Description
NUCLEAR REACTORS (analogue computers therefor G06G 7/54; fusion reactors, hybrid fission-fusion reactors G21B; nuclear explosives G21J)
NUCLEAR REACTORS (analogue computers therefor G06G 7/54; fusion reactors, hybrid fission-fusion reactors G21B; nuclear explosives G21J)
Subclass | Title |
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1/00 | Reactors |
1/01 | Reactors General details not provided for in groups G21C 3/00-G21C 19/00 |
1/02 | Reactors Fast fission reactors, i.e. reactors not using a moderator |
1/03 | Reactors Fast fission reactors, i.e. reactors not using a moderator cooled by a coolant not essentially pressurised, e.g. pool-type reactors |
1/04 | Reactors Thermal reactors |
1/06 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated |
1/07 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated Pebble-bed reactors; Reactors with granular fuel |
1/08 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor (G21C 1/22 takes precedence) |
1/09 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor (G21C 1/22 takes precedence) Pressure regulating arrangements, i.e. pressurisers |
1/10 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor (G21C 1/22 takes precedence) moderator and coolant being different or separated |
1/12 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor (G21C 1/22 takes precedence) moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor |
1/14 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor (G21C 1/22 takes precedence) |
1/16 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor (G21C 1/22 takes precedence) moderator and coolant being different or separated, e.g. sodium-graphite reactor |
1/18 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor (G21C 1/22 takes precedence) moderator and coolant being different or separated, e.g. sodium-graphite reactor coolant being pressurised |
1/20 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor (G21C 1/22 takes precedence) moderator and coolant being different or separated, e.g. sodium-graphite reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor |
1/22 | Reactors Thermal reactors Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel |
1/24 | Reactors Thermal reactors Homogeneous reactors, i.e. in which fuel and moderator present an effectively homogeneous medium to the neutrons |
1/26 | Reactors Thermal reactors Homogeneous reactors, i.e. in which fuel and moderator present an effectively homogeneous medium to the neutrons Single-region reactors |
1/28 | Reactors Thermal reactors Homogeneous reactors, i.e. in which fuel and moderator present an effectively homogeneous medium to the neutrons Two-region reactors |
1/30 | Reactors Subcritical reactors |
Publication # | Title | Filing Date | Pub Date | Patent Owner |
---|---|---|---|---|
2024/0153,652 | Core of Fast Reactor and Method of Operating Fast Reactor | Nov 13, 23 | May 09, 24 | Not available |
2024/0153,653 | NUCLEAR REACTOR WITH A LIQUID METAL COOLANT | Oct 04, 21 | May 09, 24 | "AKME-ENGINEERING", JOINT-STOCK COMPANY |
2024/0153,654 | NUCLEAR REACTOR AND FUEL | Mar 14, 22 | May 09, 24 | Not available |
2024/0153,655 | EMERGENCY CORE COOLING SYSTEM VALVE FOR INTEGRATED-TYPE REACTOR | Nov 01, 21 | May 09, 24 | Not available |
2024/0153,656 | Electrical Penetration | Nov 03, 23 | May 09, 24 | Not available |
2024/0142,328 | SENSING DEVICES FOR HARSH ENVIRONMENTS | Oct 20, 23 | May 02, 24 | Not available |
2024/0145,104 | USE OF OXIDATION RESISTANT COATINGS TO INCREASE THIN WALLED CLADDING TENSILE STRENGTH TO INCREASE URANIUM LOADINGS | Nov 02, 22 | May 02, 24 | Westinghouse Electric Company LLC |
2024/0145,105 | NUCLEAR REACTOR FUEL | Feb 25, 22 | May 02, 24 | Not available |
2024/0145,106 | Method For Estimating A Future Value Of The Axial Power Imbalance In A Nuclear Reactor | Oct 31, 23 | May 02, 24 | Electricite de France; Centre National De La Recherche Scientifique (CNRS); ECOLE CENTRALE DE NANTES; |
2024/0145,107 | NEUTRON FLUX MEASUREMENT APPARATUS | Apr 07, 21 | May 02, 24 | MITSUBISHI ELECTRIC CORPORATION |
2024/0145,108 | IN-SITU TEMPERATURE-CONTROLLED ACTIVE INSTRUMENTATION CAPSULE FOR MATERIALS IRRADIATION TESTING | Nov 02, 23 | May 02, 24 | Not available |
2024/0136,077 | NUCLEAR POWER GENERATOR, FUEL CARTRIDGES FOR NUCLEAR POWER GENERATOR, AND RELATED METHODS | Jul 18, 22 | Apr 25, 24 | Not available |
2024/0134,073 | Real-Tune Change Detection Monitoring Using Isotopic Ratio Signatures | Oct 13, 23 | Apr 25, 24 | Not available |
2024/0127,974 | REACTOR DESIGN WITH CONTROLLED THERMAL NEUTRON FLUX FOR ENHANCED NEUTRON ACTIVATION POTENTIAL | Nov 02, 23 | Apr 18, 24 | BWXT Advanced Technologies LLC |
2024/0127,975 | SERIAL HIGH-TEMPERATURE GAS-COOLED REACTOR NUCLEAR SYSTEMS AND OPERATING METHODS THEREOF | Oct 11, 23 | Apr 18, 24 | Not available |
2024/0127,977 | APPARATUS FOR ELIMINATING RESIDUAL HEAT OF NUCLEAR REACTOR FOR VEHICLE MOUNTING | May 25, 23 | Apr 18, 24 | Korea Atomic Energy Research Institute |
2024/0127,978 | METHOD FOR THERMAL PERFORMANCE MONITORING OF A NUCLEAR POWER PLANT USING THE NCV METHOD | Aug 15, 22 | Apr 18, 24 | Not available |
2024/0125,950 | Devices, Systems, and Methods for Detecting Radiation with Schottky Diodes for Enhanced In-Core Measurements n-Core Measurements | Oct 11, 23 | Apr 18, 24 | Westinghouse Electric Company LLC |
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