| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376219000 |
By movement of control element or by release of neutron absorbing material
| 83 |
| 376215000 |
By electronic signal processing circuitry (e.g., plural redundant circuits)
| 38 |
| 376210000 |
By coolant flow
| 36 |
| 376212000 |
By altering quantity of characteristic of fuel within critical area
| 11 |
| 376214000 |
Reactor start-up | 5 |
| 20080247498 | Methods 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 |
| 20100272223 | Nuclear 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 |
| 20130182808 | STABLE 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 |
| 20140098921 | METHODS 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. | 04-10-2014 |
| 20160148709 | STABLE STARTUP SYSTEM FOR 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. | 05-26-2016 |
| 376241000 |
Power output control (e.g., load follows with steam dump) | 5 |
| 20100232561 | Nuclear 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 |
| 20130058447 | NUCLEAR 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 |
| 20140254736 | METHOD FOR PRODUCING, FROM A PREFORM MADE OF AUSTENITIC STAINLESS STEEL WITH A LOW CARBON CONTENT, A WEAR-RESISTANT AND CORROSION-RESISTANT CLADDING FOR A NUCLEAR REACTOR, CORRESPONDING CLADDING AND CORRESPONDING CONTROL CLUSTER - A method for producing a wear-resistant and corrosion-resistant stainless steel part for a nuclear reactor is provided. This method includes steps of providing a tubular blank in austenitic stainless steel whose carbon content is equal to or lower than 0.03% by weight; shaping the blank; finishing the blank to form the cladding; hardening the outer surface of the cladding by diffusing one or more atomic species; the blank, before the providing step or during the shaping or finishing step, being subjected to at least one solution annealing with sub-steps of: heating the blank to a sufficient temperature and for a sufficient time to solubilise any precipitates present; quenching the blank at a rate allowing the austenitic structure to be maintained in a metastable state at ambient temperature and free of precipitates. | 09-11-2014 |
| 20150016581 | SYSTEM FOR REMOVING THE RESIDUAL POWER OF A PRESSURISED WATER NUCLEAR REACTOR - A system for discharging the residual power of a nuclear reactor includes: a containment vessel incorporating a primary vessel including the core; a water reserve; a steam source wherein the heated primary water circulates and heats the secondary water circulating in the steam source; a condenser in the containment vessel including: a recovery unit; a condenser link linked to an intermediate water circuit and ensuring the circulation of the intermediate water between the water reserve and the condenser; a hot link ensuring the circulation of the steam to the condenser; a cold link ensuring the circulation, by gravity, of the water from the recovery unit to the secondary water inlet of the steam source; a heat recovery unit on the intermediate water circuit, the heat recovery unit being traversed by a feed water circuit, the feed water capable of heating up by thermal contact with the intermediate water circulating through the heat recovery unit. | 01-15-2015 |
| 20150146836 | NUCLEAR REACTOR POWER REGULATOR - A reactor power regulator that adjusts an output of a reactor on a basis of an operation pattern or a reactor output target value and a reactor output change rate that are input by a central load dispatching center or an operator, including: a reactor output calculating device that performs computation based on a thermal equilibrium from various necessary plant state quantities to calculate a reactor output signal; a correcting device that corrects a continuously obtained reactor output equivalent signal that is considered to be equivalent to a reactor output at a calculation interval of the reactor output signal, for each calculation interval in the reactor output calculating device so that the reactor output equivalent signal coincides with the reactor output signal calculated by the reactor output calculating device, and calculates a continuous corrected reactor output equivalent signal; a reactor output controlling device that calculates at least one type of reactor output control signal for controlling the output of the reactor, using the corrected reactor output equivalent signal, the reactor output target value, and the reactor output change rate; and a reactor output controller that is actuated on a basis of the reactor output control signal. | 05-28-2015 |
| 376244000 |
Temperature reactivity control | 3 |
| 20130156142 | CRITICAL 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 |
| 20150092901 | OPERATING A NUCLEAR REACTOR USING A DEPOSIT MODEL OF A NUCLEAR REACTOR HEAT TRANSFER SURFACE - A method of operating a nuclear reactor is provided. The method includes defining a layer increment of a deposit layer modeling a deposit on a heat transfer surface of the nuclear reactor; periodically updating a thickness of the deposit layer by adding the layer increment to the deposit layer; recalculating properties of the deposit layer after each layer increment is added to the deposit layer; determining a temperature related variable of the heat transfer surface as a function of the recalculated properties of the deposit layer; and altering operation of the nuclear reactor when the temperature related variable of the heat transfer surface reaches a predetermined value. A method of modeling a deposit on a heat transfer surface of a nuclear reactor is also provided. | 04-02-2015 |
| 20160064105 | DOPPLER REACTIVITY AUGMENTATION DEVICE - A fast neutron nuclear reactor contains a nuclear reactor core having an array of device locations. Some device locations in the nuclear reactor core contain fissile and fertile nuclear fuel assembly devices. One or more other device locations in the nuclear reactor core contain Doppler reactivity augmentation devices that amplify the negativity of the Doppler reactivity coefficient within the nuclear reactor core. In some implementations, a Doppler reactivity augmentation device can also reduce the coolant temperature coefficient within the nuclear reactor core. Accordingly, a Doppler reactivity augmentation device contributes to a more stable nuclear reactor core. | 03-03-2016 |
| 376208000 |
Pulsed reactors | 1 |
| 20120020446 | 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. | 01-26-2012 |
| 376243000 |
With cooling of control element | 1 |
| 20100316178 | COOLING 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 |
| Entries |
| Document | Title | Date |
|---|
| 20090086878 | Boiling 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 |
| 20090141847 | METHOD 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 |
| 20100150292 | Controllable 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 |
| 20100266084 | 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 - 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 |
| 20140133618 | CONTROL ROOM FOR NUCLEAR POWER PLANT - A control room for a nuclear power plant including two or more nuclear reactor units includes a central workstation providing monitoring capability for both nuclear reactor units, a first operator at the controls (OATC) workstation in front of and to one side of the central workstation providing monitoring and control capabilities for the first nuclear reactor unit, a second OATC workstation in front of and to the other side of the central workstation providing monitoring and control capabilities for the second nuclear reactor unit, and a common control workstation directly in front of the central workstation providing monitoring and control capabilities for systems serving both the first nuclear reactor unit and the second nuclear reactor unit. The central and common control workstations do not provide control capabilities for either nuclear reactor unit. The common control workstation does not include any control capabilities that must be performed by a licensed operator. | 05-15-2014 |
| 20150036779 | INTEGRAL MOLTEN SALT REACTOR - The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel. | 02-05-2015 |
| 20150103967 | Steam Generator for a Nuclear Reactor - A steam generator for a nuclear reactor comprises plenums proximate with a first plane, wherein the first plane intersects a bottom portion of a riser column of a reactor vessel. The steam generator may further comprise plenums proximate with a second plane, approximately parallel with the first plane, wherein the second plane intersects a top portion of the riser column of the reactor vessel. The steam generator may further include a plurality of steam generator tubes that convey coolant from a plenum located proximate with the first plane to one of the plenums proximate with the second plane. | 04-16-2015 |
| 20160070009 | DEVICE FOR PROCESSING SIGNALS DETECTED BY NEUTRON DETECTORS AND ASSOCIATED CONTROL/COMMAND DEVICE - A device for processing signals detected by a set of n neutron detectors, the device including: n switches each including an input and an output, each switch receiving, on its input, a detected signal coming from a different detector, outputs of the n switches being linked to each other; and a clock generator including a clock circuit and a sequential counter controlled by the clock circuit and configured to deliver a plurality of pulse series, each pulse series of the plurality of pulse series constituting a control signal of a different switch, the pulses of any two pulse series of the plurality of pulse series being disjointed. | 03-10-2016 |
