• DocumentCode
    2342657
  • Title

    Generation of thermal neutron scattering libraries for beryllium carbide

  • Author

    Hehr, Brian D. ; Hawari, Ayman I.

  • Author_Institution
    Dept. of Nucl. Eng., North Carolina State Univ., Raleigh, NC, USA
  • fYear
    2010
  • fDate
    21-24 March 2010
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    Beryllium carbide is under investigation as a possible structural or moderator material in fission and fusion systems. While many of the physical properties of beryllium carbide have already been studied, neutronic properties such as the thermal scattering cross-section are not well known. The purpose of this work is to evaluate the scattering cross section of beryllium carbide through quantum mechanical ab-initio simulations. In benchmarking the calculation, physical properties such as the lattice parameter and heat capacity are also computed and compared against measured data.
  • Keywords
    ab initio calculations; beryllium compounds; fission reactor fuel; fusion reactor blankets; neutron diffusion; BeC; beryllium carbide; fission reactor fuel; fission system; fusion reactor blanket material; fusion system; moderator material; neutronic properties; quantum mechanical ab-initio simulations; structural material; thermal neutron scattering libraries; thermal scattering cross-section; Atomic measurements; Computational modeling; Electrons; Lattices; Libraries; Light scattering; Neutron spin echo; Particle scattering; Phonons; Renewable energy resources;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Nuclear & Renewable Energy Conference (INREC), 2010 1st International
  • Conference_Location
    Amman
  • Print_ISBN
    978-1-4244-5213-2
  • Electronic_ISBN
    978-1-4244-5214-9
  • Type

    conf

  • DOI
    10.1109/INREC.2010.5462583
  • Filename
    5462583