Disclosed is a reactor thermal management system. A molten salt reactor vessel and a second component (e.g., a drain tank) fluidly coupled with the molten salt reactor vessel are configured to receive a flow of a molten salt therewith. The reactor thermal management system includes an internal shield or vessel encompassing the molten salt reactor vessel and the second component, the internal shield or vessel defining a first thermally insulative region therein. The internal shield or vessel is configured to maintain the first thermally insulated region above a melting temperature of the molten salt during operation of the molten salt reactor vessel.

The group of invention refers to the area of nuclear power engineering, particularly to auxiliary devices for nuclear power plants, namely to the devices for installation of the outer heat insulation of a nuclear reactor vessel, and can be used at nuclear plants for recovery annealing of welds and/or base metal of the VVER reactor pressure vessel. The task to be solved by the claimed group of inventions is to ensure the installation and disassembly of heat insulation of the outer surface of the VVER reactor pressure vessel in the confined space under the reactor and with the high level of ionizing radiation, as well as work performance in an automated mode, which excludes the exposure of personnel to ionizing radiation.

The technical result of the invention related to outer heat insulation of the nuclear reactor pressure vessel is the reduction of the temperature gradient through the thickness of the nuclear reactor vessel by heat insulation of the external reactor vessel surface, assurance of uniform physical properties for the reactor vessel metal and welds, and reduction of thermal impacts on the surrounding structures during recovery annealing of the welds and/or base metal of the VVER reactor vessel.

The technical result of the invention is provided by the fact that the external heat insulation of the nuclear reactor pressure vessel includes racks, supporting and heat insulation rings installed in series above each other on the upper support platforms of the racks and covering the nuclear reactor pressure vessel, with the racks evenly placed under the supporting and heat insulation rings on the floor of the space under reactor, each rack is provided with guide channels made on the upper part of the inner surface of the rack, and pivoted on the rack base, while the joint between the rack and the rack base is offset relative to the center of gravity of the rack with the possibility of deflection of the rack from the vertical position and its self-return to the vertical position, and the rack base is equipped with an adjustable screw support and has a support platform. Primarily supporting and heat insulation rings are made in the form of articulated sections of frame structure, made in the form of arched ring segments; heat insulation made of mullite-silica felt is fixed on the inner side of the frame of each heat insulation ring section; heat insulation blocks made in the form of triangular sheet piles of mullite-silica felt are additionally fixed on the upper surface of the upper heat insulation ring sections; support casings are made on the outer side of the frame of the support and heat insulation ring sections adjacent to the racks.

Disclosed is a reactor thermal management system. A molten salt reactor vessel and a second component (e.g., a drain tank) fluidly coupled with the molten salt reactor vessel are configured to receive a flow of a molten salt therewith. The reactor thermal management system includes an internal shield or vessel encompassing the molten salt reactor vessel and the second component, the internal shield or vessel defining a first thermally insulative region therein. The internal shield or vessel is configured to maintain the first thermally insulated region above a melting temperature of the molten salt during operation of the molten salt reactor vessel.

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. A continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. Fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.

Disclosed is a reactor thermal management system. A molten salt reactor vessel and a second component (e.g., a drain tank) fluidly coupled with the molten salt reactor vessel are configured to receive a flow of a molten salt therewith. The reactor thermal management system includes an internal shield or vessel encompassing the molten salt reactor vessel and the second component, the internal shield or vessel defining a first thermally insulative region therein. The internal shield or vessel is configured to maintain the first thermally insulated region above a melting temperature of the molten salt during operation of the molten salt reactor vessel.