A plurality of heat transfer pipes; a first header and a second header to which both ends of each of the heat transfer pipes that are disposed in parallel are fixed, respectively; a plurality of plate shaped fins through which each of the heat transfer pipes is penetrated and that are provided at intervals in a direction in which the heat transfer pipes extend between the first header and the second header; and a fan that circulates an airflow between the plate shaped fins are included. The first header and the second header are formed to be sectioned into multiple rows, the heat transfer pipes are disposed densely in an sectioned area of the first header and the second header, and the heat transfer pipes are disposed sparsely in an area between the sectioned areas of the first header and the second header.

A plurality of heat transfer pipes; a first header and a second header to which both ends of each of the heat transfer pipes that are disposed in parallel are fixed, respectively; a plurality of plate shaped fins through which each of the heat transfer pipes is penetrated and that are provided at intervals in a direction in which the heat transfer pipes extend between the first header and the second header; and a fan that circulates an airflow between the plate shaped fins are included. The first header and the second header are formed to be sectioned into multiple rows, the heat transfer pipes are disposed densely in an sectioned area of the first header and the second header, and the heat transfer pipes are disposed sparsely in an area between the sectioned areas of the first header and the second header.

An exemplary embodiment of the present invention provides an apparatus for dismantling for heavy water reactor facilities, including: a cutting device configured to divide a calandria of the heavy water reactor facilities into a main shell and a sub-shell; and a transfer device configured to draw the main shell cut by the cutting device to the outside, wherein the transfer device includes a fixing unit configured to fix the calandria; and a transfer unit configured to transfer the fixing unit.

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.

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.

An anti-rotation device for preventing separation of a valve stem and valve disc(s) in a gate valve in a nuclear reactor power plant of the type where connection means, such as a wedge or disc hub, is threadedly engaged by the valve stem to actuate the valve and a method for maintenance or repair of the valve without disassembly of the valve or removal of the valve actuator.

Method of fabricating structures, such as parts for use in nuclear power generation systems, are described herein. A representative method of fabricating a part for a nuclear reactor system includes additively manufacturing the part as a monolithic structure from a wire formed of an oxide dispersion strengthen (ODS) material, which includes an oxide material dispersed within a metal material. Specifically, the method can include directing a beam of thermal energy toward the wire to melt the wire, and permitting the melted wire to cool and solidify to form the part such that the oxide material remains substantially dispersed within the metal material. By maintaining the dispersion of the oxide material within the metal material, the ODS material can retain a good creep resistance, wear-resistance, corrosion resistance, and/or other ODS material property at elevated temperatures—even after fabrication.

This patent application is for a process of nuclear power generation with ˜KW output by making the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 in a Thorium Molten Salt Reactor (Th-MSR) to undergo fission along the thorium fuel cycle by providing thermal neutrons which were obtained by slowing down of fast neutrons from n external neutron generators with the help of graphite moderators carefully arranged inside the Th-MSR.

The molten salt that entered the reactor at a temperature of 600° C. becomes hot to 750° C. due to nuclear fission, goes through a heat exchanger and returns to the reactor. The output power of this reactor is proportional to the number of thermal neutrons supplied to the inside of the reactor, and when the external neutron generator is turned ON-OFF, nuclear power generation is also ON-OFF.

This Th-MSR power generation process with thermal neutron generators, which Dr. Choi is applying for a patent, will be one of the most innovative ways to generate ˜kW range nuclear power with the use of 100% non-radioactive nuclear fuel since until now all the Th-MSR power generation scheme relied upon neutrons from the natural decay of Uranium-235 mixed with the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 with a mixing ratio of 80% ThF4 to 20% UF4. Key Word Thorium Molten Salt Reactor, Thermal Neutron Generator

Reverse steam generator for a lead-cooled fast reactor. The reverse steam generator comprises a cylindrical body with a bundle of heat exchange tubes located inside, the ends of the heat exchange tubes being fixed in tube sheets with intermediate support grids; inlet and outlet spherical chambers for supplying liquid metal coolant; a lower branch pipe for inlet water; and an upper branch pipe for a steam outlet. The cylindrical body is arranged horizontally and is curved in a Z-shape with a difference in height. The bundle of heat exchange tubes is also made in a Z-shape, repeating the bend of the cylindrical body.

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. Fastening the steam generator to the flow mixing header in a sealing manner includes: a base plate mounted on the flow mixing header 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 allowing an outlet of the steam generator to be inserted and fastened thereto. Since the connection for the steam generator is tightly fastened to the flow mixing header, leakage of a coolant therebetween is prevented, and since the steam generator is horizontally disposed in the flow mixing header, structural stabilization may be achieved.