G21C7/32

Core of Fast Reactor and Method of Operating Fast Reactor
20210287811 · 2021-09-16 ·

The invention provides a core of a fast reactor including a sodium plenum installed above a core fuel, which is capable of reliably reducing a void reactivity, and an operation method thereof. The core of a fast reactor including the sodium plenum installed above the core fuel is characterized in that a tip of a primary control rod is inserted into a core fuel region, and a tip of a backup control rod is arranged above an upper end of the core fuel region for operation.

Core of Fast Reactor and Method of Operating Fast Reactor
20210287811 · 2021-09-16 ·

The invention provides a core of a fast reactor including a sodium plenum installed above a core fuel, which is capable of reliably reducing a void reactivity, and an operation method thereof. The core of a fast reactor including the sodium plenum installed above the core fuel is characterized in that a tip of a primary control rod is inserted into a core fuel region, and a tip of a backup control rod is arranged above an upper end of the core fuel region for operation.

Systems and methods for maintaining cover gas in nuclear reactors

Cover gas control systems include a reservoir and injection path for direct injection into fuel transfer machinery. If seals in the fuel handling machinery leak, cover gas is provided from the reservoir to flow to the leak without contamination from a reactor to which the fuel transfer machinery is joined. This providing cover gas may be passive or automatic in response to a detected low pressure level, detected ambient air ingress, low volume level of cover gas, or manually actuated through an operator. The cover gas may be injected from below the leak but above the reactor. A limitation in the injection path keeps cover gas injection at rates sufficient to allow operator reaction and sealing before the reservoir is depleted. A pressure pulse transmitter, blowout preventer, and transfer port plug are useable in the systems, which can be implemented in fuel handling machinery for reactors using a cover gas.

Systems and methods for maintaining cover gas in nuclear reactors

Cover gas control systems include a reservoir and injection path for direct injection into fuel transfer machinery. If seals in the fuel handling machinery leak, cover gas is provided from the reservoir to flow to the leak without contamination from a reactor to which the fuel transfer machinery is joined. This providing cover gas may be passive or automatic in response to a detected low pressure level, detected ambient air ingress, low volume level of cover gas, or manually actuated through an operator. The cover gas may be injected from below the leak but above the reactor. A limitation in the injection path keeps cover gas injection at rates sufficient to allow operator reaction and sealing before the reservoir is depleted. A pressure pulse transmitter, blowout preventer, and transfer port plug are useable in the systems, which can be implemented in fuel handling machinery for reactors using a cover gas.

NUCLEAR STEAM SUPPLY AND START-UP SYSTEM, PASSIVELY-COOLED SPENT NUCLEAR FUEL POOL SYSTEM AND METHOD THEREFOR, COMPONENT COOLING WATER SYSTEM FOR NUCLEAR POWER PLANT, PASSIVE REACTOR COOLING SYSTEM, STEAM GENERATOR FOR NUCLEAR STEAM SUPPLY SYSTEM
20210142920 · 2021-05-13 ·

A nuclear steam supply system having a start-up sub-system for heating a primary coolant. The nuclear steam supply system comprises a reactor vessel with core comprising nuclear fuel, and steam generating vessel fluidly coupled to the reactor vessel. A primary coolant loop formed within the reactor vessel and the steam generating vessel circulates primary coolant through the loop. A steam supply start-up sub-system is fluidly coupled to the primary coolant loop. The start-up sub-system is configured and operable to: (1) extract and receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant back into the primary coolant loop.

NUCLEAR REACTOR SYSTEM HAVING NATURAL CIRCULATION OF PRIMARY COOLANT

A nuclear reactor system that, in one embodiment, utilizes natural circulation to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heat exchange sub-system is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heat exchange sub-system that is used to vaporize a secondary coolant. In another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground.

NUCLEAR REACTOR SYSTEM HAVING NATURAL CIRCULATION OF PRIMARY COOLANT

A nuclear reactor system that, in one embodiment, utilizes natural circulation to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heat exchange sub-system is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heat exchange sub-system that is used to vaporize a secondary coolant. In another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground.

Fast reactor with primary and backup control rods

A fast reactor core includes a sodium plenum installed above the fuel. The sodium plenum is capable of reducing a void reactivity. During operation, a tip of a primary control rod is inserted in a core fuel region, and a tip of a backup control rod is arranged near an upper end of the sodium plenum.

Nuclear reactor passive reactivity control system
11862354 · 2024-01-02 ·

A passive nuclear reactor control device. The passive nuclear reactor control device comprises a sealed chamber, which comprises a reservoir and a tube in fluid communication with the reservoir. A molten salt is within the sealed chamber, the molten salt being a eutectic mixture of a monovalent metal halide, and a fluoride or chloride of one or more lanthanides and/or a fluoride or chloride of hafnium. A gas is within the sealed chamber, and the gas does not react with the molten salt.

Nuclear reactor passive reactivity control system
11862354 · 2024-01-02 ·

A passive nuclear reactor control device. The passive nuclear reactor control device comprises a sealed chamber, which comprises a reservoir and a tube in fluid communication with the reservoir. A molten salt is within the sealed chamber, the molten salt being a eutectic mixture of a monovalent metal halide, and a fluoride or chloride of one or more lanthanides and/or a fluoride or chloride of hafnium. A gas is within the sealed chamber, and the gas does not react with the molten salt.