Class / Patent application number | Description | Number of patent applications / Date published |
376361000 |
Circulating fluid within reactor
| 134 |
376352000 |
Orifice or fluid control at inlet or outlet of coolant channels
| 10 |
376353000 |
With particular control rod guide structure
| 9 |
376354000 |
Fuel material in contact with and supported by fluid
| 6 |
376350000 |
Moderator component varies in its effective density or materials | 3 |
20140146934 | Compact Liquid Metal Cooled Spherical Fast Neutron Reactor Core Design - The present invention provides a design for a compact liquid metal cooled fast neutron nuclear reactor core. The design incorporates a single spherical fuel element with a subcritical mass. The spherical fuel element is brought to critically through the use of a plurality of adjustable concave neutron reflector panels. This novel nuclear reactor core configuration represents a simplified, compact and economical design. | 05-29-2014 |
20110222641 | 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. | 09-15-2011 |
20120288052 | 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. | 11-15-2012 |
376348000 |
Fast thermal composite core | 1 |
20120121058 | CORE OF NUCLEAR REACTOR AND NUCLEAR REACTOR - A core of a nuclear reactor wherein the core is provided with a new fuel part at which new fuel is loaded and a burning part where the fuel burns, plutonium which is produced from uranium fissions to generate output, and the burning part moves from the beginning to end of the burning cycle, wherein when dividing the core, which is substantially circular when viewed by a plan view, into a center part and a peripheral part, the new fuel part is formed so that the weight of uranium per unit volume at the center part becomes smaller than the weight of uranium per unit volume at the peripheral part. | 05-17-2012 |
Entries |
Document | Title | Date |
20090052606 | NUCLEAR REACTOR INTERNALS ALIGNMENT CONFIGURATION - An alignment system that employs jacking block assemblies and alignment posts around the periphery of the top plate of a nuclear reactor lower internals core shroud to align an upper core plate with the lower internals and the core shroud with the core barrel. The distal ends of the alignment posts are chamfered and are closely received within notches machined in the upper core plate at spaced locations around the outer circumference of the upper core plate. The jacking block assemblies are used to center the core shroud in the core barrel and the alignment posts assure the proper orientation of the upper core plate. The alignment posts may alternately be formed in the upper core plate and the notches may be formed in top plate. | 02-26-2009 |
20090296874 | Plant with Piping Mounted on Branch Pipe and Boiling Water Reactor Plant - A plant with piping mounted on branch pipe,
| 12-03-2009 |
20100208860 | GC QCMEHC nuclear power plants - Globose-conduit (GC) perimeter boundaries formations mass energy highest conserving (MEHC) Sets, balanced nuclear power plants, in millennium lifespan generate safest environmentally most friendly electric power; said perimeter boundaries' formations, multiple and serial enclosures, constitute a globose foundation globose reactor vessel, a containment building with a lower perimeter ancillary annex building for multiple primary coolant loops, light water reactors pressurized system, GC conduit tuned piping mass energy processes and buildings complex, boundaries safely closed perimeters. Two or four globose steam generators/separators two or four high pressure pumps' coolant loops and the reactor's support equipment floors in the annex building outside of the containment symmetrically align high pressure and temperature GC MEHC boundaries respectively two or four processes generated electrons turbine-generator buildings. The reactor, steam generators, processes piping and turbine-generators make GC mass energy formations. | 08-19-2010 |
20110164720 | CORE OF LIGHT WATER REACTOR AND FUEL ASSEMBLY - A core of a light water reactor has a plurality of fuel assemblies. The fuel assemblies include a plurality of fuel rods in which a lower end is supported by a lower tie-plate and an upper end is supported by an upper tie-plate. The fuel rods form plenums above a nuclear fuel material zone and have a neutron absorbing material filling zone under the nuclear fuel material zone. Neutron absorbing members attached to the upper tie-plate are disposed between mutual plenums of the neighboring fuel rods above the nuclear fuel material zone. The neutron absorbing members have a length of 500 mm and are positioned at a distance of 300 mm from the nuclear fuel material zone. Even if the overall core is assumed to become a state of 100% void, no positive reactivity is inserted to the core. | 07-07-2011 |
20110235770 | CORE SPRAY SPARGER T-BOX CLAMP ASSEMBLIES AND METHODS OF USING THEREOF - Example embodiments are directed to core spray sparger T-box repairs, specifically, to universal core spray sparger T-box weldless clamps having remote-friendly operation and methods of using universal core spray sparger T-box weldless clamps. Example embodiment clamps may be secured without welding to a variety of upper and lower sparger T-box configurations. Example embodiment clamps may be configured to simultaneously engage a sparger T-box in multiple dimensions to allow a universal fit. Further, example embodiment clamps may be accessed, installed, or removed by interacting only with a front side of the example embodiment clamps, thus potentially reducing difficulty and cost in remote access repairs to example clamps. | 09-29-2011 |
20120219102 | NUCLEAR BATTERY BASED ON HYDRIDE/THORIUM FUEL - Methods, processes, and systems of transportable nuclear batteries are provided. In one embodiment, the battery may comprise a sealed reactor shell, a reactor core, and a generator. In further embodiments, the transportable nuclear battery may comprise a nuclear fuel in the reactor core wherein the fuel comprises plutonium, carbon, hydrogen, zirconium and, thorium. In some embodiments, the fuel may comprise hydrogen-containing glass microspheres, wherein the glass microspheres, may be coated with a burnable poison, and other coating materials that may aid in keeping the hydrogen within the microsphere glass at relatively high temperature. The disclosed methods, processes and systems may aid in providing energy to remote areas. | 08-30-2012 |
20130301783 | RISER CONE APPARATUS TO PROVIDE COMPLIANCE BETWEEN REACTOR COMPONENTS AND MINIMIZE REACTOR COOLANT BIPASS FLOW - A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section. | 11-14-2013 |
20140064430 | NOZZLE REPAIRING METHOD AND NUCLEAR REACTOR VESSEL - The repairing method includes removing a connection portion with respect to an in-core instrument tube in a groove-welding portion, removing the in-core instrument tube from a lower mirror, removing the groove-welding portion and processing a plug attachment opening, and fixing a plug to the plug attachment opening by welding. | 03-06-2014 |
20140064431 | NOZZLE REPAIRING METHOD AND NUCLEAR REACTOR VESSEL - It is possible to improve the workability and the stress corrosion resistance by easily performing a repairing operation in a nozzle repairing method and a nuclear reactor vessel. The repairing method includes: removing a first connection portion ((trepanned portion) | 03-06-2014 |
20140205053 | Spacer Grids With Springs Having Improved Robustness - A spacer grid includes intersecting straps defining cells with springs and dimples arranged to hold fuel rods passing through the cells. The springs are dual cantilevered springs with a bridge section between the distal end of the spring and the base. The distal portion of the spring is less stiff than the bridge section. The bridge section creates a bump which acts as a stop or travel limiter to prevent loss of grip force due to excessive spring deflection. | 07-24-2014 |
20140376680 | Containment Sump Ceramic Drain Plug - The present invention provides a drain plug assembly that prevents significant quantities of corium from entering the drain line. By protecting the drain line, essentially no high-activity fission products would be released to the reactor building or the environment during a severe accident. The ceramic drain plug assembly includes a drain plug base and a drain plug supported by a steel pedestal. The lower surface of the plug has a spherical shape such that the plug can be positioned within the base to block access to the drain opening provided in a central portion of the base. During normal operation conditions, the plug is retained above the base by the pedestal. During a severe accident, when corium comes into contact with the pedestal, it will melt rapidly and the drain plug will drop by gravity, effectively closing the sump drain opening and preventing the flow of corium into the drain line. | 12-25-2014 |
20150063520 | Nuclear Reactor Consuming Nuclear Fuel that Contains Atoms of Elements Having a Low Atomic Number and a Low Mass Number - The invention relates to a reactor for consuming a nuclear fuel that contains atoms of elements having a low atomic number (Z) and a low mass number (A), wherein the nuclear reactor ( | 03-05-2015 |
20150117589 | Molten Salt Reactor - To provide a molten salt reactor that enables heat in the molten salt reactor to be extracted without bringing metal piping for heat exchange into direct contact with a molten salt. A molten salt reactor is provided with: a moderator structure | 04-30-2015 |
20150124922 | SYSTEMS AND METHODS FOR ENHANCING ISOLATION OF HIGH-TEMPERATURE REACTOR CONTAINMENTS - A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel. | 05-07-2015 |
20150146840 | Sodium-resistant joining glass and the use thereof - The sodium-resistant joining glass ( | 05-28-2015 |
20160012924 | ELECTRIC FISSION REACTOR FOR SPACE APPLICATIONS | 01-14-2016 |
20160180973 | REACTOR PRESSURE VESSEL ASSEMBLY INCLUDING A FLOW BARRIER STRUCTURE | 06-23-2016 |