• DocumentCode
    2930057
  • Title

    A neutronic evaluation of VHTR and LS-VHTR

  • Author

    Silva, Fabiano C. ; Pereira, Claubia ; Costa, Antonella L. ; Silva, Clarysson Alberto M ; Veloso, Maria Auxiliadora F

  • Author_Institution
    Dept. de Eng. Nucl., Univ. Fed. de Minas Gerais, Belo Horizonte, Brazil
  • fYear
    2009
  • fDate
    7-10 June 2009
  • Firstpage
    1
  • Lastpage
    7
  • Abstract
    VHTR (Very High Temperature Reactor) and LS-VHTR (Liquid Salted - Very High Temperature Reactor) reactors were analyzed and compared from the viewpoint of the neutronic parameters. The multiplication coefficient (kinf), the fuel and the moderator temperature coefficients (αTF and αTM, respectively) and the hardening spectrum (φF/φT, fast flux/total flux) parameters were analyzed focusing to understanding better the VHTR and LS-VHTR neutronic behaviors. The experience obtained performing this work will be used in the future to study and to simulate the possibility of such systems for fuel reprocessing and recycling always analyzing how the process can affect the hydrogen production efficiency. The preliminary analyses have demonstrated that the VHTR reactor has a safer behavior in comparison with to the LS-VHTR one considering the evolution of the safety parameters along the burnup using WIMSD simulations.
  • Keywords
    fission reactor fuel reprocessing; fission reactor safety; fission reactor theory; gas cooled reactors; nuclear engineering computing; LS-VHTR neutronic behavior; VHTR; WIMSD simulation; fuel recycling; fuel reprocessing; hardening spectrum parameter; hydrogen production efficiency; liquid salted-very high temperature reactor; moderator temperature coefficient; multiplication coefficient; neutronic parameter; safety parameter; Fuels; Heat transfer; Helium; Hydrogen; Inductors; Nuclear power generation; Power generation; Production; Safety; Temperature; HTR; VHTR; VHTR-LS; neutronic behavior;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
  • Conference_Location
    Marseille
  • Print_ISBN
    978-1-4244-5207-1
  • Electronic_ISBN
    978-1-4244-5208-8
  • Type

    conf

  • DOI
    10.1109/ANIMMA.2009.5503690
  • Filename
    5503690