Patent classifications
G21D3/16
Controlling a power output of a nuclear reaction without control rods
A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction. A representative nuclear power system further includes a riser positioned above the reactor core and a primary coolant flow path that extends from a bottom portion of the reactor vessel, through the reactor core, and through an annulus between the riser and the reactor vessel. A primary coolant circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to a power generation system configured to generate electric power. The nuclear power system further includes a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.
Controlling a power output of a nuclear reaction without control rods
A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction. A representative nuclear power system further includes a riser positioned above the reactor core and a primary coolant flow path that extends from a bottom portion of the reactor vessel, through the reactor core, and through an annulus between the riser and the reactor vessel. A primary coolant circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to a power generation system configured to generate electric power. The nuclear power system further includes a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.
Control rod operation monitoring method and control rod operation monitoring system
A control rod operation generates a rod insertion block signal during operation of a reactor. Four neutron detector assemblies including a plurality of LPRMs arranged in an axial direction of a core are arranged adjacent to a plurality of insertion selection control rods, respectively, which are simultaneously inserted into the core. Neutron flux ratio calculation units are arranged in each of the neutron detector assemblies, and ratios (neutron flux ratios B.sub.A/A.sub.A, C.sub.A/A.sub.A, and D.sub.A/A.sub.A) of an average LPRM signal of the respective LPRMs at positions B, C, and D to an average LPRM signal of the respective LPRMs at a position A which is closest to the control rod insertion end of the core are calculated. When the largest neutron flux ratio out of the neutron flux ratios exceeds a set neutron flux ratio, a rod insertion block signal which is generated by a local range rod insertion monitor is output.
REACTIVITY BOOSTER-QUENCHER, AUTOMATIC POWER MODULES SEPARATOR, AND RELATED METHODS THEREOF
A nuclear power reactor may include a plurality of power modules, each including a nuclear fuel and a power conversion system configured to convert heat generated from the nuclear fuel to electricity, where the nuclear fuel of the plurality of power modules collectively forms a reactor core. The nuclear power reactor may also include a sleeve being disposed between the plurality of power modules, where the sleeve has a first end and a second end opposite to the first end. The nuclear power reactor may further include a reactivity booster having a neutron source and a reactivity quencher having a neutron absorber. The reactivity booster may be movable between a first location adjacent the first end of the sleeve and a second location adjacent the reactor core, and the reactivity quencher may be movable between a third location adjacent the second end and the second location adjacent the reactor core.
REACTIVITY BOOSTER-QUENCHER, AUTOMATIC POWER MODULES SEPARATOR, AND RELATED METHODS THEREOF
A nuclear power reactor may include a plurality of power modules, each including a nuclear fuel and a power conversion system configured to convert heat generated from the nuclear fuel to electricity, where the nuclear fuel of the plurality of power modules collectively forms a reactor core. The nuclear power reactor may also include a sleeve being disposed between the plurality of power modules, where the sleeve has a first end and a second end opposite to the first end. The nuclear power reactor may further include a reactivity booster having a neutron source and a reactivity quencher having a neutron absorber. The reactivity booster may be movable between a first location adjacent the first end of the sleeve and a second location adjacent the reactor core, and the reactivity quencher may be movable between a third location adjacent the second end and the second location adjacent the reactor core.
Load-following nuclear reactor system using thermal expansion-based neutron reflector movement and fuel assembly interval adjustment mechanisms and liquid metal primary coolant
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
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.
CONTROLLING A NUCLEAR REACTION
A nuclear power system includes a reactor vessel that includes a reactor core mounted within a volume of the reactor vessel, the reactor core including one or more nuclear fuel assemblies configured to generate a nuclear fission reaction; a containment vessel sized to enclose the reactor vessel such that an open volume is defined between the containment vessel and the reactor vessel; and a boron injection system positioned in the open volume of the containment vessel and including an amount of boron sufficient to stop the nuclear fission reaction or maintain the nuclear fission reaction at a sub-critical state.
CONTROLLING A NUCLEAR REACTION
A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction; a riser positioned above the reactor core; a primary coolant flow path that extends from a bottom portion of the volume through the reactor core and through an annulus between the riser and the reactor vessel; a primary coolant that circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to generate electric power in a power generation system; and a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.
CONTROLLING A NUCLEAR REACTION
A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction; a riser positioned above the reactor core; a primary coolant flow path that extends from a bottom portion of the volume through the reactor core and through an annulus between the riser and the reactor vessel; a primary coolant that circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to generate electric power in a power generation system; and a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.