Alternative designs for a modular test reactor are presented. In one aspect, a molten fuel salt nuclear reactor includes a vessel defining a reactor volume, the vessel being open-topped and otherwise having no penetrations. A neutron reflector is provided within the vessel and displacing at least some of the reactor volume, the neutron reflector defining a reactor core volume. A plurality of heat exchangers are contained within the vessel above the neutron reflector. A flow guide assembly is provided within the neutron reflector that includes a draft tube draft tube separating a central portion of the reactor core volume from an annular downcomer duct. Fuel salt circulates from the reactor core volume, through the heat exchangers, into the downcomer duct and then back into the reactor core volume.

A canned rotodynamiic flow machine (1) configured for operating with a working fluid such as molten salt of a molten salt nuclear reactor, comprising an impeller (6) arranged in a volute (3), with an inlet (4) and an outlet (5) for the working fluid, an induction or reluctance motor or generator comprising a stator (10) and a rotor (8), a can (18) separating a working fluid area in which the rotor (8) is arranged from a dry area containing the stator (10). The rotor (8) is operably coupled to the impeller (6). The stator (10) comprises stator windings for inducing a magnetic field that penetrates the rotor (8). The stator windings are distributed in slots (11) arranged in the stator (10). The part of the stator windings inside the slots is formed by one or more electrically conductive solid bars (12). An active magnetic bearing for use in a canned rotor dynamic flow machine for a molten salt nuclear reactor, comprising a stator (110,210) and a rotor (108,208). The said stator (108,208) comprises stator windings for inducing a magnetic field that penetrates the rotor (108,208). The stator windings are distributed in one or more slots arranged in the stator. The part of the stator windings inside said one or more slots is formed by one or more electrically conductive solid bars.

A canned rotodynamiic flow machine (1) configured for operating with a working fluid such as molten salt of a molten salt nuclear reactor, comprising an impeller (6) arranged in a volute (3), with an inlet (4) and an outlet (5) for the working fluid, an induction or reluctance motor or generator comprising a stator (10) and a rotor (8), a can (18) separating a working fluid area in which the rotor (8) is arranged from a dry area containing the stator (10). The rotor (8) is operably coupled to the impeller (6). The stator (10) comprises stator windings for inducing a magnetic field that penetrates the rotor (8). The stator windings are distributed in slots (11) arranged in the stator (10). The part of the stator windings inside the slots is formed by one or more electrically conductive solid bars (12). An active magnetic bearing for use in a canned rotor dynamic flow machine for a molten salt nuclear reactor, comprising a stator (110,210) and a rotor (108,208). The said stator (108,208) comprises stator windings for inducing a magnetic field that penetrates the rotor (108,208). The stator windings are distributed in one or more slots arranged in the stator. The part of the stator windings inside said one or more slots is formed by one or more electrically conductive solid bars.

Proposed is a reactor cooling system for cooling down a reactor damaged by a disaster accident and a reactor cooling method using same using contaminated water generated at a nuclear reactor as a cooling water source for cooling the nuclear reactor after the accident, thereby maximally suppressing discharge of the contaminated water into the sea. To this end, the reactor cooling system prosed above includes a nuclear power generation facility, a seawater storage tank, a seawater inflow flow path for introducing the seawater into the seawater storage tank and a seawater discharge flow path for discharging the seawater from the seawater storage tank to the sea, connected to one end and another end of the seawater storage tank, respectively, a heat exchanger installed in a water storage space of the seawater storage tank, a contaminated water supply flow path, and a contaminated water discharge flow path.

Proposed is a reactor cooling system for cooling down a reactor damaged by a disaster accident and a reactor cooling method using same using contaminated water generated at a nuclear reactor as a cooling water source for cooling the nuclear reactor after the accident, thereby maximally suppressing discharge of the contaminated water into the sea. To this end, the reactor cooling system prosed above includes a nuclear power generation facility, a seawater storage tank, a seawater inflow flow path for introducing the seawater into the seawater storage tank and a seawater discharge flow path for discharging the seawater from the seawater storage tank to the sea, connected to one end and another end of the seawater storage tank, respectively, a heat exchanger installed in a water storage space of the seawater storage tank, a contaminated water supply flow path, and a contaminated water discharge flow path.

A power distribution plate (PDP) sits on top of a support plate. Control rod drive mechanism (CRDM) units are mounted on top of the PDP, but the PDP is incapable of supporting the weight of the CRDM units and instead transfers the load to a support plate. The PDP has receptacles which receive cable modules each including mineral insulated (MI) cables, the MI cables being connected with the CRDM units. The PDP may further include a set of hydraulic lines underlying the cable modules and connected with the CRDM units. The cable modules in their receptacles define conduits or raceways for their MI cables and for any underlying hydraulic lines.

A power distribution plate (PDP) sits on top of a support plate. Control rod drive mechanism (CRDM) units are mounted on top of the PDP, but the PDP is incapable of supporting the weight of the CRDM units and instead transfers the load to a support plate. The PDP has receptacles which receive cable modules each including mineral insulated (MI) cables, the MI cables being connected with the CRDM units. The PDP may further include a set of hydraulic lines underlying the cable modules and connected with the CRDM units. The cable modules in their receptacles define conduits or raceways for their MI cables and for any underlying hydraulic lines.

A simple nuclear reactor in which most of the reflector material is outside of the reactor vessel is described. The reactor vessel is a cylinder that contains all of the fuel salt and a displacement component, which may be a reflector, in the upper section of the reactor vessel. Other than the displacement component, the reflector elements including a radial reflector and a bottom reflector are located outside the vessel. The salt flows around the outside surface of the displacement component through a downcomer heat exchange duct defined by the exterior of the displacement component and the interior surface of the reactor vessel. This design reduces the overall size of the reactor vessel for a given volume of salt relative to designs with internal radial or bottom reflectors.

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-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.