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 present invention provides a mooring device capable of providing an omnidirectional restoring force. A support frame is provided on a dock. Two free guide rollers are provided at vertical corresponding positions that are respectively below a cross arm of the support frame and above the dock. A rotary damper is provided in the middle of a longitudinal portion of the support frame that is perpendicular to the dock. The two free guide rollers are respectively wound with a cable. The cable is fixed to a platform arm, and the platform arm is connected to a platform. An end of each cable is connected to a spring, and the other end of the spring is connected to a chain wound on a sprocket of the rotary damper.

A device for capturing a shielding ball for a heavy water reactor according to an embodiment includes: a head for separating a shielding ball positioned inside an end shield of a calandria of a heavy water reactor to an outside; and a mover for moving the head to the end shield of the calandria, wherein the head includes a head body, an opening former installed on the head body and forming an opening in the end shield, and a gate installed on the head body and controlling an amount of movement of the shielding ball discharged to the outside through the opening.

A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

A laser decontamination system according to an embodiment of the present invention includes: a laser generator generating a laser beam; an optical head inserted inside a pipe and focusing the laser beam on a contamination material inside the pipe for laser ablation; a first optical fiber connecting the laser generator and the optical head and transmitting the laser beam to the optical head; a spectroscope for analyzing a plasma spectrum generated in the pipe by the laser ablation; a second optical fiber connecting the spectroscope and the optical head and transmitting the plasma spectrum to the spectroscope; a dust collector for collecting a dust generated in the pipe by the laser ablation; a dust collection pipe connecting the dust collector and the inside of the pipe and transmitting the dust to the dust collector; and a blocking film positioned between the optical head and the pipe to block the dust.

Proposed is a system for utilizing unused heat-exchange water of a passive auxiliary feedwater system, and a reactor cooling control method utilizing the unused heat-exchange water of the passive auxiliary feedwater system and, more specifically, a system for utilizing unused heat-exchange water of a passive auxiliary feedwater system, and a reactor cooling control method utilizing the unused heat-exchange water of the passive auxiliary feedwater system, which may allow the unused heat exchange water remaining after heat exchange in the passive condensation tank to be used as cooling water, thereby increasing the efficiency of reactor cooling and increasing the efficiency of initial response in an event of a reactor accident. To this end, the proposed system includes a passive condensation tank, a condenser, a steam supply line, and a condensate water recovery line and is characterized by that a residual water discharge flow path is arranged at the inside thereof.

A mobile reactor radiation shielding solution prevents activation of structural materials to reduce a radiation dosage risk to living organisms and accelerates timetables for transport. The shielding solution can include: in-vessel neutron shield, in-vessel shadow shield, transport shield, and module shadow shield. In-vessel neutron shield reduces and prevents the activation of the structural materials and significantly reduces the need for heavy shielding to shield against the gamma emissions from activated structural materials. In-vessel shadow shield provides neutron and gamma shielding between the reactor and a balance-of-plant (BOP) module and control system. In-vessel shadow shield is placed near the active nuclear core to minimize size of the shield while maximizing the protected arc to shield radiation workers while preparing the nuclear reactor for transport. Transport shield is used during transportation when living organisms come into proximity of the reactor. Module shadow shield shields reactor control components and BOP module during operation.

A power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

A power conversion system for converting thermal energy from a heat source to electricity is provided. The system includes a chamber including an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The chamber also includes an outer shroud substantially surrounding the inner shroud. The chamber includes a source heat exchanger disposed in the internal passageway, the source heat exchanger being configured to receive a heat transmitting element associated with the heat source external to the chamber, and to transfer heat energy from the heat transmitting element to the working fluid. The system also includes a compressor disposed adjacent the inlet of the inner shroud and configured to transfer energy from the compressor to the working fluid, and an expander disposed adjacent the outlet of the inner shroud.