The mechanism of Zr and Hf in reducing radiation-induced segregation in 316 stainless steel

M. J. Hackett; J. T. Busby; G. S. Was

doi:10.1007/s11661-007-9296-1

The mechanism of Zr and Hf in reducing radiation-induced segregation in 316 stainless steel

M. J. Hackett, J. T. Busby, G. S. Was

Isotope Sci & Eng Directorate

Research output: Contribution to journal › Article › peer-review

15 Scopus citations

Abstract

The addition of oversized solutes has the potential to reduce the effects of radiation-induced segregation (RIS) in austenitic alloys. This RIS has been implicated as one of several factors in enhancing stress corrosion cracking (SCC) under irradiation, so oversized solute additions could promote SCC resistance. Either Zr or Hf was added to 316-type stainless steel, at levels between 0.05 and 0.37 at. pct. Samples were irradiated with 3 MeV protons to 3 dpa at 400 °C and analyzed using high-resolution-scanning transmission electron microscopy (HR-STEM) with energy-dispersive X-ray spectroscopy (EDS), to measure the grain-boundary (GB) composition. The Zr additions substantially reduced the amount of RIS, while the Hf was much less effective. Despite similar sizes, first-principles calculations using the Vienna Ab Initio Simulation Package (VASP) demonstrate that solute-vacancy binding for Zr is 1.05 eV vs 0.69 eV for Hf. This difference results in the greater effectiveness of Zr in reducing RIS, as determined by kinetic rate theory calculations, in agreement with experimentally-measured results.

Original language	English
Pages (from-to)	218-224
Number of pages	7
Journal	Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science
Volume	39
Issue number	2
DOIs	https://doi.org/10.1007/s11661-007-9296-1
State	Published - Feb 2008

Funding

This research was supported by the United States Department of Energy (DOE) under Grant No. DE-FG07-03ID14542. This research was also performed under appointment to the Naval Nuclear Propulsion Fellowship Program, sponsored by the Naval Reactors Division of the U.S. DOE. A portion of this research was conducted at the Oak Ridge National Laboratory, which is sponsored by the Division of Scientific User Facilities, Office of Basic Energy Sciences, U.S. DOE. The authors thank Victor Rotberg and Ovidiu Toader, Michigan Ion Beam Laboratory, Lockheed Martin, and Julie Tucker, the University of Wisconsin–Madison.

Funders	Funder number
Division of Scientific User Facilities
Office of Basic Energy Sciences
U.S. DOE
United States Department of Energy
U.S. Department of Energy
Office of Naval Reactors

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abstract = "The addition of oversized solutes has the potential to reduce the effects of radiation-induced segregation (RIS) in austenitic alloys. This RIS has been implicated as one of several factors in enhancing stress corrosion cracking (SCC) under irradiation, so oversized solute additions could promote SCC resistance. Either Zr or Hf was added to 316-type stainless steel, at levels between 0.05 and 0.37 at. pct. Samples were irradiated with 3 MeV protons to 3 dpa at 400 °C and analyzed using high-resolution-scanning transmission electron microscopy (HR-STEM) with energy-dispersive X-ray spectroscopy (EDS), to measure the grain-boundary (GB) composition. The Zr additions substantially reduced the amount of RIS, while the Hf was much less effective. Despite similar sizes, first-principles calculations using the Vienna Ab Initio Simulation Package (VASP) demonstrate that solute-vacancy binding for Zr is 1.05 eV vs 0.69 eV for Hf. This difference results in the greater effectiveness of Zr in reducing RIS, as determined by kinetic rate theory calculations, in agreement with experimentally-measured results.",

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The mechanism of Zr and Hf in reducing radiation-induced segregation in 316 stainless steel

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