236415 ⎘
Energy generation of nuclear origin Nuclear fission reactors
Wireless transmission of nuclear instrumentation signals
#902Increased efficiency strainer system
#903Increased efficiency strainer system
#904Fuel bundle designs using mixed spacer types
#905MANUFACTURING METHOD OF NUCLEAR FUEL PELLET, FUEL ASSEMBLY FOR NUCLEAR REACTOR AND MANUFACTURING METHOD THEREOF AND URANIUM POWDER
#906Module for forming a nuclear fuel assembly and corresponding nuclear fuel assembly
#907Heat exchanger, methods therefor and a nuclear fission reactor system
#908Heat exchanger, methods therefor and a nuclear fission reactor system
#909Heat exchanger, methods therefor and a nuclear fission reactor system
#910Method of operating nuclear plant
#911Nuclear fuel cell repair tool
#912Jet Pump Slip Joint Modification for Vibration Reduction
#913Movement of materials in a nuclear reactor
#914Control rod drive outer filter removal tool
#915Nuclear reactor operation and simulation
#916Spacer grid
#917Unit spacer grid strap, unit spacer grid, and spacer grid for nuclear fuel rods
#918Methods for stabilizing a steam dryer assembly in a nuclear reactor pressure vessel
#919Control rod for boiling water reactor
#920Neutron monitoring systems including gamma thermometers and methods of calibrating nuclear instruments using gamma thermometers
#921Method of handling control rod and control rod handling apparatus
#922Diversity and defense-in-depth simulation apparatus
#923Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
#924Method of and an apparatus for monitoring the operation of a nuclear reactor
#925Ni-Cr alloy material
#926RACK SYSTEMS AND ASSEMBLIES FOR FUEL STORAGE
#927Truss-reinforced spacer grid and method of manufacturing the same
#928Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
#929High Efficiency Power Plants
#930Debris mitigation upper tie plates and fuel bundles using the same
#931Method for managing internal equipment in reactor pressure vessel and apparatus thereof
#932Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
#933Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
#934Cable driven isotope delivery system
#935Irradiation target retention assemblies for isotope delivery systems
#936Method for preparing sintered annular nuclear fuel pellet
#937Computer implemented method for modelizing a nuclear reactor core and a corresponding computer program product
#938Computer Implemeneted Method for Modelizing a Nuclear Reactor Core and a Corresponding Computer Program Product
#939Computer implemented method for modelizing a nuclear reactor core and a corresponding computer program product
#940DCS control module for a transformer in nuclear power engineering
#941Method of controlling turbine equipment and turbine equipment
#942Computer implemented method for modelizing a nuclear reactor core and a corresponding computer program product
#943END OF EINSTEIN-BOHR AND MECHANISMS OF NUCLEAR FORCES: FACILITATED FUSION AND FISSION
#944Construction of nuclear power plant building and construction method thereof
#945Pressure vessel sliding support unit and system using the sliding support unit
#946Suspension type high-density storage rack for nuclear fuel assemblies
#947Decontamination of radioactive liquid effluent by solid-liquid extraction using a recycle loop
#948Helically fluted tubular fuel rod support
#949Single-plate neutron absorbing apparatus and method of manufacturing the same
#950Suppression method for corrosion of carbon steel member
#951Inspecting device including detachable probe
#952Computer implemented method for modelizing a nuclear reactor core and a corresponding computer program product
#953Method for selecting and disposing remaining spent nuclear fuel bundles for casks
#954Instrument removal system
#955Detecting pin diversion from pressurized water reactors spent fuel assemblies
#956Digital nuclear control rod control system
#957Control loop for a power plant
#958MsS PROBE FOR GUIDED-WAVE INSPECTION OF FUEL RODS
#959Compositions and methods for treating nuclear fuel
#960Electrical heating element and method of measuring a filling level
#961Advanced fuel CRUD sampling tool method
#962Method for recovery of residual actinide elements from chloride molten salt
#963Special nuclear material simulation device
#964Method of Searching for Positions to Place Control Rods with Crack in a Boiling Water Reactor Core
#965Corrosion resistant neutron absorbing coatings
#966METHOD AND APPARATUS FOR DETERMINING THE DEFORMATION OF A FUEL ASSEMBLY OF A PRESSURIZED WATER REACTOR
#967Machinery system allowing replacement of old reactor with a new reactor in nuclear power electric generating station
#968MOISTURE SEPARATOR REHEATER
#969Method for estimating the concentration of a chemical element in the primary coolant of a nuclear reactor
#970Pooled separation of actinides from a highly acidic aqueous phase using a solvating extractant in a salting-out medium
#971Nuclear fuel assembly support grid
#972NUCLEAR FUEL ASSEMBLY SUPPORT GRID
#973Nuclear fuel cladding having an exterior comprising burnable poison in contact with aqueous reactor coolant
#974Water reactor fuel cladding tube
#975INCORE INSTRUMENT CORE PERFORMANCE VERIFICATION METHOD
#976Container for nuclear fuel transportation
#977System for dampening vibration
#978Basket and pH adjusting device
#979Drain sump of nuclear reactor containment vessel
#980Systems, Apparatuses and Methods of Gripping, Cutting and Removing Objects
#981Method for Repairing Primary Nozzle Welds
#982Method of manufacture of noble metal/zinc oxide hybrid product for simultaneous dose reduction and SCC mitigation of nuclear power plants
#983OPTIMIZED FLOWER TUBES AND OPTIMIZED ADVANCED GRID CONFIGURATIONS
#984PROCESS OF MANUFACTURING ZIRCONIUM ALLOY FOR FUEL GUIDE TUBE AND MEASURING TUBE HAVING HIGH STRENGTH AND EXCELLENT CORROSION RESISTANCE
#985LIQUID COOLED NUCLEAR REACTOR WITH ANNULAR STEAM GENERATOR
#986Enhanced steam dump (bypass) control system
#987Method for separating and recycling uranium and fluorine form solution
#988Integral helical coil pressurized water nuclear reactor
#989Jet pump riser brace clamp
#990Control rod blade extension for a nordic nuclear reactor
#991Cooling structure and cooling method for control rod drive mechanism and nuclear reactor
#992Control rod drive mechanism for nuclear reactor
#993METHOD FOR PROCESSING NUCLEAR FUELS CONTAINING SILICON CARBIDE AND FOR DECLADDING NUCLEAR FUEL PARTICLES
#994Use of butyraldehyde oxime as an anti-nitrous agent in an operation for the reductive stripping of plutonium
#995Nuclear fuel assembly protective bottom grid
#996Method to process fission chamber measurement signals
#997METHOD FOR FILLING THE MAIN PRIMARY COOLANT SYSTEM OF A NUCLEAR POWER PLANT WITH WATER AND FOR DRAINING IT OF AIR, AND HEAD FOR IMPLEMENTING THIS METHOD
#998Process for Converting Alkaline-Earth Metal Chlorides to Tungstates and Molybdates and Applications Thereof
#999Systems and methods for reducing the storage time of spent nuclear fuel
#1000NUCLEAR FUEL ARRANGEMENT IN FUEL POOLS FOR NUCLEAR POWER PLANT
#1001Particulate metal fuels used in power generation, recycling systems, and small modular reactors
#1002Supersafe and simply-/easily-decommissionable nuclear power plant
#1003DRY STORAGE OF SPENT NUCLEAR FUEL
#1004Method of producing mixed in-core maps and application to the calibration of fixed instrumentation
#1005Device for inspecting a fuel rod assembly in the pool of a nuclear plant and corresponding inspection method
#1006Apparatus and method for searching eddy current of electric heat tube using measuring magnetic permeability in steam generator
#1007In Situ Pipe Repair Controller and System
#1008PREPARATION OF NUCLEAR FUEL COMPOSITION AND RECYCLING
#1009Process for Treating Spent Nuclear Fuel
#1010DISPERSANT APPLICATION FOR CLEAN-UP OF RECIRCULATION PATHS OF A POWER PRODUCING FACILITY DURING START-UP
#1011Method of manufacturing nuclear fuel elements and a container for implementing such a method
#1012High power density liquid-cooled pebble-channel nuclear reactor
#1013Safety system for a nuclear plant and nuclear plant with a safety system
#1014Expansion gap radiation shield
#1015Inspection, maintenance, repair, and operating methods for nuclear reactors
#1016REFLECTOR GRAPHITE CONSISTING OF ISOTROPIC HIGHLY CRYSTALLINE NATURAL GRAPHITE AS THE MAIN COMPONENT AND SILICON OR ZIRCONIUM CARBIDE, AND PRODUCTION THEREOF
#1017Nuclear reactor, in particular pool-type nuclear reactor, with new-concept fuel elements
#1018DEPLOYABLE ELECTRIC ENERGY REACTOR
#1019Nuclear reactor having efficient and highly stable thermal transfer fluid
#1020Boiling water reactor
#1021PARTICLE BEAM ISOTOPE GENERATOR APPARATUS, SYSTEM AND METHOD
#1022Particle beam source apparatus, system and method
#1023HEAD SPRAY SYSTEM OF REACTOR PRESSURE VESSEL
#1024Nuclear reactor
#1025Apparatus for storing and/or transporting high level radioactive waste, and method for manufacturing the same
#1026Method and apparatus for annulus spacer detection and repositioning in nuclear reactors
#1027DEVICE AND APPARATUS FOR MEASURING THE ENRICHMENT PROFILE OF A NUCLEAR FUEL ROD
#1028Radioisotope production structures, fuel assemblies having the same, and methods of using the same
#1029Visual inspection apparatus and visual inspection method
#1030In-situ bwr and pwr CRUD flake analysis method and tool
#1031Two step dry UOproduction process utilizing a positive sealing valve means between steps
#1032Emergency core cooling duct for emergency core cooling water injection of a nuclear reactor
#1033TUBE SUPPORT STRUCTURE
#1034Feedwater debris trap
#1035Non-destructive pipe scanner
#1036Boiling water nuclear reactor and emergency core cooling system of the same
#1037Fuel transfer system
#1038Nuclear reactor system and nuclear reactor control method
#1039Method for surface processing a zirconium or hafnium alloy, and component processed in this manner
#1040Burnable poison materials and apparatuses for nuclear reactors and methods of using the same
#1041Dual-cooled nuclear fuel rod having annular plugs and method of manufacturing the same
#1042Methods and apparatuses for clamping a jet pump sensing line support
#1043Nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product
#1044Nuclear 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
#1045Nuclear 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
#1046Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system
#1047Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system
#1048Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system
#1049Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system
#1050Nuclear 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
#1051Nuclear plant
#1052Method, system, and apparatus for selectively transferring thermoelectrically generated electric power to nuclear reactor operation systems
#1053Method, system, and apparatus for selectively transferring thermoelectrically generated electric power to nuclear reactor operation systems
#1054Method and system for the thermoelectric conversion of nuclear reactor generated heat
#1055Method, system, and apparatus for the thermoelectric conversion of gas cooled nuclear reactor generated heat
#1056Method and system for the thermoelectric conversion of nuclear reactor generated heat
#1057NUCLEAR REACTOR WITH IMPROVED COOLING IN AN ACCIDENT SITUATION
#1058Method for predicting stresses on a steam system of a boiling water reactor
#1059Method of determining the value of a parameter representative of the operability of a nuclear reactor, determining system, computer and corresponding medium
#1060Apparatus and method for removing a dry tube assembly from a nuclear reactor pressure vessel
#1061EVALUATING METHOD FOR INTEGRITY OF VIBRATION OF STEAM DRYER AND TEST DEVICE STEAM DRYER
#1062Method for manufacturing sintered annular nuclear fuel pellet without surface grinding
#1063Long-term storage site for radioactive materials
#1064Methods and apparatuses for operating nuclear reactors and for determining power levels in the nuclear reactors
#1065Power Monitoring System
#1066Apparatus and systems for measuring elongation of objects, methods of measuring, and reactor
#1067Traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein
#1068Traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein
#1069Nut assembly for connecting adjoining poles in a nuclear reactor
#1070Nuclear fuel assembly with pivot dimpled grids
#1071Nuclear fuel rod spacer grid and framework and assembly comprising such a grid
#1072Process for adding an organic compound to coolant water in a pressurized water reactor
#1073Methods for operating and methods for reducing post-shutdown radiation levels of nuclear reactors
#1074Apparatus and system for dampening the vibration experienced by an object
#1075STEAM FLOW VORTEX STRAIGHTENER
#1076System for assembling or disassembling a segmented rod
#1077NUCLEAR-PLANT SAFETY SYSTEM OPERATING DEVICE
#1078Manipulator for remote activities in a nuclear reactor vessel
#1079Method and apparatus for jet pump restrainer assembly repair
#1080Telescoping tool assembly and method for refurbishing welds of a core shroud of a nuclear reactor vessel
#1081Coolant with dispersed neutron poison micro-particles, used in SCWR emergency core cooling system
#1082REACTOR CONTAINMENT VESSEL AND WATER LEAK DETECTION FLOOR
#1083REFLECTOR-CONTROLLED FAST REACTOR
#1084Systems for aligning and handling fuel rods within a nuclear fuel bundle
#1085Apparatus and method for supporting fuel assemblies in an underwater environment having lateral access loading
#1086Working device and working method
#1087PH adjusting system and PH adjusting method
#1088pH adjusting apparatus
#1089System and method for detecting position of underwater vehicle
#1090NUCLEAR FUEL ELEMENT AND ASSEMBLY
#1091SYSTEM FOR EVACUATING THE RESIDUAL HEAT FROM A LIQUID METAL OR MOLTEN SALTS COOLED NUCLEAR REACTOR
#1092Direct vessel injection (DVI) nozzle for minimum emergency core cooling (ECC) water bypass
#1093ATOMIC REACTOR WATER SUPPLY PIPING STRUCTURE AND ULTRASONIC FLOWMETER SYSTEM
#1094METHOD FOR DETERMINING AN UNCERTAINTY COMPONENT RELATING TO POWER DISTRIBUTION IN A NUCLEAR REACTOR CORE
#1095Moderator temperature coefficient measurement apparatus
#1096Axial power distribution control method, axial power distribution control system and axial power distribution control program
#1097Control rod guide tube and method for providing coolant to a nuclear reactor fuel assembly
#1098Electrochemically Modulated Separations for In-line and At-line Monitoring of Actinides in High-Volume Process Streams
#1099Steam generator
#1100Method and apparatus for dehydrating high level waste based on dew point temperature measurements
#1101Device for supporting nuclear fuel plate for a fissile bundle of a nuclear reactor of GFR type with high-temperature heat transfer gas
#1102Method and system for providing fuel in a nuclear reactor
#1103GC QCMEHC nuclear power plants
#1104Method for selecting a loading map for a nuclear reactor core, corresponding selection system, computer program and storage medium
#1105Laser-based maintenance apparatus using ultrasonic wave detection for flaw analysis and repair
#1106Electrochemical corrosion potential sensor
#1107TUBE CUTTING DEVICE AND METHOD THEREOF
#1108METHOD OF REMOVING RETAINER OF JET PUMP AND JET PUMP
#1109Cleaning apparatus
#1110Posture control method and posture control device
#1111Purification of metals
#1112System and method for storing energy in a nuclear power plant
#1113VIBRATION EVALUATION APPARATUS AND VIBRATION EVALUATION METHOD
#1114Laser ultrasonic detection device including a laser oscillating device which includes a seed laser oscillating element
#1115Laser-based maintenance apparatus for inspecting flaws
#1116Solute precipitation method and device
#1117Automated cleaning equipment and method for the nuclear fuel-cladding tube
#1118Temperature Detection Apparatus For Natural Circulation Boiling Water Reactor
#1119CLOSED-CYCLE PLANT
#1120Apparatus for repairing a damaged area in an underwater wall region of a vessel or pool
#1121Jet pump and reactor
#1122Method of manufacturing core shroud for nuclear power plant and structure of nuclear power plant
#1123Ex-vessel accident mitigation
#1124Safety valve drive system
#1125Fully passive decay heat removal system for sodium-cooled fast reactors that utilizes partially immersed decay heat exchanger
#1126Nuclear reactor building and construction method thereof
#1127Storage rack arrangement for the storage of nuclear fuel elements
#1128Perforated plate support for dual-cooled segmented fuel rod
#1129FAST REACTOR
#1130Operation method of nuclear power plant
#1131Debris filtering bottom spacer grid with louvers for preventing uplift of fuel rods
#1132Top nozzle for nuclear fuel assembly
#1133USE OF ISOTOPICALLY ENRICHED NITROGEN IN ACTINIDE FUEL IN NUCLEAR REACTORS
#1134Method and apparatus of estimating dryout properties in a nuclear light water reactor
#1135NUCLEAR FUEL IN THE FORM OF A PELLET, WITH IMPROVED STRUCTURE
#1136Method and apparatus for executing an operation in a pressure vessel of a nuclear reactor
#1137Core shroud corner joints
#1138PREVENTIVE MAINTENANCE/REPAIR DEVICE AND PREVENTIVE MAINTENANCE/REPAIR METHOD FOR CYLINDRICAL STRUCTURE
#1139Subcritical reactivity measurement method
#1140Upper internals arrangement for a pressurized water reactor
#1141Controllable long term operation of a nuclear reactor
#1142Method for repairing guide rails of an assembly radially maintaining a support plate of a pressurized water nuclear reactor core
#1143POROUS PLENUM SPACER FOR DUAL-COOLED FUEL ROD
#1144Device for handling a fuel assembly
#1145Xenon oscillation prediction method and computer program for xenon oscillation prediction
#1146Mechanical assembly for securing the structural integrity of a pipe joint
#1147Liquid-metal-cooled fast reactor core comprising nuclear fuel assembly with nuclear fuel rods with varying fuel cladding thickness in each of the reactor core regions
#1148Debris Trap
#1149Crystal habit modifiers for nuclear power water chemistry control of fuel deposits and steam generator crud
#1150Intermediate end plug assembly for segmented fuel rod and segmented fuel rod having the same
#1151ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE AND METHOD FOR FABRICATING ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE
#1152Reactor core
#1153Doppler reactivity coefficient measuring method
#1154Zirconium alloy resistant to corrosion in drop shadows for a fuel assembly component for a boiling water reactor, component produced using said alloy, fuel assembly, and use of same
#1155Process for the extraction of technetium from uranium
#1156Apparatus and method for measuring and setting perpendicularity of an upper tie plate of a nuclear fuel bundle
#1157Reactor vessel reflector with integrated flow-through
#1158Covering element for a reactor core of a nuclear installation, and nuclear reactor
#1159Seismically isolated containment vessel
#1160Steam generator flow by-pass system
#1161Method and composition for moderated nuclear fuel
#1162Method of forming a silicon carbide material, and structures including the material
#1163Coupling structure of fuel assembly
#1164NUCLEAR REACTOR INTERNALS ALIGNMENT CONFIGURATION
#1165Nuclear reactor steam dryer manipulator
#1166Self-Regulating Nuclear Power Module
#1167Method for Determining the Three-Dimensional Power Distribution of the Core of a Nuclear Reactor
#1168Apparatus for detecting the leakage of heavy water in nuclear reactor system and detection method using the same
#1169Fixed cluster having a spider-like support, corresponding pressurized water nuclear reactor core and assembly comprising a nuclear fuel assembly and such a fixed cluster
#1170Method for operating a reactor of a nuclear plant
#1171Apparatus for welding a flange of a guide thimble tube in nuclear fuel assembly
#1172ZIRCONIUM ALLOY COMPOSITION FOR NUCLEAR FUEL CLADDING TUBE FORMING PROTECTIVE OXIDE FILM, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE MANUFACTURED USING THE COMPOSITION, AND METHOD OF MANUFACTURING THE ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE
#1173Optical gamma thermometer
#1174RENORMALIZATION METHOD OF EXCORE DETECTOR
#1175Method and apparatus for moving nuclear fuel
#1176Fault tree analysis system for the instrument control process for nuclear power plant with advanced boiling water reactor background
#1177Method for extraction of metals by methyliminobisalkylacetamide
#1178Anti-fretting wear spacer grid with canoe-shaped spring
#1179Jet pump riser clamp
#1180Modular reactor head area assembly
#1181Multi-axis laser welding head for spacer grid
#1182Non-destructive test apparatus
#1183RELATIVELY THICK-WALLED VACUUM-RESISTANT AND PRESSURE-RESISTANT VESSEL
#1184Fuel rod assembly and method for mitigating the radiation-enhanced corrosion of a zirconium-based component
#1185METHOD OF PRODUCING LARGE-GRAINED NUCLEAR FUEL PELLET BY CONTROLLING CHROME CATION SOLUBILITY IN UO2 LATTICE
#1186Method for designing a fuel assembly optimized as a function of the stresses in use in light-water nuclear reactors, and resulting fuel assembly
#1187Structure for suppressing flow vibration of instrumentation guide tube
#1188Protection systems for nuclear boiling water reactors
#1189Underwater remote surface inspection method and apparatus for reactor constituting member
#1190Single quantification method of external event PSA model containing multi-compartment propagation scenarios
#1191Boiling water reactor nuclear power plant with alcohol injection
#1192METHOD AND APPARATUS FOR VERIFYING PERFORMANCE OF CONTROL SYSTEM OF NUCLEAR POWER PLANT
#1193Method for the production of spherical combustible or fertile material particles
#1194METHOD FOR WEATHER MODIFICATION AND VAPOR GENERATOR FOR WEATHER MODIFICATION
#1195Replacement basket, a system using the replacement basket, and a method for loading the replacement basket
#1196REFLECTOR SYSTEM OF FAST REACTOR
#1197Thorium-based nuclear reactor and method
#1198High dielectric insulated coax cable for sensitive impedance monitoring
#1199Control rod drive mechanism
#1200REACTIVITY CONTROL ROD FOR CORE, CORE OF NUCLEAR REACTOR, NUCLEAR REACTOR AND NUCLEAR POWER PLANT