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Induced nuclear reactions: processes, systems, and elements

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Class / Patent application numberDescriptionNumber of patent applications / Date published
376409000 FUEL COMPONENT STRUCTURE 164
376245000 TESTING, SENSING, MEASURING, OR DETECTING A FISSION REACTOR CONDITION 151
376100000 NUCLEAR FUSION 150
376277000 REACTOR PROTECTION OR DAMAGE PREVENTION 149
376260000 HANDLING OF FISSION REACTOR COMPONENT STRUCTURE WITHIN REACTOR SYSTEM 134
376207000 WITH CONTROL OF REACTOR (E.G., CONTROL OF COOLANT FLOW) 116
376347000 REACTOR STRUCTURES 115
376156000 NUCLEAR TRANSMUTATION (E.G., BY MEANS OF PARTICLE OR WAVE ENERGY) 102
376308000 FISSION REACTOR MATERIAL (INCLUDING REACTION PRODUCTS) TREATMENT 33
376327000 CONTROL COMPONENT FOR A FISSION REACTOR 17
376203000 SEAL ARRANGEMENTS 15
376153000 DETECTION OF RADIATION BY AN INDUCED NUCLEAR REACTION 14
376317000 COMBINED 12
376462000 GRIDS 5
20120201343NUCLEAR FUEL ASSEMBLY BODY AND A NUCLEAR FUEL ASSEMBLY WITH SUCH A BODY - A nuclear fuel assembly body with a lengthways axis includes first and second tubular segments made from a metal material forming the lengthways ends of the assembly body. A frame made from a metal material connects the first and second segments. The frame is openworked. A ceramic tubular internal structure is positioned between the first and second segments inside the frame.08-09-2012
20110051883RACK SYSTEMS AND ASSEMBLIES FOR FUEL STORAGE - A rack assembly for nuclear fuel assemblies generally includes a frame assembly and a container assembly including a plurality of individual fuel containers designed to contain individual fuel assemblies, wherein the individual fuel containers are received within and supported by the frame assembly. The rack assembly further includes a shielding assembly including at least one of an inner shielding assembly comprising a substantially continuous shield between the individual fuel containers and an outer shielding assembly comprising a substantially continuous shield around at least a portion of the outer surfaces of the rack assembly. A rack storage system generally includes a plurality of rack assemblies.03-03-2011
20110051882TRUSS-REINFORCED SPACER GRID AND METHOD OF MANUFACTURING THE SAME - A truss-reinforced spacer grid and a method of manufacturing the same are provided, in which truss members having a small diameter are woven to form a truss structure surrounded by an external plate, and the truss structure is joined to the external plate to thereby improve the strength of the mechanical structure. The truss-reinforced spacer grid includes a truss structure in which horizontal trusses formed by horizontally weaving a plurality of truss members are vertically disposed at regular intervals, and an external plate is joined with ends of the horizontal trusses and surrounds the truss structure.03-03-2011
20110075789Module for Forming a Nuclear Fuel Assembly and Corresponding Nuclear Fuel Assembly - A module including a casing extending in a longitudinal direction, a bundle of fuel rods encased in and supported by the casing and connector provided on the casing for connecting the casing side-by-side to the casing of at least one other module to obtain a nuclear fuel assembly having a channel box defined by the casings of the assembled modules and of larger cross-section than the casing of each of the assembled modules and a bundle of fuel rods of larger cross-section than that of each the assembled modules.03-31-2011
20110064185SPACER GRID - The invention relates to a final, ready to use, spacer grid for a nuclear boiling water reactor. The final spacer grid comprises: i) a spacer grid structure made of an alloy that has been formed and assembled such that it constitutes a spacer grid, and ii) an outer oxide coating on the surface of the spacer grid structure. Said alloy is a Ni base alloy that consists of the following: (table) The invention also relates to a method of manufacturing the final spacer grid according to the invention.03-17-2011
376458000 MODERATOR OR REFLECTOR COMPONENT STRUCTURE FOR A FISSION REACTOR 4
20130039454CONTROL ROD - A control rod for a nuclear boiling water reactor is described. The control rod has a longitudinal centre axis and control rod blades, each control rod blade having a first and a second side and being substantially parallel to the longitudinal center axis. Each control rod blade comprises an absorber material which extends from a first absorber end to a second absorber end, the distance between the first absorber end and the second absorber end defining an active length. The control rod blades are provided with distance means on the first and second sides of the control rod blades, the distance means extending a distance of at least a third of the active length of the control rod blade.02-14-2013
20080285702Structure and Method For Bolting Neutron Reflector - A neutron reflector bolt fastening structure is disclosed in which even upon relaxation in the fastening forces thereof being generated in tie rods for divided stage portions as a result of neutron irradiation, it is possible to press the neutron reflector firmly against a core vessel. The neutron reflector bolt fastening structure includes: a neutron reflector which includes of a plurality of divided stage portions and situated in a core vessel in a reactor vessel; a plurality of tie rods for fixing the neutron reflector to the core vessel; and a plurality of bolts for exclusively fixing the lowermost stage portion of the plurality of stage portions of the neutron reflector to the core vessel.11-20-2008
20100067645REFLECTOR SYSTEM OF FAST REACTOR - A reflector system of a fast reactor according to the present invention comprises a reflector having a neutron reflecting portion reflecting a neutron radiated from a reactor core, and a cavity portion provided above the neutron reflecting portion and having a lower neutron reflecting capacity than a coolant, and a reflector drive apparatus coupled to the reflector and moving the reflector in a vertical direction. The reflector drive apparatus has a driving portion which is coupled to the reflector via a drive shaft, and drives the reflector up and down, and a load sensing portion which is provided between the driving portion and the drive shaft, and senses a load of the reflector. A detecting portion receiving a load signal from the load sensing portion so as to detect a breakage of the cavity portion of the reflector is connected to the load sensing portion.03-18-2010
20110096890MODULAR RADIAL NEUTRON REFLECTOR - A lower internals nuclear reactor structure having a tubular core barrel with an upper and lower open end, coaxially supported therein. A reflector having an outside curvature that substantially matches the curvature of the inside surface of the core barrel and substantially contacts the inside surface substantially over an axial length of the core, is fixedly connected to the inside surface of the core barrel at a plurality of axial and circumferential locations to be substantially supported by the inside surface of the core barrel.04-28-2011
376340000 REACTOR STRUCTURES WITH TESTING OR IRRADIATION FACILITIES 3
20130177126SYSTEMS AND METHODS FOR RETAINING AND REMOVING IRRADIATION TARGETS IN A NUCLEAR REACTOR - A retainer is placed on a conduit to control movement of objects within the conduit in access-restricted areas. Retainers can prevent or allow movement in the conduit in a discriminatory fashion. A fork with variable-spacing between prongs can be a retainer and be extended or collapsed with respect to the conduit to change the size of the conduit. Different objects of different sizes may thus react to the fork differently, some passing and some being blocked. Retainers can be installed in inaccessible areas and allow selective movement in remote portions of conduit where users cannot directly interface, including below nuclear reactors. Position detectors can monitor the movement of objects through the conduit remotely as well, permitting engagement of a desired level of restriction and object movement. Retainers are useable in a variety of nuclear power plants and with irradiation target delivery, harvesting, driving, and other remote handling or robotic systems.07-11-2013
20130177125SYSTEMS AND METHODS FOR MANAGING SHARED-PATH INSTRUMENTATION AND IRRADIATION TARGETS IN A NUCLEAR REACTOR - Systems and methods permit discriminate access to nuclear reactors. Systems provide penetration pathways to irradiation target loading and offloading systems, instrumentation systems, and other external systems at desired times, while limiting such access during undesired times. Systems use selection mechanisms that can be strategically positioned for space sharing to connect only desired systems to a reactor. Selection mechanisms include distinct paths, forks, diverters, turntables, and other types of selectors. Management methods with such systems permits use of the nuclear reactor and penetration pathways between different systems and functions, simultaneously and at only distinct desired times. Existing TIP drives and other known instrumentation and plant systems are useable with access management systems and methods, which can be used in any nuclear plant with access restrictions.07-11-2013
20100329411DYNAMIC PORT FOR MEASURING REACTOR COOLANT PUMP BEARING OIL LEVEL - A dynamic port that extends from the bottom wall of an oil reservoir that surrounds the lower guide bearing of a reactor coolant pump and is in fluid communication within an oil level gauge. The dynamic port is rotatable into and out of the oil flow path to adjust the dynamic oil level shown by the oil level gauge when the pump is at operating speed to be substantially equal to the static oil level when the motor is at rest.12-30-2010
376461000 VESSEL SUPPORT (E.G., CORE VESSEL SUPPORTS) 3
20120288054FOUNDATION FOR BUILDING IN NUCLEAR FACILITY AND NUCLEAR FACILITY - To provide a lower foundation 11-15-2012
20090296877NUCLEAR REACTOR ALIGNMENT PLATE CONFIGURATION - An alignment plate that is attached to a core barrel of a pressurized water reactor and fits within slots within a top plate of a lower core shroud and upper core plate to maintain lateral alignment of the reactor internals. The alignment plate is connected to the core barrel through two vertically-spaced dowel pins that extend from the outside surface of the core barrel through a reinforcement pad and into corresponding holes in the alignment plate. Additionally, threaded fasteners are inserted around the perimeter of the reinforcement pad and into the alignment plate to further secure the alignment plate to the core barrel. A fillet weld also is deposited around the perimeter of the reinforcement pad. To accommodate thermal growth between the alignment plate and the core barrel, a gap is left above, below and at both sides of one of the dowel pins in the alignment plate holes through which the dowel pins pass.12-03-2009
20110038450PRESSURE VESSEL SLIDING SUPPORT UNIT AND SYSTEM USING THE SLIDING SUPPORT UNIT - Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.02-17-2011
376273000 SUBTERRANEAN REACTOR STRUCTURES (E.G., UNDERGROUND CONTAINMENT, UNDERGROUND EXPLOSIVE) 2
20090252274SYSTEMS AND METHODS FOR STORING SPENT NUCLEAR FUEL HAVING FLOOD PROTECTION DESIGN - A system and method for storing spent nuclear fuel that affords adequate cooling capabilities under “smart flood” criteria. In one aspect, the invention is a method of storing spent nuclear fuel comprising: providing a system comprising a structure forming a cavity for receiving and storing a spent fuel canister, the cavity having a top, a bottom, and a bottom surface, at least one inlet ventilation duct forming a passageway from an ambient air inlet to an outlet at or near the bottom of the cavity; and at least one outlet ventilation duct forming a passageway from at or near the top of the cavity to ambient air; lowering a canister loaded with spent nuclear fuel into the cavity until a bottom surface of the canister is lower than a top of the outlet of the at least one inlet ventilation duct; supporting the canister in the cavity in a position where the bottom surface of the canister is lower than the top of the outlet of the at least one inlet ventilation duct; and cool air entering the cavity via the at least one ventilation duct; the cool air being warmed by heat emanating from the canister; and warm air exiting the cavity via the at least one ventilation duct. In another aspect, the invention is a system comprising: a structure forming a cavity for receiving and storing a spent fuel canister, the cavity having a top, a bottom, and a bottom surface; at least one inlet ventilation duct forming a passageway from an ambient air inlet to an outlet at or near the bottom of the cavity; at least one outlet ventilation duct forming a passageway from at or near the top of the cavity to ambient air; and means to support a spent fuel canister in the cavity so that the bottom surface of the canister is lower than a top of the outlet; wherein the inlet ventilation duct is shaped so that a line of sight does not exist to a canister supported by the support means from the ambient air inlet.10-08-2009
20100303192SUPERSAFE AND SIMPLY- / EASILY-DECOMMISSIONABLE NUCLEAR POWER PLANT - The invention relates to an inexpensively-/easily-decommissionable nuclear power plant, where a nuclear isle of one or more nuclear power-stations is installed in caverns, and further, side by side with them, a centre for characterising, treating and conditioning radioactive wastes and two repositories are installed in suitable caverns, with a final repository being adapted to store low-intermediate level nuclear wastes and a temporary repository being adapted to store spent fuel, high-level long-life radioactive materials and, in case, spare nuclear rods for reactor refueling.12-02-2010
376346000 EPI-THERMAL REACTOR STRUCTURES (E.G., INTERMEDIATE NEUTRON SPECTRUM) 1
20120106693HIGH Cr FERRITIC/MARTENSITIC STEELS HAVING AN IMPROVED CREEP RESISTANCE FOR IN-CORE COMPONENT MATERIALS IN NUCLEAR REACTOR, AND PREPARATION METHOD THEREOF - Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with to superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR).05-03-2012
376463000 MISCELLANEOUS 1
20100246749NUT ASSEMBLY FOR CONNECTING ADJOINING POLES IN A NUCLEAR REACTOR - A nut assembly for connecting adjoining poles in a nuclear reactor may include an upper nut and a lower nut. The upper nut may include first threads on an inner surface of the upper nut. The lower nut may include second threads on an inner surface of the lower nut. The lower nut may include third threads on an outer surface of the lower nut. The upper nut may rotate over the lower nut in order to lock the lower nut.09-30-2010

Patent applications in class Induced nuclear reactions: processes, systems, and elements

Patent applications in all subclasses Induced nuclear reactions: processes, systems, and elements