• Title of article

    Derivation of fuel bundle power limits using fuel element modelling code FUDA

  • Author/Authors

    Prasad، نويسنده , , P.N. and Soni، نويسنده , , Rakesh and Tripathi، نويسنده , , Rahul Mani and Pandarinathan، نويسنده , , P.R. and Neema، نويسنده , , L.K.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2008
  • Pages
    3
  • From page
    150
  • To page
    152
  • Abstract
    The fuel designs, used in India are 19-element circular geometry and 37-element circular geometry for the 220 MWe PHWR and 540 MWe PHWR, respectively. The fuel bundle design has been evaluated by theoretical analysis, development tests and type tests. The theoretical analysis comprises of fuel bundle sub-channel analysis, fuel element thermo-mechanical analysis and fuel failure analysis during accidents etc. The fuel element thermo-mechanical analysis is carried out using computer code FUDA (Fuel Design Analysis) code. The fuel bundle power limit is derived based on fuel central line temperature, sheath strain and fission gas release parameters. The paper brings out the details of the FUDA code, the typical analysis carried out to estimate these parameters by FUDA code for deriving bundle power limits during operation for 540 MWe PHWR for 37-element fuel bundle.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2008
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1364655