• Title of article

    Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code

  • Author/Authors

    Adoo، نويسنده , , N.A. and Nyarko، نويسنده , , B.J.B. and Akaho، نويسنده , , E.H.K. and Alhassan، نويسنده , , E. and Agbodemegbe، نويسنده , , V.Y. and Bansah، نويسنده , , C.Y. and Della، نويسنده , , R.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2011
  • Pages
    8
  • From page
    5203
  • To page
    5210
  • Abstract
    The PARET/ANL code has been adapted by the IAEA for testing transient behaviour in research reactors since it provides a coupled thermal hydrodynamic and point kinetics capability for estimating thermal hydraulic margins. A two-channel power peaking profile of the Ghana Research Reactor-1 (GHARR-1) has been developed for the PARET/ANL (Version 7.3; 2007) using the Monte Carlo N-Particle code (MCNP) to determine the thermal hydraulic data for reactivity insertion transients in the range of 2.0 × 10−3 Δk/k to 5.5 × 10−3 Δk/k. Peak clad and coolant temperatures ranged from 59.18 °C to 112.36 °C and 42.95 °C to 79.42 °C respectively. Calculated safety margins (DNBR) satisfied the MNSR thermal hydraulic design criteria for which no boiling occurs in the reactor core. The generated thermal hydraulic data demonstrated a high inherent safety feature of GHARR-1 for which the high negative reactivity feedback of the moderator limits power excursion and consequently the escalation of the clad temperature.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2011
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    1591733