initial inlet, a plurality of zone outlets, and a plurality of gradient zones corresponding to each zone outlet and being stacked in the tank. Each gradient zone has a molten salt portion at a portion temperature corresponding to the molten salt supply from the molten salt reactor being stored in the tank and stratified. The molten salt portions at higher portion temperatures generate thermal energy for process heat systems that require higher temperatures, and molten salt portions at lower portion temperatures generate thermal energy for process heat systems that require lower temperatures. The system continuously pumps the molten salt supply in controlled rates to deliver the heat exchange fluid supply to perform work in the corresponding particular process heat system.

A modular and transportable nuclear reactor system comprising a transportation module including a housing. A cask and a radiation shielding section are located in the housing with the shielding surrounding the cask. A high temperature sodium cooled reactor is located in the cask and the reactor is cooled by the natural circulation of in-vessel sodium. The reactor powers at least one thermal-to-electric conversion unit.

The present invention relates to a connecting apparatus for a steam generator disposed between a steam generator and a flow mixing header to fasten the steam generator to the flow mixing header in a sealed manner, and an integral reactor including the same. The connecting apparatus for a steam generator disposed between a steam generator and a flow mixing header and fastening the steam generator to the flow mixing header in a sealing manner includes: a baseplate mounted on the flow mixing header and having a through hole formed at the center thereof; and a steam generator connecting portion protruding along the circumference of the through hole in the base plate and allowing an outlet of the steam generator to be inserted and fastened thereto. Through this configuration, since the connecting apparatus for a steam generator is tightly fastened to the flow mixing header, leakage of a coolant therebetween may be prevented, and since the steam generator is horizontally disposed in the flow mixing header, structural stabilization may be achieved.

The invention relates to the field of nuclear technology, in particular, to the disposal of spent long-length elements of a nuclear reactor. The invention reduces the complexity and time required to splice long-length elements and minimizes dose loads on attendants. The method of splicing long-length elements of a nuclear reactor into fragments involves placement of long-length elements inside the container and subsequent cutting. The long element is lowered into the container to its full height and cut on the level of the upper edge of the container with the separation from it of a fragment equal to the height of the container, then the upper part of the long-length element remaining after cutting is lowered inside the container to its full height and the cutting of the long-length element into fragments is repeated until it is fully spliced.

A dismantling and decontamination system of biodegradable concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under biodegradable concrete to form a lower penetrated part of the biodegradable concrete; a decontamination device inserted inside the biodegradable concrete for decontaminating radioactive waste of the inner wall of the biodegradable concrete; a waste receiving device movable through the lower penetrated part of the biodegradable concrete; and a blocking device for blocking the upper opening of the biodegradable concrete to block an outflow of the radioactive dust.

The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

A nuclear reactor decommissioning system according to an embodiment includes a cutting device to cut a reactor, a lifting device inserted inside the reactor to lift the reactor, and a shielding device that is positioned between the reactor and the lifting device and blocks radioactive dust generated by the cutting device from spreading.

An austenitic stainless steel includes a mixed grain structure composed of a columnar crystal having an average crystal grain size of 20 μm or less and an equiaxed crystal having an average crystal grain size of 5.0 μm or less, in which an area proportion of the columnar crystal in the mixed grain structure is 20% or more, and an average crystal grain size of the whole mixed grain structure is 5.0 μm or less. Accordingly, it is possible to provide a material having excellent irradiation resistance and mechanical properties.

A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.