Class / Patent application number | Description | Number of patent applications / Date published |
376366000 |
Plural fluids or a fluid in plural phases circulating within reactor (e.g., pressure tube reactors)
| 49 |
376383000 |
Fluid is a gas
| 20 |
376402000 |
Manipulated or used exterior of reactor core
| 19 |
376395000 |
Having specified fluid flow path or pattern within reactor core
| 17 |
376362000 |
Fuel assembly supports
| 11 |
376381000 |
Pebble bed reactor | 2 |
20110142190 | NUCLEAR REACTOR - A nuclear reactor includes a reflector and a flow path. The reflector reflects neutrons, contains graphite and a moderator having a smaller moderating power than the graphite, and is sectioned into plural parts along a direction of flow of fuel pebbles. The flow path is surrounded by the reflector, and the fuel pebbles flow through the flow path and undergo nuclear reaction to generate power. Volume ratio of the graphite to the moderator having a smaller moderating power than the graphite in each part of the reflector is determined based on a power distribution in the reactor core in the direction of flow of the fuel pebbles. | 06-16-2011 |
20110255650 | BI-STABLE NUCLEAR REACTOR - An improved nuclear fission reactor of the liquid metal cooled type including a core configuration allowing for only two operational states, “On” or “Off”, therefore bi-stable. The flow of the primary cooling fluid suspends the core in the “On” state, with sufficient flow to remove the heat to an intermediate heat exchanger during normal operation. This invention utilizes the force of gravity to shut down the reactor after any loss of coolant flow, either a controlled reactor shut down or a “LOCA” event, as the core is controlled via dispersion of fuel elements. Electromagnetic pumps incorporating automatic safety electrical cut-offs are employed to shutdown the primary cooling system to disassemble the core to the “Off” configuration in a situation of a loss of secondary coolant. This design is a hybrid pool-loop unpressurized reactor unique in its use of a minimum number of components, utilizing no moving mechanical parts, no seals, optimized piping, and no control rods, defining an elegantly simple intrinsically safe nuclear reactor. | 10-20-2011 |
Entries |
Document | Title | Date |
20080247499 | Natural Circulation Boiling Water Reactor And Handling Method Thereof - A handling method for a natural circulation boiling water reactor having a chimney having cylindrical chimney shell disposed above a core in a reactor pressure vessel, a plurality of square tubes disposed in the chimney shell, and a grid support plate with grid holes supporting and in communication with a lower end portion of the square tubes so that adjacent square tubes are disposed at an interval which exceeds the width of one square tube between them. The method includes steps shifting predetermined ones of the square tubes to the interval between the square tubes, and performing maintenance and inspection of members around a core via the grid holes which appear at positions from which the predetermined square tubes are taken out due to the shift of the predetermined square tubes. | 10-09-2008 |
20090154636 | Chemical injection system and chemical delivery process/method of injecting into an operating power reactor - An injection system designed to deliver a chemical solution into a reactor through feedwater system taps during normal operating condition of a power reactor is disclosed. The process of delivery is via positive displacement pumps. Injection of chemical is in a concentrated solution form, which is internally diluted by the system prior to discharging from the skid. The injection system minimizes chemical loss due to deposition on the transit line, enables a higher concentrated solution to be used as the injectant, eliminates the time consuming laborious process of chemical dilution, raises chemical solution to the pressure required for injection, prevents solid precipitations out of solution at the injection pump head through the use of a flush solution, and deposits fresh chemical on new crack surfaces that develop during a power reactor start-up, shutdown and operation. | 06-18-2009 |
20090252276 | Jet Pump and Nuclear Reactor - A jet pump comprising:
| 10-08-2009 |
20100091931 | REACTOR COOLANT PUMP FLYWHEEL - A flywheel for a pump, and in particular a flywheel having a number of high density segments for use in a nuclear reactor coolant pump. The flywheel includes an inner member and an outer member. A number of high density segments are provided between the inner and outer members. The high density segments may be formed from a tungsten based alloy. A preselected gap is provided between each of the number of high density segments. The gap accommodates thermal expansion of each of the number of segments and resists the hoop stress effect/keystoning of the segments. | 04-15-2010 |
20100183113 | JET PUMP AND REACTOR - A jet pump has a plurality of nozzles installed to a nozzle base, a throat and a diffuser. A first nozzle straight-tube portion, a first nozzle narrowing portion, a second nozzle straight-tube portion, a second nozzle narrowing portion, and a nozzle lower end portion formed in those nozzles are disposed in this order from the nozzle base to a ejection outlet. A narrowing angle of the second nozzle narrowing portion is larger than of the first nozzle narrowing portion. The jet pump forms, in a lower end portion of the throat, a flow passage narrowing portion having a flow passage cross-sectional area that gradually diminishes. This flow passage narrowing portion is inserted into an upper end portion of the diffuser. | 07-22-2010 |
20100290578 | DEPLOYABLE ELECTRIC ENERGY REACTOR - A nuclear fission reactor device including a core having an array of fissile material and which is capable of being transported to and from the place of operation using conventional transportation vehicles. In a first embodiment, the fissile material is a uranium hydride enriched 15%-to-20% with U-235. In a second embodiment, the fissile material is a uranium oxide enriched to 18% to 20% with U-235. | 11-18-2010 |
20110211663 | RADIATION EXPOSURE REDUCTION METHOD - A radiation exposure reduction method includes the steps of: injecting iron into a coolant which flows from the reactor cooling system to the reactor core in a nuclear power plant; and ferritizing and fixing radionuclides or parent nuclides thereof, which are contained in the coolant, on the surface of a reactor core structure, wherein an iron citrate which is soluble organic iron, or iron oxalate or iron fumarate which has a particle diameter of 3 μm or less, is used as the iron to be injected into the coolant. | 09-01-2011 |
20120321030 | INTEGRATED EMERGENCY CORE COOLING SYSTEM CONDENSER FOR PRESSURIZED WATER REACTOR - A pressurized water nuclear reactor (PWR) includes a pressure vessel having a lower portion containing a nuclear reactor core comprising a fissile material and an upper portion defining an internal pressurizer volume. A condenser is secured to, and optionally supported by, the upper portion of the pressure vessel. A condenser inlet is in fluid communication with the internal pressurizer volume. A heat sink is in fluid communication with the condenser such that the condenser operates as a passive heat exchanger to condense steam from the internal pressurizer volume into condensate while rejecting heat to the heat sink. A condenser outlet connects with the pressure vessel to return condensate to the pressure vessel. A single metal forging having a first end welded to the pressure vessel and a second end welded to the condenser inlet may provide the fluid communication between the condenser inlet and the internal pressurizer volume. | 12-20-2012 |
20130044852 | TREATMENT OF A HEATER TUBE INTENDED FOR A PRESSURIZER OF THE PRIMARY COOLING SYSTEM OF A NUCLEAR REACTOR - A treatment of a heater tube intended to be used in a pressurizer of the primary cooling system of a nuclear reactor. In particular, the heater tube comprises a heater housed in a substantially cylindrical sheath. The material of which this sheath is made is a work-hardened austenitic stainless steel. In particular, the external surface of the sheath is liable to undergo a stress corrosion during use of the heatertube. The method includes a heat treatment step, preferably using induction heating, in which the external surface of the sheath is heat-treated so as to recrystallize the material of the sheath at least on the surface thereof. | 02-21-2013 |
20130070889 | DOUBLE-WALLED TUBE WITH INTERFACE GAP AND PRODUCTION METHOD THEREFOR - After an inner wall tube, made of steel or alloy containing not less than 2% of Cr, whose outer surface thereof is machined and/or ground to a thickness of 0.1 mm or more including the scale layer, is inserted into an outer wall tube, made of ferritic steel containing not less than 2% of Cr, in which an oxide scale layer containing Cr and having a thickness of 10 to 30 μm is formed in the inner surface thereof , cold working at an outside diameter reduction rate of 5 to 30% is performed. Similarly cold worked after an inner wall tube having an oxide scale layer on the outer surface thereof, is inserted into an outer wall tube whose inner surface is machined and ground. A double-walled tube made has a uniform gap and an excellent thermal conductivity, and is suitable as materials for SG tubes of future FBR. | 03-21-2013 |
20130108005 | PRESSURIZED WATER REACTOR WITH UPPER VESSEL SECTION PROVIDING BOTH PRESSURE AND FLOW CONTROL | 05-02-2013 |
20130343505 | PRESSURIZED WATER REACTOR - The pressurized water reactor according an embodiment comprises: a cylindrical reactor pressure vessel ( | 12-26-2013 |
20140064432 | PARTICULATE METAL FUELS USED IN POWER GENERATION, RECYCLING SYSTEMS, AND SMALL MODULAR REACTORS - A metal particulate fuel system is described. The metal fuel system may include particulate metal fuel for use in nuclear reactors. The particulate metal fuel may include a plurality of particles of at least one enriched alloy where the particles are compacted into a fuel column. The metal particulate fuel system may also include a cladding and/or a gas-filled plenum. | 03-06-2014 |
20140348287 | Dual Fluid Reactor - The present invention describes a nuclear reactor with a loop for liquid nuclear fuel, which, contrary to similar systems like the Molten-Salt Reactor of the Generation-IV canon, does not use the fuel loop for the heat transport at the same time. Instead, cooling is provided by an additional coolant loop, which is intensively coupled to the nuclear fuel duct for heat transport. That way, the advantages of liquid fuel can be utilized while optimizing the coolant loop performance, so the complexity of safety systems can be reduced significantly. This reactor design further includes an optimized neutron economy and is able to deactivate long-lived fission products generated by its own, so only short-lived radiotoxic waste has to be stored. With the neutron surplus it is also possible to deactivate long-lived radiotoxic waste from used fuel of today's light water reactors or to produce medical radioisotopes. | 11-27-2014 |
20150348654 | Organically Cooled Nuclear Reactor for Enhanced Economics and Safety - An organically cooled nuclear reactor comprises fissionable fuel pellets and a neutron-moderator matrix in which the fissionable fuel pellets are distributed. The neutron-moderator matrix also defines coolant channels for flow of an organic coolant. | 12-03-2015 |
20160064107 | NUCLEAR POWER GENERATION SYSTEM - Disclosed is a nuclear power generation system that may secure safety even in a case where a failure occurs in a system due to natural disasters or component malfunction. | 03-03-2016 |