• Title of article

    Thermal, structural, and radiological properties of irradiated graphite from the ASTRA research reactor – Implications for disposal

  • Author/Authors

    Lexa، نويسنده , , Dusan and Kropf، نويسنده , , A. Jeremy، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2006
  • Pages
    11
  • From page
    122
  • To page
    132
  • Abstract
    The release of Wigner energy from the graphite of the inner thermal column of the ASTRA research reactor has been studied by differential scanning calorimetry and simultaneous differential scanning calorimetry/synchrotron powder X-ray diffraction between 25 °C and 725 °C at a heating rate of 10 °C min−1. The graphite, having been subject to a fast-neutron fluence from ∼1017 to ∼1020 n cm−2 over the life time of the reactor at temperatures not exceeding 100 °C, exhibits Wigner energies ranging from 25 to 572 J g−1 and a Wigner energy accumulation rate of ∼7 × 10−17 J g−1/n cm−2. The shape of the rate-of-heat-release curves, e.g., maximum at ca. 200 °C and a fine structure at higher temperatures, varies with sample position within the inner thermal column, i.e., the distance from the reactor core. Crystal structure of samples closest to the reactor core (fast-neutron fluence >1.5−5.0 × 1019 n cm−2) is destroyed while that of samples farther from the reactor core (fast-neutron fluence <1.5−5.0 × 1019 n cm−2) is intact, with marked swelling along the c-axis. The dependence of the c lattice parameter on temperature between 25 °C and 200 °C as determined by Rietveld refinement for the non-amorphous samples leads to the expected microscopic thermal expansion coefficient along the c-axis of ∼ 26 × 10−6 °C−1. However, at 200 °C, coinciding with the maximum in the rate-of-heat-release curves, the rate of thermal expansion abruptly decreases indicating a crystal lattice relaxation. The 14C activity in the inner thermal column graphite ranges from 6 to 467 kBq g−1. The graphite of the inner thermal column of the ASTRA research reactor has been treated by heating to 400 °C for 24 h in a hot-cell facility prior to interim storage.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2006
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1363004