High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel

C. Tomchik, J. Almer, O. Anderoglu, L. Balogh, D. W. Brown, B. Clausen, S. A. Maloy, T. A. Sisneros, J. F. Stubbins

Research output: Contribution to journalArticle


Samples harvested from an HT-9 fuel test assembly (ACO-3) irradiated for six years in the Fast Flux Test Facility (FFTF) reaching 2-147 dpa at 382-504°C were deformed in-situ while collecting high-energy X-ray diffraction data to monitor microstructure evolution. With the initiation of plastic deformation, all samples exhibited a clear load transfer from the ferrite matrix to carbide particulate. This behavior was confirmed by modeling of the control material. The evolution of dislocation density in the material as a result of deformation was characterized through full pattern line profile analysis. The dislocation densities increased substantially after deformation, the level of dislocation evolution observed was highly dependent upon the irradiation temperature of the sample. Differences in both the yield and hardening behavior between samples irradiated at higher and lower temperatures suggest the existence of a transition in tensile behavior at an irradiation temperature near 420°C dividing regions of distinct damage effects.

Original languageEnglish (US)
Pages (from-to)46-56
Number of pages11
JournalJournal of Nuclear Materials
StatePublished - Jul 1 2016



  • Ferritic martensitic steel
  • HT-9
  • High-energy X-ray diffraction
  • In-situ tensile test
  • Irradiation embrittlement
  • Lattice strain

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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