Patent classifications
G21D3/00
MACHINE LEARNING IN FUSION REACTORS
A method of controlling a plasma in a nuclear fusion reactor. The nuclear fusion reactor comprises sensors and plasma control inputs. An initial control model is provided, relating readings of at least a subset of the sensors to control of the plasma control inputs. A control loop is performed, comprising: operating the plasma control inputs in dependence upon the sensors according to the control model; determining correlations between readings of each of the sensors, and/or between readings of the sensors and states of the plasma control inputs; and adjusting the control model based on the determined correlations.
Core monitoring system
A core monitoring system including: a TIP measuring a neutron amount in a nuclear reactor; a TIP drive device; a TIP panel; a neutron monitoring panel; and a process computer. The TIP panel includes: a TIP level processor and a TIP position processor that process a TIP level signal and a TIP position signal input from the TIP drive device, respectively; a time setting section synchronizing the TIP level signal and the TIP position signal; and a TIP level data storage section storing synchronized TIP level data. The neutron monitoring panel includes a time setting section setting collecting time of a LPRM level signal and an APRM level signal. The process computer compares the time and stores the TIP level data from the TIP panel and the LPRM and APRM level signals from the neutron monitoring panel corresponding in time, and calculates core performance based on the TIP level data.
Method for regulating operating parameters of a nuclear reactor and corresponding nuclear reactor
A method regulates operating parameters comprising at least the mean temperature of the core (T.sub.m), and the axial power (AO) imbalance. The method includes development of a vector (U.sub.S) of control values of the nuclear reactor by a supervisor (31) implementing a predictive control algorithm; development of a vector (u.sub.K) of corrective values of the nuclear reactor controls by a regulator (33) implementing a sequenced gain control algorithm; development of a vector (U) of corrected values of the commands of the nuclear reactor, by using the vector (U.sub.S) of the values of the commands produced by the supervisor (31) and the vector (u.sub.K) of the corrective values of the commands produced by the regulator (33); and regulation of the operating parameters of the nuclear reactor, by controlling actuators using the vector (U) of the corrected values of the controls.
Method and system for providing fuel in a nuclear reactor
Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.
Method and system for providing fuel in a nuclear reactor
Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.
Method for calculating a PCI margin associated with a loading pattern of a nuclear reactor, associated system, computer program and medium
A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating a reference secondary PCI margin for the reference pattern; calculating a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.
Absolute Technologies Maximizing Cycled Energy
A super plant absolute technologies, comprising an ultra-transport system total energy of displacements embodied in electromagnetic fluids creep stiffness, cycle bulk power ultra-cycling light fluids by cosmological global gravitational dynamics conforming nullities, energy relativity structures, a relativity energy, a minimum energy balancing, a minimal energy displacement and: a reactor to and from steam generators (SGs) primary coolant loops piping, Regions 1; Regions 1, radial inline hot legs from the SG to turbines, condenser units, return to the SGs, cold legs, secondary coolant loops Regions 2; a containment, an annex building Regions 3; cooling water cycling gravitational field, the hydrosphere Regions 4; bulk power electrical distribution Regions 5; and opposing global air warming, effecting Heat Rate maximum efficiencies of the ultra-transport system and Regions 1-5 ultra-longevity boundaries an ultra-fluxing, an ultra-conserving the bulk power, the mega bulk power sustaining a boundaries perfection.
Absolute Technologies Maximizing Cycled Energy
A super plant absolute technologies, comprising an ultra-transport system total energy of displacements embodied in electromagnetic fluids creep stiffness, cycle bulk power ultra-cycling light fluids by cosmological global gravitational dynamics conforming nullities, energy relativity structures, a relativity energy, a minimum energy balancing, a minimal energy displacement and: a reactor to and from steam generators (SGs) primary coolant loops piping, Regions 1; Regions 1, radial inline hot legs from the SG to turbines, condenser units, return to the SGs, cold legs, secondary coolant loops Regions 2; a containment, an annex building Regions 3; cooling water cycling gravitational field, the hydrosphere Regions 4; bulk power electrical distribution Regions 5; and opposing global air warming, effecting Heat Rate maximum efficiencies of the ultra-transport system and Regions 1-5 ultra-longevity boundaries an ultra-fluxing, an ultra-conserving the bulk power, the mega bulk power sustaining a boundaries perfection.
Method and system for the thermoelectric conversion of nuclear reactor generated heat
A method and system for the thermoelectric conversion of nuclear reactor generated heat including upon a nuclear reactor system shutdown event, thermoelectrically converting nuclear reactor generated heat to electrical energy and supplying the electrical energy to a mechanical pump of the nuclear reactor system.
Methods and systems for migrating fuel assemblies in a nuclear fission reactor
Illustrative embodiments provide methods and systems for migrating fuel assemblies in a nuclear fission reactor, methods of operating a nuclear fission traveling wave reactor, methods of controlling a nuclear fission traveling wave reactor, systems for controlling a nuclear fission traveling wave reactor, computer software program products for controlling a nuclear fission traveling wave reactor, and nuclear fission traveling wave reactors with systems for migrating fuel assemblies.