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WITH CONTROL OF REACTOR (E.G., CONTROL OF COOLANT FLOW)

Subclass of:

376 - Induced nuclear reactions: processes, systems, and elements

Patent class list (only not empty are listed)

Deeper subclasses:

Class / Patent application numberDescriptionNumber of patent applications / Date published
376219000 By movement of control element or by release of neutron absorbing material 44
376210000 By coolant flow 28
376215000 By electronic signal processing circuitry (e.g., plural redundant circuits) 26
376212000 By altering quantity of characteristic of fuel within critical area 6
376214000 Reactor start-up 3
20100272223Nuclear reactor system and nuclear reactor control method - In order to stably control a nuclear reactor in a short time, so as not to enter an unstable region that is determined by the relationship between the reactor pressure, the reactor power and the subcooling of the core inlet coolant at start-up time, the nuclear reactor system comprises: an power control apparatus for generating a control rod operation signal for operating a control rod, based on the reactor water temperature change rate; a feed water control apparatus for generating a feed water flow rate signal and a discharge water flow rate signals based on the reactor water level signal; and a process computer for performing overall control of the power control apparatus and the feed water control apparatus, wherein the feed water control apparatus has the reactor water temperature change rate setting section for adjusting the reactor water temperature change rate set value based on the variation of the reactor water level signal.10-28-2010
20080247498Methods and apparatuses for operating and repairing nuclear reactors - Method of repairing nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: removing a damaged section of one of the one or more submerged lines; and replacing the damaged section of the one of the one or more submerged lines without welding. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: shutting down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and starting up the nuclear reactor. Methods of operating nuclear reactors that include one or more submerged lines welded to one or more support brackets may include: cooling down the nuclear reactor; repairing damage to at least one of the one or more submerged lines without welding; and heating up the nuclear reactor.10-09-2008
20130182808STABLE STARTUP SYSTEM FOR A NUCLEAR REACTOR - A stable startup system includes a reactor vessel containing coolant, a reactor core submerged in the coolant, and a heat exchanger configured to remove heat from the coolant. The stable startup system further includes one or more heaters configured to add heat to the coolant during a startup operation and prior to the reactor core going critical.07-18-2013
376241000 Power output control (e.g., load follows with steam dump) 2
20130058447NUCLEAR REACTOR POWER MONITOR - Provide a nuclear reactor power monitoring technology for enhancing the monitoring accuracy and reliability in nuclear thermal hydraulic stability.03-07-2013
20100232561Nuclear power generation method and system - A power generation system is disclosed. The power generation system includes a nuclear reactor, a steam turbine, a gas turbine, and a primary generator. The steam turbine is in thermal connection with the nuclear reactor via a transfer medium and converts thermal energy to rotation. The gas turbine converts thermal energy to rotation and is in thermal connection with the transfer medium to increase a thermal energy of the transfer medium. The primary generator is in mechanical connection with the steam turbine to generate power in response to a rotation of a rotor of the primary generator.09-16-2010
376243000 With cooling of control element 1
20100316178COOLING STRUCTURE AND COOLING METHOD FOR CONTROL ROD DRIVE MECHANISM AND NUCLEAR REACTOR - In a cooling structure and a cooling method for a control rod drive mechanism and in a nuclear reactor, a housing (12-16-2010
376244000 Temperature reactivity control 1
20130156142CRITICAL HEAT FLUX PREDICTION DEVICE, CRITICAL HEAT FLUX PREDICTION METHOD AND SAFETY EVALUATION SYSTEM - A critical heat flux prediction device, a critical heat flux prediction method, a safety evaluation system, and a core monitoring system using the safety evaluation system can predict critical heat flux in a core of a reactor with a high degree of accuracy by obtaining a correlation plot distribution representing a relation of critical heat flux on a thermal equilibrium quality based on experimental data, approximating a correlation plot distribution through a logistic function that is a model function in which critical heat flux is expressed by a function of a thermal equilibrium quality, and obtaining a critical heat flux correlation of critical heat flux and a thermal equilibrium quality.06-20-2013
376208000 Pulsed reactors 1
20120020446METHOD 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.01-26-2012
Entries
DocumentTitleDate
20100266084Nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same - A nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same. The fuel assembly comprises an enclosure adapted to enclose a porous nuclear fuel body having the volatile fission product therein. A fluid control subassembly is coupled to the enclosure and adapted to control removal of at least a portion of the volatile fission product from the porous nuclear fuel body. In addition, the fluid control subassembly is capable of circulating a heat removal fluid through the porous nuclear fuel body in order to remove heat generated by the nuclear fuel body.10-21-2010
20090086878Boiling water reactor nuclear power plant with alcohol injection - A nuclear power plant is provided including a BWR, a reactor cooling system cooling the BWR, an HWC hydrogen injection system connected to the reactor cooling system and an alcohol injection system connected to the reactor cooling system. Methods for providing methanol and hydrogen are also provided.04-02-2009
20100150292Controllable long term operation of 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.06-17-2010
20090141847METHOD FOR OPERATING NUCLEAR POWER GENERATION PLANT AND NUCLEAR POWER GENERATION PLANT - An method for operating a nuclear power generation plant, comprising the steps of: 06-04-2009

Patent applications in all subclasses WITH CONTROL OF REACTOR (E.G., CONTROL OF COOLANT FLOW)