G21D3/12

Wind-solar reactor system and working method thereof

The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

Wind-solar reactor system and working method thereof

The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

WIND-SOLAR REACTOR SYSTEM AND WORKING METHOD THEREOF

The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

Load-following nuclear reactor system using thermal expansion-based neutron reflector movement and fuel assembly interval adjustment mechanisms and liquid metal primary coolant
10991468 · 2021-04-27 · ·

Provided is a nuclear reactor having a load following control system in which a nuclear reaction therein is naturally controlled by the generated heat, the nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a-liquid or a gas having a thermal expansion coefficient greater than that of the neutron reflector, and converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.

Load-following nuclear reactor system using thermal expansion-based neutron reflector movement and fuel assembly interval adjustment mechanisms and liquid metal primary coolant
10991468 · 2021-04-27 · ·

Provided is a nuclear reactor having a load following control system in which a nuclear reaction therein is naturally controlled by the generated heat, the nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a-liquid or a gas having a thermal expansion coefficient greater than that of the neutron reflector, and converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.

METHODS AND SYSTEMS FOR FACILITATING THE MANAGEMENT OF REACTOR TRANSIENT CONDITIONS ASSOCIATED WITH REACTORS
20210027901 · 2021-01-28 ·

Disclosed herein is a method of facilitating the management of reactor transient conditions associated with reactors. Accordingly, the method may include a step of receiving reactor data associated with a reactor from a reactor computer. Further, the method may include a step of determining a reactor transient condition associated with the reactor based on the reactor data. Further, the method may include a step of receiving reactor design data and measurement data associated with a plurality of reactor components of the reactor from the reactor computer. Further, the method may include a step of analyzing the reactor design data and the reactor measurement data. Further, the method may include a step of generating a notification corresponding to the reactor transient condition based on the analyzing. Further, the method may include a step of transmitting the notification to a user device associated with a user.

METHODS AND SYSTEMS FOR FACILITATING THE MANAGEMENT OF REACTOR TRANSIENT CONDITIONS ASSOCIATED WITH REACTORS
20210027901 · 2021-01-28 ·

Disclosed herein is a method of facilitating the management of reactor transient conditions associated with reactors. Accordingly, the method may include a step of receiving reactor data associated with a reactor from a reactor computer. Further, the method may include a step of determining a reactor transient condition associated with the reactor based on the reactor data. Further, the method may include a step of receiving reactor design data and measurement data associated with a plurality of reactor components of the reactor from the reactor computer. Further, the method may include a step of analyzing the reactor design data and the reactor measurement data. Further, the method may include a step of generating a notification corresponding to the reactor transient condition based on the analyzing. Further, the method may include a step of transmitting the notification to a user device associated with a user.

Nuclear power generation system utilizing thermal expansion in metallic members to move a neutron reflector
10522259 · 2019-12-31 · ·

A nuclear power generation system being safe and easily controlled by load following. The nuclear power generation system has a nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core having metallic fuel containing at least one selected from uranium-235, uranium-238 and plutonium-239; a reactor vessel containing the reactor core; metallic sodium loaded into the reactor vessel and heated by the reactor core; and a neutron reflector for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the reactor core being maintained at or above about 1. The neutron reflector is coupled to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector.

Nuclear power generation system utilizing thermal expansion in metallic members to move a neutron reflector
10522259 · 2019-12-31 · ·

A nuclear power generation system being safe and easily controlled by load following. The nuclear power generation system has a nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core having metallic fuel containing at least one selected from uranium-235, uranium-238 and plutonium-239; a reactor vessel containing the reactor core; metallic sodium loaded into the reactor vessel and heated by the reactor core; and a neutron reflector for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the reactor core being maintained at or above about 1. The neutron reflector is coupled to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector.

LOAD-FOLLOWING SMALL NUCLEAR REACTOR SYSTEM USING LIQUID METAL PRIMARY COOLANT
20190311816 · 2019-10-10 ·

Engineering safety systems always have insufficiencies in terms of safety, and construction of a complete safety system causes installation costs for the safety system to become very high. Provided is a small nuclear reactor HAVING a load following control system in which a nuclear reaction in the nuclear reactor is naturally controlled by the generated heat, the small nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a liquid or a gas having an expansion coefficient greater than that of the neutron reflector, converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.