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This content will become publicly available on April 15, 2019

Title: Radiation resistance of oxide dispersion strengthened alloys: Perspectives from in situ observations and rate theory calculations

Here, in situ ion irradiation and rate theory calculations were employed to directly compare the radiation resistance of an oxide dispersion strengthened alloy with that of a conventional ferritic/martensitic alloy. Compared to the rapid buildup of dislocation loops, loop growth, and formation of network dislocations in the conventional ferritic/martensitic alloy, the superior radiation resistance of the oxide dispersion strengthened alloy is manifested by its stable dislocation structure under the same irradiation conditions. Thus, the results are consistent with rate theory calculations, which show that high-density nanoparticles can significantly reduce freely migrating defects and suppress the buildup of clustered defects.
Authors:
 [1] ;  [2] ;  [2] ;  [2] ;  [3] ;  [4] ; ORCiD logo [5] ;  [6]
  1. Univ. of Illinois, Urbana, IL (United States). Dept. of Nuclear, Plasma, and Radiological Engineering
  2. Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division
  3. Qingdao Univ. of Technology, Shandong (China)
  4. Hokkaido Univ., Sapporo (Japan). Materials Science and Engineering
  5. Los Alamos National Lab. (LANL), Los Alamos, NM (United States).
  6. Univ. of Illinois, Urbana, IL (United States). Dept. of Nuclear, Plasma, and Radiological Engineering; Kyushu Univ. (Japan). International Inst. for Carbon Neutral Energy Research (WPI-I2CNER)
Publication Date:
Report Number(s):
LA-UR-18-20960
Journal ID: ISSN 1359-6462
Grant/Contract Number:
AC52-06NA25396; NE0008291; AC02-06CH11357; AC07-051D14517
Type:
Accepted Manuscript
Journal Name:
Scripta Materialia
Additional Journal Information:
Journal Volume: 148; Journal Issue: C; Journal ID: ISSN 1359-6462
Publisher:
Elsevier
Research Org:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org:
USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE). Nuclear Energy University Program (NEUP)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; Oxide dispersion strengthened (ODS) alloy; Dislocation structure; Microstructure; Transmission electron microscopy; Radiation enhanced diffusion (RED)
OSTI Identifier:
1422905