• Title of article

    Integrity assessment of the high temperature engineering test reactor (HTTR) control rod at very high temperatures Original Research Article

  • Author/Authors

    Y. Tachibana، نويسنده , , S. Shiozawa، نويسنده , , J. Fukakura، نويسنده , , F. Matsumoto، نويسنده , , T. Araki، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 1997
  • Pages
    10
  • From page
    93
  • To page
    102
  • Abstract
    The high temperature engineering test reactor (HTTR) is the first high temperature gas-cooled reactor (HTGR) in Japan with a reactor outlet coolant temperature of 950°C at high temperature test operation. The HTTR contains 16 pairs of control rods for which Alloy 800H is chosen of the metallic parts. Because the maximum temperature of the control rods reaches about 900°C at reactor scrams, structural design guideline and design material data on Alloy 800H are needed for the high temperature design. The design guideline for the HTTR control rod is based on ASME Code Case N-47-21. Design material data is also determined and shown in this paper. Under the guideline, temperature and stress analysis was conducted, and it is confirmed that the target life of the control rods of 5 years can be achieved.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    1997
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    888260