DOCSLIB.ORG
  • Sign Up
  • Log In
  • Upload
  • Sign Up
  • Log In
  • Upload
  • Home
  • »  Tags
  • »  Uranium nitride

Uranium nitride

  • Transition-Metal-Bridged Bimetallic Clusters with Multiple Uranium–Metal Bonds

    Transition-Metal-Bridged Bimetallic Clusters with Multiple Uranium–Metal Bonds

  • Process for the Production of Uranium Trifluoride

    Process for the Production of Uranium Trifluoride

  • Impact of the Synthesis Process on Structure Properties for AFCI Fuel Candidates

    Impact of the Synthesis Process on Structure Properties for AFCI Fuel Candidates

  • Impact of the Synthesis Process on Structure Properties for AFCI Fuel Candidates

    Impact of the Synthesis Process on Structure Properties for AFCI Fuel Candidates

  • Nitride Fuel for Gen IV Nuclear Power Systems

    Nitride Fuel for Gen IV Nuclear Power Systems

  • Appendix 2: Development of LWR Fuels with Enhanced Accident Tolerance; Task 2 – Description of Research & Development Required to Qualify

    Appendix 2: Development of LWR Fuels with Enhanced Accident Tolerance; Task 2 – Description of Research & Development Required to Qualify

  • First Principles Investigations of Electronic, Magnetic and Bonding Peculiarities of Uranium Nitride-Fluoride UNF

    First Principles Investigations of Electronic, Magnetic and Bonding Peculiarities of Uranium Nitride-Fluoride UNF

  • Achievable Power Uprates in Pressurized Water Reactors Using Uranium Nitride Fuel

    Achievable Power Uprates in Pressurized Water Reactors Using Uranium Nitride Fuel

  • First-Principles Investigations of the Electronic and Magnetic Structures

    First-Principles Investigations of the Electronic and Magnetic Structures

  • Nitride Fuel for Gen IV Nuclear Power Systems

    Nitride Fuel for Gen IV Nuclear Power Systems

  • Production of Low-Enriched Uranium Nitride Kernels for TRISO Particle Irradiation Testing

    Production of Low-Enriched Uranium Nitride Kernels for TRISO Particle Irradiation Testing

  • Research and Development of Nitride Fuel Cycle Technology in Japan Is Reviewed and the Research Program PROMINENT Is Introduced

    Research and Development of Nitride Fuel Cycle Technology in Japan Is Reviewed and the Research Program PROMINENT Is Introduced

  • Principles of Chemical Recognition and Transport in Extractive

    Principles of Chemical Recognition and Transport in Extractive

  • UN Microspheres Embedded in UO2 Matrix: an Innovative Accident Tolerant Fuel

    UN Microspheres Embedded in UO2 Matrix: an Innovative Accident Tolerant Fuel

  • FISSION-GAS RELEASE from URANIUM NITRIDE at HIGH FISSION-RATE DENSITY by Michael B

    FISSION-GAS RELEASE from URANIUM NITRIDE at HIGH FISSION-RATE DENSITY by Michael B

  • Manufacturing Methods for (U-Zr)N-Fuels

    Manufacturing Methods for (U-Zr)N-Fuels

  • Experimental and Theoretical Studies of Nitride Fuels

    Experimental and Theoretical Studies of Nitride Fuels

  • JAERI-Review 2001-040 REVIEW of ACTINIDE NITRIDE PROPERTIES

    JAERI-Review 2001-040 REVIEW of ACTINIDE NITRIDE PROPERTIES

Top View
  • Experimental Equilibrium Data for the Uranium(IV) Thiocyanate System
  • Uranium Mononitride: Heat Capacity and Thermodynamic Properties from 5° to 350 0 K*
  • Arxiv:1206.3597V2 [Cond-Mat.Mtrl-Sci] 22 Jun 2012 Lnt S Na Fuel
  • Generation IV Reactors
  • Terminal Uranium(V)-Nitride Hydrogenations Involving Direct Addition Or Frustrated Lewis Pair Mechanisms
  • FABRICATION of URANIUM MONONITRIDE COMPACTS by Robert R
  • Activation of Carbon Dioxide by a Terminal Uranium-Nitrogen Bond in the Gas-Phase
  • Preliminary Developments of Mtr Plates with Uranium Nitride
  • Metallacyclic Actinide Catalysts for Dinitrogen Conversion to Ammonia and Secondary Amines
  • Accident-Tolerant Uranium Nitride
  • Nitrogen Reduction by Multimetallic Uranium Complexes
  • Investigations of Nitride Fuels for Fast Reactors in Russia
  • A Sintered Nuclear Fuel Pellet, a Fuel Rod, a Fuel Assembly, and a Method Of
  • Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor
  • Assessment of the Technical Maturity of Generation IV Concepts for Test Or Demonstration Reactor Applications
  • Nuclear Reactors: Generation to Generation
  • Development of Uranium Nitride Composite for Space Reactors Application
  • TM-44-14-03.Pdf


© 2024 Docslib.org    Feedback