Irradiation behaviors of nuclear grade graphite in commercial reactor, (III) Mechanical properties.

DOI
  • MATSUO Hideto
    Department of Fuels and Materials Research, Tokai Research Establishment, Japan Atomic Energy Research Institute
  • SAITO Tamotsu
    Department of Fuels and Materials Research, Tokai Research Establishment, Japan Atomic Energy Research Institute

Bibliographic Information

Other Title
  • Mechanical Properties

Search this article

Description

Bending and compressive strengths, and Young's modulus were measured for Pechiney nuclear grade graphite irradiated in the temperature range 220400°C in the environment of CO2 in a commercial reactor, up to the neutron fluence 6.2×1019 and 2.2×1020 n/cm2 (E>0.85 MeV), respectively.<BR>All of them increased owing to neutron irradiation, and the changes in both strengths were almost similar in the whole range of irradiation temperature, however the changes in Young's modulus depended on irradiation temperature.<BR>It was clarified in the present experiment that both strengths were related with Young's modulus and the relation could be expressed by the formula σ=kEn, where σ and E are strength and Young's modulus, respectively, and n is constant which has different value for bending or compressive strength and also for their measured direction.

Journal

Keywords

Details 詳細情報について

  • CRID
    1390282679073013376
  • NII Article ID
    130000827555
  • DOI
    10.3327/jnst.22.313
  • COI
    1:CAS:528:DyaL2MXitFWis74%3D
  • ISSN
    18811248
    00223131
  • Text Lang
    en
  • Data Source
    • JaLC
    • Crossref
    • CiNii Articles
  • Abstract License Flag
    Disallowed

Report a problem

Back to top