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Title: The effect of secondary phases on microstructure and irradiation damage in an as-built additively manufactured 316 L stainless steel with a hafnium compositional gradient

Journal Article · · Journal of Nuclear Materials
ORCiD logo [1]; ORCiD logo [2];  [3]; ORCiD logo [4];  [5];  [6];  [2];  [7]
  1. Texas A & M University, College Station, TX (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  2. Purdue University, West Lafayette, IN (United States)
  3. University of Michigan, Ann Arbor, MI (United States)
  4. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  5. University of Wisconsin-Madison, MI (United States)
  6. Texas A & M University, College Station, TX (United States)
  7. Idaho National Laboratory (INL), Idaho Falls, ID (United States); North Carolina State University, Raleigh, NC (United States)

Additive manufacturing (AM) or rapid prototyping has become a crucial tool for reducing both cost and time while increasing efficiency in qualifying structural materials for reactor use. In this study, directed energy deposition (DED) was used to develop an as-built 316 L stainless steel sample with three regions of increasing Hf-dopant to study the effects of Hf on the irradiation response of the material. Morphological and microstructural changes were analyzed before and after 2 MeV proton irradiation at 360 °C to a damage of 2.5 dpa at ~ 10 µm below the surface. The addition of Hf effectively suppressed radiation-induced damage (dislocation loops, radiation-induced segregation) due to enhanced point defect recombination. The radiation damage seen in the as-built sample was further compared to a thermo-mechanically treated counterpart of the same fabrication and irradiation parameters which was found to behave superiorly. In conclusion, the increased radiation resistance of this material may be attributed to the as-built microstructure, which includes undissolved Hf particles, delta ferrite grains and cellular sub-grain boundaries that can hinder defect motion.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2274954
Alternate ID(s):
OSTI ID: 2368882
Report Number(s):
INL/JOU-23-71665-Rev000; TRN: US2408107
Journal Information:
Journal of Nuclear Materials, Vol. 587; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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