236415 ⎘
Energy generation of nuclear origin Nuclear fission reactors
Nuclear power plant using nanoparticles in emergency systems and related method
#1502Tub-Type Meltdown Retaining Device
#1503Radioactive substance container, manufacturing apparatus thereof and manufacturing method thereof
#1504Monitoring and operation image integrating system of plants and monitoring and operation image integrating method
#1505Distance lattice for fuel rod assembly in nuclear reactor
#1506Apparatus and method for reinforcing jet pump riser
#1507Systems for aligning and handling fuel rods within a nuclear fuel bundle
#1508Boiling water reactor, core of boiling water reactor and fuel assembly
#1509Method of inspecting or utilizing tools in a nuclear reactor environment
#1510Control rod for nuclear reactor and method of manufacturing control rod
#1511Nuclear reactor vessel fuel thermal insulating barrier
#1512Methods and apparatus for detecting cracks in welds
#1513Nuclear Power Plant and a Steam Turbine
#1514High Fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof
#1515REACTOR START-UP MONITORING SYSTEM
#1516Monitoring
#1517Method of manufacturing sinter-active UOpowder and method of producing nuclear fuel pellets utilizing the same
#1518Robust distance measures for on-line monitoring
#1519Method of suppressing deposition of radioactive isotope
#1520MOX fuel assembly for pressurized nuclear reactors
#1521Nuclear power plant and operation method thereof
#1522Method and sampling system for taking sample from the atmosphere in the reactor containment of a nuclear plant
#1523Clad tube for nuclear fuel
#1524Tool for brushing circumferential welds in restricted access areas
#1525Method of repairing a nuclear reactor vessel bottom head penetration
#1526Pumping Device for Nuclear Facility
#1527Failure Proof Gantry Crane and Chain Jack Hoist Assembly
#1528Fuel assembly for a pressurized water reactor
#1529FAST REACTOR
#1530Head-end process for the reprocessing of reactor core material
#1531Handoff methods and assemblies for refueling a nuclear reactor
#1532Single cycle and equilibrium fuel loading method and system to reduce cycle outage in a boiling water nuclear reactor
#1533Finned strainer
#1534TUBE CUTTING DEVICE ANG METHOD THEREOF
#1535Methods for evaluating robustness of solutions to constraint problems
#1536Assembly and method for mounting a fuel assembly having a predefined orientation within a nuclear reactor
#1537Fuel support and method for modifying coolant flow in a nuclear reactor
#1538Control rod guide tube and method for providing coolant to a nuclear reactor fuel assembly
#1539Granulation accelerating device and nuclear reactor housing
#1540Protection systems for and methods of operating nuclear boiling water reactors
#1541Suppression method of radionuclide deposition on reactor component of nuclear power plant and ferrite film formation apparatus
#1542Channel Fastener
#1543Method for perturbating a nuclear reactor core fuel bundle design to generate a group of designs
#1544Non Proliferating Thorium Nuclear Fuel Inert Metal Matrix Alloys for Fast Spectrum and Thermal Spectrum Thorium Converter Reactors
#1545Method and apparatus for repairing a jet pump diffuser adapter to tailpipe weld
#1546Nuclear fuel assembly
#1547Tube-in-tube threaded dashpot end plug
#1548Method for reducing carbon steel corrosion in high temperature, high pressure water
#1549Systems and methods for loading and transferring spent nuclear fuel
#1550Vertical spring wedge
#1551Method for improving energy output of a nuclear reactor, method for determining natural uranium blanket layer for a fuel bundle, and a fuel bundle having a variable blanket layer
#1552Method and system for recovering metal from metal-containing materials
#1553ZIRCONIUM ALLOY COMPOSITION HAVING EXCELLENT CORROSION RESISTANCE FOR NUCLEAR APPLICATIONS AND METHOD OF PREPARING THE SAME
#1554FUEL SUPPORTING ATTACHMENT AND FUEL INLET MECHANISM
#1555Renew process implementation for reactor bottom head
#1556Leak detection method for testing fuel rods of fuel assemblies of a boiling water reactor for leaks
#1557METHOD AND APPARATUS FOR MEASUREMENT OF TERMINAL SOLID SOLUBILITY TEMPERATURE IN ALLOYS CAPABLE OF FORMING HYDRIDES
#1558Storage device for storing and/or transporting nuclear fuel assemblies
#1559Automated nuclear power reactor for long-term operation
#1560Method and system for providing fuel in a nuclear reactor
#1561Controllable long term operation of a nuclear reactor
#1562Systems and methods of predicting a critical effective k for a nuclear reactor
#1563Accumulator
#1564Accumulator and method of manufacturing flow damper
#1565Rod spacer grid for a nuclear fuel assembly, and a corresponding assembly
#1566Methods for detecting contaminants in a liquid
#1567Core spray sparger T-box attachment and clamp and method for clamping
#1568Fuel assembly nozzleless handling tool and method
#1569Method of manufacture of noble metal/zinc oxide hybrid product for simultaneous dose reduction and SCC mitigation of nuclear power plants
#1570Jet pump diffuser weld repair device and method
#1571Thermal load reducing system for nuclear reactor vessel
#1572Fuel assembly for a boiling water reactor
#1573Expanded nuclear fuel channel
#1574Purex method and its uses
#1575Fuel rods for nuclear reactor fuel assemblies and methods of manufacturing thereof
#1576METHOD OF REMOVING RETAINER OF JET PUMP AND JET PUMP
#1577Nuclear reactor fuel assemblies
#1578Condensing chamber design
#1579Method of manufacturing a fuel cladding tube for a nuclear reactor, and a tube obtained thereby
#1580Method for prediction of light water reactor fuel defects using a fuel condition index
#1581Method for positive identification of inner surface and outer surface of sample flakes
#1582Integrated monitoring method for nuclear device and system using the same
#1583Self-regulating nuclear power module
#1584Method for regulation of operational parameters of the core of a pressurised water nuclear reactor
#1585Apparatus for monitoring deposition of a noble metal in a nuclear reactor
#1586APPARATUS AND METHOD FOR PREPARING A CANISTER LOADED WITH WET RADIOACTIVE ELEMENTS FOR DRY STORAGE
#1587Fuel element for a light water reactor, and method for repairing the fuel element
#1588Neutron Absorption Effectiveness for Boron Content Aluminum Materials
#1589Clading complex piping geometry
#1590Process for manufacturing enhanced thermal conductivity oxide nuclear fuel and the nuclear fuel
#1591Reactor containment vessel
#1592Method and apparatus for ultrasonic inspection of reactor pressure vessel
#1593Apparatus For Manufacturing Coated Fuel Particles For High-Temperature Gas-Cooled Reactor
#1594Method for operating a nuclear reactor and use of a specific fuel rod cladding alloy in order to reduce damage caused by pellet/cladding interaction
#1595Use of boron or enriched boron 10 in UO2
#1596Core spray apparatus and method for installing the same
#1597Feedwater controller, nuclear power plant and method for controlling feedwater
#1598Jet pump slip joint piston ring seal
#1599REACTOR FEEDWATER SYSTEM
#1600Method for Operating a Reactor of a Nuclear Plant
#1601Extraction of radionuclides by crown ether-containing extractants
#1602Lower and upper end plugs of an annular fuel rod
#1603Method for in-situ production of hyperstoichiometric oxide fuel
#1604Method of providing and evaluating a mid-wall repair
#1605FULL FUNCTION PRECISION WELDING SYSTEM
#1606Reactor tray vertical geometry with vitrified waste control
#1607Nuclear fuel spacer assembly with debris guide
#1608Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
#1609Method of monitoring deposition of a noble metal in a nuclear reactor and deposition monitor therefor
#1610Nuclear fuel assembly control rod drive thimble to bottom nozzle connector
#1611Control Rod for a Nuclear Plant
#1612Method for the Production of Nuclear Fuel Pellets
#1613Method for analysis of pellet-cladding interaction
#1614Thermal load reducing system for nuclear reactor vessel
#1615Method and apparatus for measuring hydrogen concentration in zirconium alloy components in the fuel pool of a nuclear power plant
#1616Fuel element for a boiling water reactor
#1617Pressuriser for a pressurised water nuclear power station
#1618NATURAL CIRCULATION TYPE BOILING WATER REACTOR
#1619Apparatus and method for welding strap connections between inner grid straps of spacer grid using laser tool, and spacer grid manufactured using the same
#1620Nuclear Fuel
#1621Method for protecting components of a primary system of a boiling water reactor in particular from stress corrosion cracking
#1622Installation for Welding Frameworks of Nuclear Fuel Assemblies, Programming Method, Corresponding Methods for Framework Welding and Assembling
#1623Annular nuclear fuel rod controllable in heat fluxes of inner and outer tubes
#1624Single Plaiting Nuclear Fuel and Method for the Production Thereof
#1625Nuclear Reactor
#1626Stable and passive decay heat removal system for liquid metal reactor
#1627Method and device for checking a welding seam present at one of the interior surfaces of a reactor pressure vessel
#1628Working device and working method
#1629Method for the non-destructive testing of an element for a nuclear reactor
#1630T-shaped pipefitting element pertaining to an auxiliary circuit of a nuclear reactor, connection piece
#1631Spacer grid spring for increasing the conformal contact area with fuel rod
#1632Fuel rod for a nuclear reactor
#1633Process for Producing Pellets of a Nuclear Fuel Based on a (U, Pu)02 or (U, Th)02 Mixed Oxide
#1634Apparatus and method for moving a ferromagnetic element
#1635Boundary condition adjustment methods and systems
#1636Isolation list creation program, method, and device
#1637Bi-alloy spacer grid and associated methods
#1638Bonding Radioactive Iodine in a Nuclear Reactor
#1639Method for analyzing fuel displacement accident of boiling water reactor
#1640Nondestructive inspection apparatus
#1641Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor
#1642Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria
#1643Spacer grid with mixing vanes and nuclear fuel assembly employing the same
#1644Multiple and variably-spaced intermediate flow mixing vane grids for fuel assembly
#1645Method for testing a fuel rod cladding tube and associated device
#1646Natural circulation boiling water reactor and handling method thereof
#1647TEMPERATURE DETECTION APPARATUS FOR NATURAL CIRCULATION BOILING WATER REACTOR
#1648NATURAL CIRCULATION BOILING WATER REACTOR
#1649Steam separator, boiling water reactor and swirler assembly
#1650Reactor power control apparatus of natural circulation reactor and method for controlling reactor power of natural circulation reactor
#1651Reactor power control apparatus of natural circulation reactor, generation system of natural circulation reactor and method for controlling reactor power of natural circulation reactor
#1652Apparatus and method for measuring a temperature of coolant in a reactor core, and apparatus for monitoring a reactor core
#1653System For Controlling A Shell-Type Nuclear Reactor And A Two-Position Switch For The Passive Protection Thereof
#1654Reactor power control apparatus of a natural circulation boiling water reactor and a feed water control apparatus and nuclear power generation plant
#1655Fuel assembly for a pressurized water nuclear reactor containing plutonium-free enriched uranium
#1656Display, visualization, and processing tool for channel distortion and cell friction mitigation
#1657Precursor formulation of a silicon carbide material
#1658Underwater inspecting and repairing system
#1659Method and apparatus for clamping a riser brace assembly in nuclear reactor
#1660Method for limiting the maintenance loads applied to a fuel assembly of a nuclear reactor and fuel assembly
#1661Safety protection instrumentation system and method of operating the system
#1662Terminal end-piece for a fuel assembly having an arrangement for maintaining the ends of the rods and corresponding assembly
#1663Method and apparatus for evaluating robustness of proposed solution to constraint problem and considering robustness in developing a constraint problem solution
#1664Method of preparing feedstock liquid, method of preparing uranyl nitrate solution, and method of preparing polyvinyl alcohol solution
#1665Fuel assembly and thimble screw of the same
#1666Method of determining a cell friction metric for a control cell of a nuclear reactor
#1667Pressurised water nuclear reactor vessel
#1668Hydraulic system for driving control rod drive mechanism
#1669Terminal end-piece for a fuel assembly having a nose for orienting the flow of coolant fluid and corresponding assembly
#1670Nuclear fuel assemblies with structural support replacement rods
#1671Pyrochemical reprocessing method for spent nuclear fuel
#1672Laser-based maintenance apparatus
#1673Methods for installing a fuel pellet locking retainer in a nuclear fuel rod
#1674Method for producing ceramic nuclear fuel tablets, device and container for carrying out said method
#1675Corrosion resistant neutron absorbing coatings
#1676Method and device for stabilizing a steam dryer assembly in nuclear reactor pressure vessel
#1677LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields
#1678Method and system for optimizing a refueling outage schedule
#1679Method of determining margins to operating limits for nuclear reactor operation
#1680Absorber tube for BWR control rods
#1681System and method for collecting and transmitting nuclear reactor control rod position information
#1682Apparatus and method for inspecting areas surrounding nuclear boiling water reactor core and annulus regions
#1683Method and device for measuring the power dissipated by a hydridation reaction in tubes and tubular claddings and the corresponding variation in electric resistance
#1684Method and system for designing a nuclear reactor core for uprated power operations
#1685Device for moving a control bar of a pressurized water nuclear reactor and method for mounting said device on a vessel cover
#1686Neutron absorbing coating for nuclear criticality control
#1687Instrument removal system
#1688Method for inspection and maintenance of an inside of a nuclear power reactor
#1689Modular integrated head assembly
#1690Producing a design for a nuclear fuel element
#1691Trash rack for nuclear power plant
#1692Gas turbine plant
#1693Rod assembly for nuclear reactors
#1694Method for developing nuclear fuel and its application
#1695Nuclear reactor internal structure
#1696Article and method
#1697Method and apparatus utilizing first and second heating devices for heat treating a fuel assembly channel with induction heating
#1698Suppression method of radionuclide deposition on reactor component of nuclear power plant and ferrite film formation apparatus
#1699Control rod and a control rod blade for a boiling water reactor
#1700Method of inspecting or utilizing tools in a nuclear reactor environment
#1701System and method for multiple usage tooling for pressurized water reactor
#1702Vol-oxidizer for spent nuclear fuel
#1703Thermal efficiency diagnosing system for nuclear power plant, thermal efficiency diagnosing program for nuclear power plant, and thermal efficiency diagnosing method for nuclear power plant
#1704Method and a device for packaging leaky nuclear fuel rods for the purposes of transport and long-duration storage or warehousing
#1705System and method for testing the steam system of a boiling water reactor
#1706Separation and receiving device for spent nuclear fuel rods
#1707Reactor containment vessel and boiling water reactor power plant
#1708Device and method for controlling the exterior aspect of fuel rods for nuclear reactors
#1709Radioactive substance container, manufacturing apparatus thereof and manufacturing method thereof
#1710Fuel compact
#1711Control rod position detector
#1712Filter medium for strainers used in nuclear reactor emergency core cooling systems
#1713Zirconium-niobium oxygen-containing alloy and method for producing said alloy
#1714Method and device for manufacturing non-contaminated MOX fuel rods
#1715Nuclear fuel assembly comprising a reinforcing mesh device and the use of one such device in a nuclear fuel assembly
#1716Axial void fraction distribution measurement method and neutron multiplication factor evaluating method
#1717Nuclear reactor feed-water system
#1718Support arrangement
#1719Reactor containment vessel cooling equipment
#1720Electrical hermetic penetrant structure of average voltage
#1721Pressurized water nuclear reactor fuel assembly including rods having two different contents of gadolinium
#1722High-density, solid solution nuclear fuel and fuel block utilizing same
#1723Aluminum-based neutron absorber and method for production thereof
#1724Method of improving the safety of accelerator coupled hybrid nuclear systems, and device for implementing same
#1725Rod block monitor
#1726Device for recovering feedstock liquid, device for supplying a feedstock liquid, device for solidifying the surfaces of drops, and apparatus for producing ammonium diuranate particles
#1727Method of producing a flat zirconium alloy product, flat product thus obtained and a nuclear plant reactor grid which is made from said flat product
#1728Compliant connector for ECCS strainer modules
#1729Electrical hermetic penetrant structure of low voltage
#1730Plate-type nuclear fuels having regularly arranged coarse spherical particles of U-Mo- or U-Mo-X alloy and fabrication method thereof
#1731Advanced gray rod control assembly
#1732Oxygen reduction system for nuclear power plant boiler feedwater and method thereof
#1733Fuel spacer for a nuclear fuel bundle
#1734Repair apparatus for a nuclear reactor shroud
#1735Control rod drive for a nuclear reactor and method for moving a control rod into a reactor core of a nuclear reactor
#1736Apparatus and method for measuring radioactive material in a matrix
#1737Method of manufacture of noble metal/zinc oxide hybrid product for simultaneous dose reduction and SCC mitigation of nuclear power plants
#1738Support system for reactor vessel internals
#1739In-core-monitor-guide-tube supporting apparatus
#1740Micro neutron detectors
#1741Liquid-metal cooled reactor equipped with alkali metal thermoelectric converter
#1742Method and apparatus for maximizing radiation shielding during cask transfer procedures
#1743Fuel grasping device and fuel exchanger
#1744Method for operating a nuclear reactor
#1745Method of improving nuclear reactor performance during reactor core operation
#1746Operation method of nuclear power plant
#1747Fuel channel characterization method and device
#1748Micro neutron detectors
#1749Forced gas flow canister dehydration
#1750Fuel assembly for a pressurized water nuclear reactor
#1751Fuel assembly for a pressurized-water nuclear reactor, and a core of a pressurized-water nuclear reactor which is composed of fuel assemblies of this type
#1752Use of boron or enriched boron 10 in UO
#1753Nuclear fuel rod loading method and apparatus
#1754Method and device for facilitating a uniform loading condition for a plurality of support members supporting a steam dryer in a nuclear reactor
#1755Method and apparatus for backscatter neutron non-destructive examination
#1756Debris filter
#1757Method and apparatus for dehydrating high level waste based on dew point temperature measurements
#1758Mox fuel assembly for pressurized water reactors
#1759Ex-vessel core melt retention device preventing molten core concrete interaction
#1760Method of fuel bundle consideration in a reactor
#1761Lithium ion secondary battery
#1762Label including identifier having specific color or shape and distribution system using the same
#1763Adjustable speed drive system for primary loop recirculation pump
#1764Use of isotopically enriched actinide fuel in nuclear reactors
#1765In-core fuel restraint assembly
#1766Nuclear facility and method for operating a nuclear facility
#1767Mitigation of stress corrosion cracking of structural materials exposed to a high temperature water
#1768Zirconium alloys with improved corrosion resistance and method for fabricating zirconium alloys with improved corrosion
#1769Non-aqueous method for separating chemical constituents in spent nuclear reactor fuel
#1770Providing information
#1771Method of offering wall-thickness thinning prediction information, and computer-readable recording medium storing wall-thickness thinning prediction program, and method of planning piping work plan
#1772Four point contact structural spacer grid
#1773High heat flux rate nuclear fuel cladding and other nuclear reactor components
#1774Nuclear fuel assembly low pressure drop top nozzle
#1775In-situ BWR and PWR CRUD flake analysis method and tool
#1776Method of delivering a tool into a submerged bore
#1777Apparatus for delivering a tool into a submerged bore
#1778Eccentric support grid for nuclear fuel assembly
#1779Methods for demonstrating moderator exclusion for nuclear criticality safety
#1780Apparatus and method for mounting and moving a working apparatus on a structure for the performance of works on the structure
#1781Lifetime support process for rapidly changing, technology-intensive systems
#1782Method for making a flat zirconium alloy product, resulting flat product and fuel, assembly component for nuclear power plant reactor made from said flat product
#1783Sealing device for the outer surface of a nuclear fuel cladding
#1784Inhibitor of corrosion and stress corrosion cracking containing nickel boride (NiB) in the secondary side of steam generator tubes in a nuclear power plant and inhibiting method using the same
#1785Apparatus for dismantling a radioactively contaminated installation part and method for dismantling the installation part
#1786Method and apparatus for repairing a jet pump riser brace to reactor vessel pad attachment in a nuclear reactor
#1787System for measuring burn-out of fuel elements of a high-temperature reactor
#1788Incineration process for transuranic chemical elements and nuclear reactor implementing this process
#1789Digital broadcasting recording/reproducing apparatus and method for the same
#1790High temperature gas-cooled fast reactor
#1791Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant
#1792Boiling water reactor core and fuel assemblies therefor
#1793Image display
#1794Fuel element for a pressurized water reactor
#1795Methods of reducing hydrogen absorption in zirconium alloys of nuclear fuel assemblies
#1796Procedure and means for replacing and procedure for repairing a section of a pipe in the primary circuit of a nuclear reactor
#1797Fuel assembly for a pressurized water nuclear reactor
#1798Multi-core fuel rod for research reactor and manufacturing method thereof
#1799Apparatus and method for limiting and analyzing stress corrosion cracking in pressurized water reactors
#1800Clamp for feedwater sparger end bracket assemblies and method of preventing separation of feedwater sparger end bracket assemblies