Patent classifications
G21C7/26
CLOSED-VESSEL MOLTEN SALT FISSION REACTOR
A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.
NUCLEAR REACTOR AND OPERATION METHOD FOR NUCLEAR REACTOR
A nuclear reactor comprising: a moderator including a metal hydride; and a nuclear fuel in which europium is added as an additive to a main nuclear fuel material. Thus, the nuclear reactor can be kept in the subcritical state even under the state where all the control devices are pulled out before startup.
NUCLEAR REACTOR AND OPERATION METHOD FOR NUCLEAR REACTOR
A nuclear reactor comprising: a moderator including a metal hydride; and a nuclear fuel in which europium is added as an additive to a main nuclear fuel material. Thus, the nuclear reactor can be kept in the subcritical state even under the state where all the control devices are pulled out before startup.
Magneto-Rheological Nuclear Reactivity Distribution Control Elements
A stationary control rod that controls overall nuclear reactivity and axial reactivity distribution of a fuel assembly, such that power level and axial power distribution within the fuel assembly is controlled without the need for movable control rods and associated hardware. The device uses magnetic fields to control the concentration and distribution of a magneto-rheological fluid containing a material with a very high neutron capture cross section, contained in one or more enclosed thimbles placed within existing thimbles in a fuel assembly. The magnetic fields are generated from electricity produced from interactions of the radiation particles within the core, or supplied using electrical cables that attach to fuel assembly top nozzles. The electricity drives a device that encloses associated wire coil assemblies that surround different axial regions of a tube that contains the magneto-rheological fluid.
Magneto-Rheological Nuclear Reactivity Distribution Control Elements
A stationary control rod that controls overall nuclear reactivity and axial reactivity distribution of a fuel assembly, such that power level and axial power distribution within the fuel assembly is controlled without the need for movable control rods and associated hardware. The device uses magnetic fields to control the concentration and distribution of a magneto-rheological fluid containing a material with a very high neutron capture cross section, contained in one or more enclosed thimbles placed within existing thimbles in a fuel assembly. The magnetic fields are generated from electricity produced from interactions of the radiation particles within the core, or supplied using electrical cables that attach to fuel assembly top nozzles. The electricity drives a device that encloses associated wire coil assemblies that surround different axial regions of a tube that contains the magneto-rheological fluid.
Automated In-Vessel Neutron Flux Detector System Embedded in Control Drum Assembly
A measurement device for determining a power level of a nuclear reactor core is provided, the measurement device comprising an in-vessel detector assembly. The in-vessel detector assembly comprises a rotatable housing defining a cavity therein and a detector element positioned in a first angular portion of the cavity of the housing. A control drum for a nuclear reactor core and a system for monitoring a power level of a nuclear reactor are also provided.
Automated In-Vessel Neutron Flux Detector System Embedded in Control Drum Assembly
A measurement device for determining a power level of a nuclear reactor core is provided, the measurement device comprising an in-vessel detector assembly. The in-vessel detector assembly comprises a rotatable housing defining a cavity therein and a detector element positioned in a first angular portion of the cavity of the housing. A control drum for a nuclear reactor core and a system for monitoring a power level of a nuclear reactor are also provided.
Nuclear Reactor and Operation Method for Nuclear Reactor
A nuclear reactor comprising: a moderator including a metal hydride; and a nuclear fuel in which europium is added as an additive to a main nuclear fuel material. Thus, the nuclear reactor can be kept in the subcritical state even under the state where all the control devices are pulled out before startup.
Nuclear Reactor and Operation Method for Nuclear Reactor
A nuclear reactor comprising: a moderator including a metal hydride; and a nuclear fuel in which europium is added as an additive to a main nuclear fuel material. Thus, the nuclear reactor can be kept in the subcritical state even under the state where all the control devices are pulled out before startup.
Method and apparatus for real-time learning-based augmented irradiation control and optimization
A machine-learning tool learns from sensors' data of a nuclear reactor at steady state and maps them to controls of the nuclear reactor. The tool learns all given ranges of normal operation and responses for corrective measures. The tool may train another learning tool (or the same tool) that forecasts the behavior of the reactor based on real-time changes (e.g., every 10 seconds). The tool implements an optimization technique for differing half-life materials to be placed in the reactor. The tool maximizes isotope production based on optimal controls of the reactor.