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Title: Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature

Journal Article · · Journal of Materials Research
DOI:https://doi.org/10.1557/jmr.2015.99· OSTI ID:1265501
 [1];  [2];  [3];  [4];  [5];  [6];  [7];  [8];  [9];  [10];  [11];  [5];  [6];  [12]
  1. Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics
  2. Univ. of South Carolina, Columbia, SC (United States). Dept. of Mechanical Engineering
  3. Boise State Univ., ID (United States). Dept. of Materials Science & Engineering
  4. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Materials Science and Engineering
  5. Pennsylvania State Univ., University Park, PA (United States). Dept. of Mechanical and Nuclear Engineering
  6. Univ. of Tennessee, Knoxville, TN (United States). Dept. of Nuclear Engineering
  7. Univ. of Wisconsin-Madison, Madison, WI (United States). Dept. of Materials Science & Engineering
  8. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
  9. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  10. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Materials Science & Engineering
  11. Univ. of Wisconsin-Madison, Madison, WI (United States). Dept. of Materials Science & Engineering
  12. Univ. of Florida, Gainesville, FL (United States). Dept. of Nuclear Engineering

Designing materials for performance in high-radiation fields can be accelerated through a carefully chosen combination of advanced multiscale modeling paired with appropriate experimental validation. Here, the studies reported in this work, the combined efforts of six universities working together as the Consortium on Cladding and Structural Materials, use that approach to focus on improving the scientific basis for the response of ferritic–martensitic steels to irradiation. A combination of modern modeling techniques with controlled experimentation has specifically focused on improving the understanding of radiation-induced segregation, precipitate formation and growth under radiation, the stability of oxide nanoclusters, and the development of dislocation networks under radiation. Experimental studies use both model and commercial alloys, irradiated with both ion beams and neutrons. Lastly, transmission electron microscopy and atom probe are combined with both first-principles and rate theory approaches to advance the understanding of ferritic–martensitic steels.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1265501
Journal Information:
Journal of Materials Research, Vol. 30, Issue 09; ISSN 0884-2914
Publisher:
Materials Research SocietyCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 27 works
Citation information provided by
Web of Science

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