200256 ⎘
Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants Selection of specific coolants Additions to the reactor coolants, e.g. against moderator corrosion
TRACE OXYGEN SODIUM LEAK DETECTION IN NUCLEAR REACTOR ENCLOSURE
#2SYSTEMS AND METHODS FOR DECAY HEAT REMOVAL FROM AN EXTERIOR OF A NUCLEAR REACTOR
#3DILUTE RADIONUCLIDE CONCENTRATION ENHANCEMENT THROUGH DISTILLATION
#4ENERGY SOURCE
#5MOLTEN SALT HEAT EXCHANGER
#6SYSTEMS AND METHODS FOR REDUCING COOLANT BACKFLOW THROUGH A POOL-TYPE REACTOR CORE
#7NUCLEAR REACTOR SYSTEM AND METALLIC COOLANT COMPOSITION
#8Nuclear Reactor with Liquid Coolant and Solid Fuel Assemblies, Integrating a System of Evacuation of the Nominal Power with Liquid Metal Bath and Material(s) (MCP) for the Evacuation of the Residual Power in the Event of an Accident
#9Flow through liquid metal cooled molten salt reactors
#10DRILLHOLE NUCLEAR REACTOR
#11COMPACT MOBILE REACTOR SYSTEM USING HIGH DENSITY NUCLEAR FUEL
#12LIQUID METAL OR MOLTEN SALT(S) REACTOR INCORPORATING A DECAY HEAT REMOVAL (DHR) SYSTEM THAT REMOVES HEAT THROUGH THE PRIMARY REACTOR VESSEL, COMPRISING A MODULE OF PASSIVELY OR ACTIVELY TRIGGERED PIVOTING FINS LOCATED IN THE GUARD GAP
#13SYSTEMS AND METHODS OF THERMOELECTRIC COOLING IN POWER PLANTS
#14NUCLEAR REACTOR WITH A HEAVY LIQUID METAL COOLANT
#15NUCLEAR REACTOR WITH A LIQUID METAL COOLANT
#16MOLTEN SALT FISSION REACTOR WITH INTEGRATED PRIMARY EXCHANGER AND ELECTROGENERATOR COMPRISING SUCH A REACTOR
#17Core of Fast Reactor
#18Multipurpose passive residual heat removal system for small fluoride-salt-cooled high-temperature reactor
#19ENERGY SOURCE
#20Processing method for improving corrosion resistance of iron and steel materials in lead or lead-bismuth
#21MOLTEN SALT FAST REACTOR
#22Flow through liquid metal cooled molten salt reactors
#23Energy production devices and associated components, and related heat transfer devices and methods
#24EXTERNAL REACTOR VESSEL COOLING SYSTEM FOR FLOATING NUCLEAR POWER PLANTS
#25Multipurpose small modular fluoride-salt-cooled high-temperature reactor energy system
#263D printed features on nuclear fuel cladding for optimized heat transfer
#27MOLTEN FUEL REACTOR THERMAL MANAGEMENT CONFIGURATIONS
#28Emergency heat removal in a light water nuclear reactor by using a passive endothermic reaction cooling system
#29Structural material for molten salt reactors
#30Molten salt compositions with enhanced heat transfer and reduced corrosion properties
#31Molten fuel nuclear reactor
#32Predictive model construction and prediction method for radioactive metal corrosion concentration in nuclear reactor water
#33FERRITIC ALLOY
#34Heat exchanger assemblies having embedded sensors
#35Advanced Automated Fabrication System And Methods For Thermal And Mechanical Components Utilizing Quadratic Or Squared Hybrid Direct Laser Sintering, Direct Metal Laser Sintering, CNC, Thermal Spraying, Direct Metal Deposition And Frictional Stir Welding. Cross-reference To Related Applications
#36Honeycomb-shaped fuel assembly cooled by liquid chloride salt and reactor core using this assembly
#37Molten fuel reactor thermal management configurations
#38Fission reaction control in a molten salt reactor
#39High efficiency power generation system and system upgrades
#40Passive reactor cavity cooling system
#41Method and Control System for Gas Injection into Coolant and Nuclear Reactor Plant
#42Combination reactor gamma radiation power harvesting reactor power distribution measurement, and support to coolant freezing protection system for liquid metal and molten salt-cooled reactor systems
#43Electrochemical Separation Mechanism in a Molten Salt Reactor
#44HIGH-TEMPERATURE NUCLEAR REACTOR COOLED WITH MOLTEN FLUORIDE SALT
#45Sodium-tin and sodium-tin-lead coolants
#46Nuclear reactor system for extinguishing radioactivity
#47Heat transport apparatus
#48System for the highly autonomous operation of a modular liquid-metal reactor with steam cycle
#49GAS-COOLED PRESSURE TUBE REACTOR
#50CONTROL OF CORROSION BY MOLTEN SALTS
#51FAST NEUTRON REACTOR FUEL ROD
#52Nuclear reactor having efficient and highly stable carbon-based thermal transfer fluid
#53Emergency and back-up cooling of nuclear fuel and reactors and fire-extinguishing, explosion prevention using liquid nitrogen
#54Molten fuel nuclear reactor with neutron reflecting coolant
#55Nuclear reactor, in particular liquid-metal-cooled compact nuclear reactor
#56Ferritic alloy
#57Molten fuel reactor cooling and pump configurations
#58MOLTEN FUEL REACTOR THERMAL MANAGEMENT CONFIGURATIONS
#59Method and control system for gas injection into coolant and nuclear reactor plant
#60Molten fuel nuclear reactor with neutron reflecting coolant
#61NUCLEAR FUEL SALTS
#62Modular nuclear fission waste conversion reactor
#63Platinum oxide colloidal solution, manufacturing method therefor, manufacture apparatus thereof, and method of injection noble metal of boiling water nuclear power plant
#64Fuel bundle for a liquid metal cooled nuclear reactor
#65Apparatus and method for stripping tritium from molten salt
#66Porous cooling block for cooling corium and corium cooling apparatus including same, and corium cooling method using same
#67NUCLEAR POWER PLANT AND DEVICE FOR FEEDING A COVER GAS INTO THE PLANT
#68MOVEMENT OF FUEL TUBES WITHIN AN ARRAY
#69Chemical optimisation in a molten salt reactor
#70Fast Neutron Reactor and Neutron Reflector Block of a Fast Neutron Reactor
#71High efficiency power generation system and system upgrades
#72Reactor system with a lead-cooled fast reactor
#73Emergency and back-up cooling of nuclear fuel and reactors and fire-extinguishing, explosion prevention using liquid nitrogen
#74Nuclear reactor coolant pump and nuclear power plant having same
#75MOLTEN NUCLEAR FUEL SALTS AND RELATED SYSTEMS AND METHODS
#76NUCLEAR MATERIALS PROCESSING
#77Fission reaction control in a molten salt reactor
#78Light water reactor with condensing steam generator
#79Method of cooling nuclear reactor and nuclear reactor including polyhedral boron hydride or carborane anions
#80Liquid nitrogen emergency cooling system for nuclear power plants
#81Photocatalyst injection method and photocatalyst injection system
#82Heat exchange medium, heat exchange system, and nuclear reactor system
#83High temperature gas cooled reactor steam generation system
#84Dual fluid reactor
#85Controllable long term operation of a nuclear reactor
#86Method of operating a power generator based on noble metal induced oxidation of a heat transfer surface
#87Platinum Oxide Colloidal Solution, Manufacturing Method Therefor, Manufacture Apparatus Thereof, and Method of Injection Noble Metal of Boiling Water Nuclear Power Plant
#88Method for cleaning and conditioning the water-steam circuit of a power plant, especially of a nuclear power plant
#89Method for conditioning a power-generating circulatory system of a power plant
#90Method of fabricating liquid-metal coolants for nuclear reactors
#91Fuel bundle for a liquid metal cooled nuclear reactor
#92Method for protecting components of a primary system of a boiling water reactor in particular from stress corrosion cracking
#93Colloidal dispersion of aluminum oxide
#94INSTALLATION FOR PRODUCING POWER FROM A GAS-COOLED FAST NUCLEAR REACTOR
#95Annular core liquid-salt cooled reactor with multiple fuel and blanket zones
#96Liquid alkali metal with dispersed nanoparticles and method of manufacturing the same
#97High Efficiency Power Plants
#98Nuclear reactor having efficient and highly stable thermal transfer fluid
#99Coolant with dispersed neutron poison micro-particles, used in SCWR emergency core cooling system
#100NUCLEAR REACTOR
#101Conducting fluid containing millimetric magnetic particles
#102Controllable long term operation of a nuclear reactor
#103Method for protecting components of a primary system of a boiling water reactor in particular from stress corrosion cracking
#104Fluid in liquid state containing dispersed nano-particles of metal or the like
#105Fluid in liquid state containing dispersed nano-particles of metal or the like
#106Dielectric coating for surfaces exposed to high temperature water
#107Method for protecting components of a primary system of a boiling water reactor in particular from stress corrosion cracking