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Title: Understanding radiation effects in friction stir welded MA956 using ion irradiation and a rate theory model

Abstract

We report an outstanding challenge in the manufacturing and joining of oxide dispersion strengthened steels is retaining the nanofeatures in the alloy throughout the fabrication and welding process. MA956 was friction stir welded with two different sets of welding parameters, resulting in a medium and high heat input. After welding, 5 MeV Fe++ ion irradiations were performed at doses ranging from 50 to 200 dpa in the temperature range of 400 to 500°C. Post-irradiation characterization was performed with scanning transmission electron microscopy and energy-dispersive x-ray spectroscopy to investigate the Y-Al-O dispersoids, voids, and dislocations. After welding, the dispersoid microstructure coarsened, resulting in fewer and larger dispersoids regardless of heat input. After irradiation, the dispersoid behavior in the welded material was sensitive to temperature, exhibiting growth behavior attributed to Ostwald coarsening at 500 °C but a mixture of nucleation and more muted growth at 400 and 450 °C, attributed to competing mechanisms of radiation-enhanced diffusion and Ostwald coarsening. Void swelling correlated to heat input; being more prevalent in the welded conditions occurring at lower doses and in higher values relative to the base material. The low values of swelling despite microstructure coarsening caused by welding demonstrate the excellent swelling resistance ofmore » MA956, even after welding with the highest swelling values of 0.5% noted in the stir zone high heat input condition at 450 °C, 200 dpa. The dislocation behavior was inconsistent: the strongest trend was that network density was higher for welded versus base material, and an increase in loop diameter with temperature was observed. A rate theory model based on the observed microstructure suggests at high temperature interstitial loss to sinks was more likely to be dominant compared to mutual annihilation via point defect recombination, because of an increase of the radiation diffusion coefficient with temperature regardless of initial welded microstructure.« less

Authors:
 [1];  [1];  [1];  [2];  [1]
  1. US Naval Academy, Annapolis, MD (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE); Defense Threat Reduction Agency (DTRA)
OSTI Identifier:
1860569
Alternate Identifier(s):
OSTI ID: 1840783
Grant/Contract Number:  
AC05-00OR22725; AC07–051D14517; 17-1032; 17-906; 18-1396; AC07-051D14517
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 561; Journal Issue: 1; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; friction stir welding; MA956; ion irradiation; microstructure characterization; oxide dispersion strengthened steel; scanning transmission electron microscopy

Citation Formats

Getto, E., Nathan, N., McMahan, J., Taller, S. A., and Baker, B. Understanding radiation effects in friction stir welded MA956 using ion irradiation and a rate theory model. United States: N. p., 2022. Web. doi:10.1016/j.jnucmat.2022.153530.
Getto, E., Nathan, N., McMahan, J., Taller, S. A., & Baker, B. Understanding radiation effects in friction stir welded MA956 using ion irradiation and a rate theory model. United States. https://doi.org/10.1016/j.jnucmat.2022.153530
Getto, E., Nathan, N., McMahan, J., Taller, S. A., and Baker, B. Tue . "Understanding radiation effects in friction stir welded MA956 using ion irradiation and a rate theory model". United States. https://doi.org/10.1016/j.jnucmat.2022.153530. https://www.osti.gov/servlets/purl/1860569.
@article{osti_1860569,
title = {Understanding radiation effects in friction stir welded MA956 using ion irradiation and a rate theory model},
author = {Getto, E. and Nathan, N. and McMahan, J. and Taller, S. A. and Baker, B.},
abstractNote = {We report an outstanding challenge in the manufacturing and joining of oxide dispersion strengthened steels is retaining the nanofeatures in the alloy throughout the fabrication and welding process. MA956 was friction stir welded with two different sets of welding parameters, resulting in a medium and high heat input. After welding, 5 MeV Fe++ ion irradiations were performed at doses ranging from 50 to 200 dpa in the temperature range of 400 to 500°C. Post-irradiation characterization was performed with scanning transmission electron microscopy and energy-dispersive x-ray spectroscopy to investigate the Y-Al-O dispersoids, voids, and dislocations. After welding, the dispersoid microstructure coarsened, resulting in fewer and larger dispersoids regardless of heat input. After irradiation, the dispersoid behavior in the welded material was sensitive to temperature, exhibiting growth behavior attributed to Ostwald coarsening at 500 °C but a mixture of nucleation and more muted growth at 400 and 450 °C, attributed to competing mechanisms of radiation-enhanced diffusion and Ostwald coarsening. Void swelling correlated to heat input; being more prevalent in the welded conditions occurring at lower doses and in higher values relative to the base material. The low values of swelling despite microstructure coarsening caused by welding demonstrate the excellent swelling resistance of MA956, even after welding with the highest swelling values of 0.5% noted in the stir zone high heat input condition at 450 °C, 200 dpa. The dislocation behavior was inconsistent: the strongest trend was that network density was higher for welded versus base material, and an increase in loop diameter with temperature was observed. A rate theory model based on the observed microstructure suggests at high temperature interstitial loss to sinks was more likely to be dominant compared to mutual annihilation via point defect recombination, because of an increase of the radiation diffusion coefficient with temperature regardless of initial welded microstructure.},
doi = {10.1016/j.jnucmat.2022.153530},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 561,
place = {United States},
year = {Tue Jan 11 00:00:00 EST 2022},
month = {Tue Jan 11 00:00:00 EST 2022}
}

Works referenced in this record:

Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel
journal, April 2013


Emulation of reactor irradiation damage using ion beams
journal, October 2014


Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation
journal, March 2008


Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix
journal, October 1993


Microstructure and mechanical properties of friction stir welded oxide dispersion strengthened alloy
journal, January 2013


Formation of Y2O3 nanoclusters in nano-structured ferritic alloys: Modeling of precipitation kinetics and yield strength
journal, July 2010


Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations
journal, April 2017


Applications of the FIB lift-out technique for TEM specimen preparation
journal, May 1998


Microstructure evolution of T91 irradiated in the BOR60 fast reactor
journal, June 2018


Stability of nano-oxides upon heavy ion irradiation of an ODS material
journal, October 2011


The influence of helium on cavity evolution in ion-irradiated T91
journal, October 2018


Joining of Oxide Dispersion Strengthened Steels for Advanced Reactors
journal, November 2014


Ion-irradiation effects on dissimilar friction stir welded joints between ODS alloy and ferritic stainless steel
journal, December 2014


Friction stir welding and processing
journal, August 2005


Atomic number dependence of Z contrast in scanning transmission electron microscopy
journal, August 2018


Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels
journal, November 2016


Interfaces under ion irradiation: growth and taming of nanostructures
journal, June 2003

  • Heinig, K. H.; M�ller, T.; Schmidt, B.
  • Applied Physics A: Materials Science & Processing, Vol. 77, Issue 1
  • DOI: 10.1007/s00339-002-2061-9

Cu-precipitation kinetics in α Fe from atomistic simulations: Vacancy-trapping effects and Cu-cluster mobility
journal, December 2007


Microstructures and ion-irradiation behaviour of friction stir welded 12Cr-ODS steel
journal, May 2017


SRIM – The stopping and range of ions in matter (2010)
journal, June 2010

  • Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12
  • DOI: 10.1016/j.nimb.2010.02.091

Formation energy of vacancies in FeCr alloys: Dependence on Cr concentration
journal, January 2011


Radiation response of oxide-dispersion-strengthened alloy MA956 after self-ion irradiation
journal, October 2017

  • Chen, Tianyi; Kim, Hyosim; Gigax, Jonathan G.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 409
  • DOI: 10.1016/j.nimb.2017.05.024

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
journal, June 2017


On the use of transmission electron microscopy to quantify dislocation densities in bulk metals
journal, March 2020


Stress-induced diffusion of point defects to voids
journal, November 1973


In situ TEM study of the stability of nano-oxides in ODS steels under ion-irradiation
journal, September 2012


Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa
journal, October 2014


The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels
journal, February 2017


14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation
journal, December 1990


Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys
journal, October 2015


Molecular statics calculations of the biases and point defect capture volumes of small cavities
journal, February 2018


EELS log-ratio technique for specimen-thickness measurement in the TEM
journal, February 1988

  • Malis, T.; Cheng, S. C.; Egerton, R. F.
  • Journal of Electron Microscopy Technique, Vol. 8, Issue 2
  • DOI: 10.1002/jemt.1060080206

Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications
journal, February 2020


Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment
book, January 1976

  • Smidt, F. A.; Malmberg, P. R.; Sprague, J. A.
  • Irradiation Effects on The Microstructure and Properties of Metals
  • DOI: 10.1520/STP38051S

Carbon–vacancy complexes as traps for self-interstitial clusters in Fe–C alloys
journal, September 2013


Microstructural evolution in friction stir welding of nanostructured ODS alloys
journal, August 2010


Influence of high dose neutron irradiation on microstructure of EP-450 ferritic–martensitic steel irradiated in three Russian fast reactors
journal, August 2004


Effects of grain boundary misorientation on the solute segregation in austenitic stainless steels
journal, October 1998


A review of the irradiation evolution of dispersed oxide nanoparticles in the b.c.c. Fe-Cr system: Current understanding and future directions
journal, April 2017


Selection of fuel cladding material for nuclear fission reactors
journal, December 2011


Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9
journal, July 2015


Microstructural examination of commercial ferritic alloys at 200 dpa
journal, October 1996


Dual-beam irradiation of friction stir spot welding of nanostructured ferritic oxide dispersion strengthened alloy
journal, September 2012


Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation
journal, December 2015


Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
journal, April 2015

  • Parish, Chad M.; Field, Kevin G.; Certain, Alicia G.
  • Journal of Materials Research, Vol. 30, Issue 9
  • DOI: 10.1557/jmr.2015.32

Irradiation response of ODS ferritic steels to high-energy Ne ions at HIRFL
journal, December 2014


The mechanism of radiation-induced segregation in ferritic–martensitic alloys
journal, February 2014