Apparatus and methods for jet impingement cooling are provided. In one arrangement, a fluid channelling structure engages against a target surface to define a flow volume. Fluid is jetted onto the target surface from inlets and is removed via outlets. Flow directing features form a plurality of channels with no straight paths between inlets and outlets. A time averaged flow direction of fluid in contact with each flow directing feature is more nearly perpendicular to a direction of jetting of the fluid from a nearest inlet than parallel to the direction of jetting One or more pairs of the inlets and outlets are such that a majority of fluid jetted onto the target surface from the inlet of the pair will be removed from the flow volume through the outlet of the same pair.

Apparatus and methods for jet impingement cooling are provided. In one arrangement, a fluid channelling structure engages against a target surface to define a flow volume. Fluid is jetted onto the target surface from inlets and is removed via outlets. Flow directing features form a plurality of channels with no straight paths between inlets and outlets. A time averaged flow direction of fluid in contact with each flow directing feature is more nearly perpendicular to a direction of jetting of the fluid from a nearest inlet than parallel to the direction of jetting One or more pairs of the inlets and outlets are such that a majority of fluid jetted onto the target surface from the inlet of the pair will be removed from the flow volume through the outlet of the same pair.

Claimed embodiments of the integral nuclear reactor relate to nuclear technology and can be used in reactors with different types of heat transfer fluids with a high boiling point, such as, for example, liquid metals, molten salts, etc. Design features of the invention embodiments claimed which have a coil heat exchanger sectioned along the secondary heat carrier circuit provides for an improvement in technical and economic features due to a decrease in metal consumption of the reactor; efficient use of the internal volume of the reactor; improved safety in case of the heat exchanger tube leaks; enabling the removal of residual heat during the time after removal of the protective plug before fuel discharge operations.

A nuclear reactor cooled by liquid metal or by molten salts, provided with a heat exchanger, having inlet of the primary fluid in the lower part and circumferential outlet window in the vicinity of the free surface of the primary fluid in the cold collector. The outlet window is located in an intermediate position with respect to the tube bundle partially raised with respect to the free surface in the cold collector and supplied with primary fluid throughout its height by means of an ancillary device for creating an underpressure in the cover gas of the exchanger with respect to the cover gas in the vessel. The raising of the exchanger and the positioning of the outlet window in the vicinity of the free surface of the primary coolant help to minimize the displacement of primary fluid in the event of accidental release of secondary fluid inside the heat exchanger.

A nuclear reactor cooled by liquid metal or by molten salts, provided with a heat exchanger, having inlet of the primary fluid in the lower part and circumferential outlet window in the vicinity of the free surface of the primary fluid in the cold collector. The outlet window is located in an intermediate position with respect to the tube bundle partially raised with respect to the free surface in the cold collector and supplied with primary fluid throughout its height by means of an ancillary device for creating an underpressure in the cover gas of the exchanger with respect to the cover gas in the vessel. The raising of the exchanger and the positioning of the outlet window in the vicinity of the free surface of the primary coolant help to minimize the displacement of primary fluid in the event of accidental release of secondary fluid inside the heat exchanger.

An energy production device may include a core configured to heat a heat transmission fluid, an energy harnessing device configured to convert heat into electrical energy and a heat transfer device positioned over the core configured to receive the heat transmission fluid and transfer the heat to the energy harnessing device. The energy production device may further include a vibration isolator positioned between the energy harnessing device and the heat transfer device. The vibration isolator may be configured to secure the energy harnessing device to the heat transfer device and substantially prevent the transmission of motion from the energy harnessing device to the heat transfer device.

An energy production device may include a core configured to heat a heat transmission fluid, an energy harnessing device configured to convert heat into electrical energy and a heat transfer device positioned over the core configured to receive the heat transmission fluid and transfer the heat to the energy harnessing device. The energy production device may further include a vibration isolator positioned between the energy harnessing device and the heat transfer device. The vibration isolator may be configured to secure the energy harnessing device to the heat transfer device and substantially prevent the transmission of motion from the energy harnessing device to the heat transfer device.

A closed loop heat convection cooling system for nuclear reactors. The cooling system is formed outside the containment structure of the nuclear reactor and the structure of the cooling system prevents gas that is not in the closed circuit to approach the reactor within neutron radiation distance. The cooling systems has cooling assemblies that are housed in protective structures, which shield the cooling assemblies for projectile impact. Air inlet and outlet apertures are formed in the protective structures to cause outside air to be drawn into the protective structures to cool the cooling assemblies.

A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.

The present disclosure relates to reducing losses in the effective delayed neutron fraction during the operation of a reactor, making it possible to provide for a high efficiency of burning out of minor actinides, and also that of increasing the leak-tight integrity of the primary circuit and the reliability of the reactor. The above-mentioned technical result is achieved in an integral molten salt fast reactor with a circulating fuel composition, comprising a vessel with inlet and outlet secondary circuit pipelines and a connection pipe for initial filling and replenishment with molten salt coolant, heat exchangers of the primary/secondary circuit, a side reflector, an upper reflector and a lower reflector, a core with a shell, and a main circulation pipe, wherein the side reflector is made of sections between which the heat exchangers of the primary/secondary circuit are arranged such that they lie flush against the shell of the core.