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

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. The 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.
Authors:
 [1] ;  [2] ;  [3] ;  [4] ; ORCiD logo [3] ; ORCiD logo [3] ; ORCiD logo [3] ;  [3] ;  [1]
  1. Univ. of Illinois, Urbana-Champaign, IL (United States)
  2. Argonne National Lab. (ANL), Argonne, IL (United States)
  3. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  4. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Queen's Univ., Kingston, ON (Canada)
Publication Date:
Report Number(s):
LA-UR-15-22913
Journal ID: ISSN 0022-3115
Grant/Contract Number:
AC52-06NA25396; AC02-06CH11357; 485363-973000-191100
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 475; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22). Scientific User Facilities Division; USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 42 ENGINEERING; Ferritic martensitic steel; HT-9In-situ tensile test; High-energy X-ray diffraction; Lattice strain; Irradiation embrittlement
OSTI Identifier:
1457236
Alternate Identifier(s):
OSTI ID: 1341163

Tomchik, C., Almer, J., Anderoglu, O., Balogh, L., Brown, Donald William, Clausen, Bjorn, Maloy, Stuart Andrew, Sisneros, Thomas A., and Stubbins, J. F.. High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel. United States: N. p., Web. doi:10.1016/j.jnucmat.2016.03.023.
Tomchik, C., Almer, J., Anderoglu, O., Balogh, L., Brown, Donald William, Clausen, Bjorn, Maloy, Stuart Andrew, Sisneros, Thomas A., & Stubbins, J. F.. High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel. United States. doi:10.1016/j.jnucmat.2016.03.023.
Tomchik, C., Almer, J., Anderoglu, O., Balogh, L., Brown, Donald William, Clausen, Bjorn, Maloy, Stuart Andrew, Sisneros, Thomas A., and Stubbins, J. F.. 2016. "High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel". United States. doi:10.1016/j.jnucmat.2016.03.023. https://www.osti.gov/servlets/purl/1457236.
@article{osti_1457236,
title = {High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel},
author = {Tomchik, C. and Almer, J. and Anderoglu, O. and Balogh, L. and Brown, Donald William and Clausen, Bjorn and Maloy, Stuart Andrew and Sisneros, Thomas A. and Stubbins, J. F.},
abstractNote = {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. The 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.},
doi = {10.1016/j.jnucmat.2016.03.023},
journal = {Journal of Nuclear Materials},
number = C,
volume = 475,
place = {United States},
year = {2016},
month = {3}
}