A heavy-water reactor facility dismantling apparatus according to an embodiment includes: a first cutting device for cutting the periphery of a first nozzle portion of a calandria, wherein the first nozzle portion is connected to the upper end of a first pipe positioned in the calandria of a heavy-water reactor facility; a second cutting device for cutting a first support part of the calandria, wherein the first support portion is connected to the lower end of the first pipe connected to the first nozzle portion; and a fixing and drawing device for fixing and drawing the first nozzle portion cut by the first cutting device.

An exposure prevention device for dismantling a heavy water reactor facility according to an embodiment includes: a shielding film that covers a front surface and a rear surface of a heavy water facility including a calandria and a calandria vault that accommodates the calandria; a plurality of radiation measuring instruments installed in the shielding film; and a motion detector installed in the shielding film.

The objective of the present invention is to provide a construction simulation system for nuclear power plant equipment, the system comprising: an information input unit into which nuclear power plant equipment installation information related to nuclear power plant equipment is inputted; a simulation implementation unit for generating a virtual reality simulation related to the nuclear power plant equipment on the basis of the nuclear power plant equipment installation information, and allowing the virtual reality simulation to be outputted through a nuclear power plant equipment installation simulation program; and a utilization unit for outputting the virtual reality simulation.

A method for decommissioning a heavy water reactor facility includes: removing the plurality of guide tubes from a plurality of through-holes; installing a plurality of shielding stoppers in the plurality of through-holes; removing the shielding stopper installed in one through-hole of the plurality of through-holes, and inserting a cutting device into a lower portion of the reactivity mechanism deck through the one through-hole to cut a connection portion between the reactivity mechanism deck and the calandria vault by using the cutting device; and separating the reactivity mechanism deck from the calandria vault.

A molten chloride fast reactor (MCFR) includes a plurality of reflectors defining a central core having a core geometric center. A flow channel fluidically connected to the central core. The flow channel includes an outlet flow channel downstream of the central core and an inlet flow channel upstream from the central core. A primary heat exchanger (PHX) disposed outside the central core and between the outlet flow channel and the inlet flow channel. The MCFR also includes a decay heat heat exchanger (DHHX). At least a portion of the DHHX is disposed above the core geometric center, and a fuel salt is configured to circulate at least partially through the outlet flow channel, the DHHX, the PHX, the inlet flow channel, and the central core.

A heat exchanger module with a longitudinal axis including a stack of plates defining at least two fluid circuits, at least a portion of the plates each including fluid circulation channels each delimited, at least in part, by a groove. A communication is produced between the channels within a same plate and between all the plates of a same circuit, in a feed or pre-collector zone, with a succession of channel groupings, two-by-two, in the form of bifurcations.

The present disclosure relates to a method of removing a nuclear power plant activation structure. Specifically, an embodiment of the present disclosure may provide a method of removing a nuclear power plant activation structure including flattening at least a portion of a wall surface of a peripheral portion of a wall of a nuclear reactor, the wall including a buried portion in which a nuclear power plant activation structure is buried and the peripheral portion circumferentially surrounding the buried portion; installing a drilling device in the flattened peripheral portion and performing a drilling operation; removing the nuclear power plant activation structure from the buried portion; and cutting the removed nuclear power plant activation structure and storing pieces of the cut nuclear power plant activation structure in a shielding container.

In one form, during the production of electrical energy from a stable uranium isotope by means of a fission chain reaction, extra neutrons are formed that can be used, in addition to electricity production, to also convert certain elements to other elements, specifically of some selected stable isotopes of particular elements to stable isotopes of other elements.

Neutron sources are used in the production of electrical energy in nuclear reactors, which are currently considered to be nuclear waste (they are absorbed in control rods in reactors and considered to be undesirable parts, that could start an uncontrolled fission reaction), or they are used to produce militarily sensitive fissionable plutonium, the commercial use of which is not allowed at present due to possible military abuse.

In one form, during the production of electrical energy from a stable uranium isotope by means of a fission chain reaction, extra neutrons are formed that can be used, in addition to electricity production, to also convert certain elements to other elements, specifically of some selected stable isotopes of particular elements to stable isotopes of other elements.

Neutron sources are used in the production of electrical energy in nuclear reactors, which are currently considered to be nuclear waste (they are absorbed in control rods in reactors and considered to be undesirable parts, that could start an uncontrolled fission reaction), or they are used to produce militarily sensitive fissionable plutonium, the commercial use of which is not allowed at present due to possible military abuse.

An apparatus for decommissioning heavy-water reactor facilities includes a shielding device including a drawing-out space that is mounted on the reactivity mechanism deck and communicates with one through-hole among the plurality of through-holes, a separating device that is inserted into the inside of one of the plurality of guide tubes through the drawing-out space and the one through-hole and cuts an end portion of the one guide tube connected to the calandria, and a drawing-out device that is inserted into the inside of the one guide tube through the drawing-out space and the one through-hole and supports the end portion of the one guide tube to draw out the one guide tube into the inside of the drawing-out space through the one through-hole.