Microstructural Evolution of an Ion Irradiated Ni–Mo–Cr–Fe Alloy at Elevated Temperatures

DOI Web Site Web Site 参考文献34件
  • de los Reyes Massey
    Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO)
  • Edwards Lyndon
    Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO)
  • Bhattacharyya Dhriti
    Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO)
  • Kirk Marquis A.
    Materials Science Division, Argonne National Laboratory
  • Lu Kim T.
    Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO)
  • Lumpkin Gregory R.
    Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO)

書誌事項

タイトル別名
  • Microstructural Evolution of an Ion Irradiated Ni–Mo–Cr–Fe Alloy at Elevated Temperatures
公開日
2014
DOI
  • 10.2320/matertrans.md201311
公開者
公益社団法人 日本金属学会

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説明

The irradiation behavior of a Ni–Mo–Cr–Fe alloy, of the type currently being considered for use in future molten salt cooled reactors, has been investigated in situ using 1 MeV Kr ions at temperatures of 723 and 973 K. When irradiated to 5 dpa, experimental observations reveal the instantaneous formation and annihilation of point defect clusters, with such processes attributed to the long range elastic interactions that occur between defects through multiple intra-cascade overlap. Corresponding differences in the defect cluster density and size distribution suggest that changes to the microstructure were dependent upon temperature and dose, affecting the growth, accumulation and mobility of irradiation-induced defect clusters under these conditions.

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