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Title: Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations

Abstract

FeCrAl ferritic alloys are excellent cladding candidates for accident tolerant fuel systems due to their high resistance to oxidation as a result of formation of a protective Al2O3 scale at high temperatures in steam. In this study, we report the irradiation response of the 10Cr and 13Cr FeCrAl cladding tubes under Fe2+ ion irradiation up to ~16 dpa at 300 °C. Dislocation loop size, density and characteristics were determined using both two beam bright field transmission electron microscopy and on-zone scanning transmission electron microscopy techniques. 10Cr (C06M2) tube has a lower dislocation density, larger grain size and a slightly weaker texture compared to the 13Cr (C36M3) tube before irradiation. After irradiation to 0.7 dpa and 16 dpa, the fraction of <100> type sessile dislocations decreases with increasing Cr amount in the alloys. It has been found that there is neither void formation nor α' precipitation as a result of ion irradiations in either alloy. Therefore, dislocation loops were determined to be the only irradiation induced defects contributing to the hardening. Nanoindentation testing before the irradiation revealed that the average nanohardness of the C36M3 tube is higher than that of the C06M2 tube. The average nanohardness of irradiated tube samples saturatedmore » at 1.6-2.0 GPa hardening for both tubes between ~3.4 dpa and ~16 dpa. The hardening calculated based on transmission electron microscopy was found to be consistent with nanohardness measurements.« less

Authors:
ORCiD logo [1];  [1];  [1];  [1];  [1];  [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1425772
Alternate Identifier(s):
OSTI ID: 1548647
Report Number(s):
LA-UR-18-20922
Journal ID: ISSN 0022-3115; TRN: US1802164
Grant/Contract Number:  
AC52-06NA25396
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 503; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE

Citation Formats

Aydogan, E., Weaver, J. S., Maloy, S. A., El-Atwani, O., Wang, Y. Q., and Mara, N. A. Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations. United States: N. p., 2018. Web. doi:10.1016/j.jnucmat.2018.03.002.
Aydogan, E., Weaver, J. S., Maloy, S. A., El-Atwani, O., Wang, Y. Q., & Mara, N. A. Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations. United States. https://doi.org/10.1016/j.jnucmat.2018.03.002
Aydogan, E., Weaver, J. S., Maloy, S. A., El-Atwani, O., Wang, Y. Q., and Mara, N. A. Fri . "Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations". United States. https://doi.org/10.1016/j.jnucmat.2018.03.002. https://www.osti.gov/servlets/purl/1425772.
@article{osti_1425772,
title = {Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations},
author = {Aydogan, E. and Weaver, J. S. and Maloy, S. A. and El-Atwani, O. and Wang, Y. Q. and Mara, N. A.},
abstractNote = {FeCrAl ferritic alloys are excellent cladding candidates for accident tolerant fuel systems due to their high resistance to oxidation as a result of formation of a protective Al2O3 scale at high temperatures in steam. In this study, we report the irradiation response of the 10Cr and 13Cr FeCrAl cladding tubes under Fe2+ ion irradiation up to ~16 dpa at 300 °C. Dislocation loop size, density and characteristics were determined using both two beam bright field transmission electron microscopy and on-zone scanning transmission electron microscopy techniques. 10Cr (C06M2) tube has a lower dislocation density, larger grain size and a slightly weaker texture compared to the 13Cr (C36M3) tube before irradiation. After irradiation to 0.7 dpa and 16 dpa, the fraction of <100> type sessile dislocations decreases with increasing Cr amount in the alloys. It has been found that there is neither void formation nor α' precipitation as a result of ion irradiations in either alloy. Therefore, dislocation loops were determined to be the only irradiation induced defects contributing to the hardening. Nanoindentation testing before the irradiation revealed that the average nanohardness of the C36M3 tube is higher than that of the C06M2 tube. The average nanohardness of irradiated tube samples saturated at 1.6-2.0 GPa hardening for both tubes between ~3.4 dpa and ~16 dpa. The hardening calculated based on transmission electron microscopy was found to be consistent with nanohardness measurements.},
doi = {10.1016/j.jnucmat.2018.03.002},
journal = {Journal of Nuclear Materials},
number = C,
volume = 503,
place = {United States},
year = {2018},
month = {3}
}

Journal Article:

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Cited by: 3 works
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Figures / Tables:

Fig. 1 Fig. 1: SRIM calculated damage and implanted atom profiles for 45 peak dpa with 5 MeV Fe2+ ions using Kinchin-Pease option at 40 eV displacement energy.

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Works referenced in this record:

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
journal, May 2014


Alumina Scale Formation on a Powder Metallurgical FeCrAl Alloy (Kanthal APMT) at 900–1,100 °C in Dry O2 and in O2 + H2O
journal, September 2009


Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
journal, December 2015


Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors
journal, January 2015


Deformation behaviour of iron-rich iron-aluminum alloys at low temperatures
journal, June 2003


Microstructural stability of Fe–Cr–Al alloys at 450–550 °C
journal, February 2015


Mapping of 475°C embrittlement in ferritic Fe–Cr–Al alloys
journal, November 2010


Phase separation in PM 2000™ Fe-base ODS alloy: Experimental study at the atomic level
journal, August 2008

  • Capdevila, C.; Miller, M. K.; Russell, K. F.
  • Materials Science and Engineering: A, Vol. 490, Issue 1-2
  • DOI: 10.1016/j.msea.2008.01.029

On the α–α′ miscibility gap of Fe–Cr alloys
journal, December 2008


A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels
journal, February 2003


Irradiation-enhanced α′ precipitation in model FeCrAl alloys
journal, April 2016


Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa
journal, November 2017


Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015


Precipitation of α′ in neutron irradiated commercial FeCrAl alloys
journal, January 2018


A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
journal, May 2017


Challenges to the use of ion irradiation for emulating reactor irradiation
journal, April 2015


Synergistic effect of helium and hydrogen for defect evolution under multi-ion irradiation of Fe–Cr ferritic alloys
journal, August 2004


On the use of SRIM for computing radiation damage exposure
journal, September 2013

  • Stoller, R. E.; Toloczko, M. B.; Was, G. S.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 310
  • DOI: 10.1016/j.nimb.2013.05.008

A review of nanoindentation continuous stiffness measurement technique and its applications
journal, February 2002


Continuous Stiffness Measurement During Instrumented Indentation Testing
journal, January 2010


Measurement of hardness and elastic modulus by instrumented indentation: Advances in understanding and refinements to methodology
journal, January 2004


Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions
journal, April 2017


Comparison of preparation techniques for nuclear materials for transmission electron microscopy (TEM)
journal, April 2015


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

Effect of shock loading on the microstructure, mechanical properties and grain boundary characteristics of HT-9 ferritic/martensitic steels
journal, January 2016


Microstructure examination of Fe–14Cr ODS ferritic steels produced through different processing routes
journal, August 2014


Texture evolution in pure aluminum subjected to monotonous and reversal straining in high-pressure torsion
journal, May 2009


Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys
journal, April 2016


TEM characterization of dislocation loops in irradiated bcc Fe-based steels
journal, March 2013


-Loop characterization in α-Fe: comparison between experiments and modeling
journal, December 2002


Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress
journal, January 2008


An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments
journal, June 1992

  • Oliver, W. C.; Pharr, G. M.
  • Journal of Materials Research, Vol. 7, Issue 06, p. 1564-1583
  • DOI: 10.1557/JMR.1992.1564

Understanding the effects of ion irradiation using nanoindentation techniques
journal, July 2015


Nanoindentation of model Fe–Cr alloys with self-ion irradiation
journal, February 2013


A model of size effects in nano-indentation
journal, August 2006

  • Huang, Y.; Zhang, F.; Hwang, K.
  • Journal of the Mechanics and Physics of Solids, Vol. 54, Issue 8
  • DOI: 10.1016/j.jmps.2006.02.002

The correlation of the indentation size effect measured with indenters of various shapes
journal, April 2002

  • Swadener, J. G.; George, E. P.; Pharr, G. M.
  • Journal of the Mechanics and Physics of Solids, Vol. 50, Issue 4
  • DOI: 10.1016/S0022-5096(01)00103-X

Indentation size effects in crystalline materials: A law for strain gradient plasticity
journal, March 1998


The Indentation Size Effect: A Critical Examination of Experimental Observations and Mechanistic Interpretations
journal, June 2010


Influences of pileup on the measurement of mechanical properties by load and depth sensing indentation techniques
journal, April 1998


Effect of the α γ Phase Transition on the Stability of Dislocation Loops in bcc Iron
journal, April 2008


The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures
journal, December 2010

  • Yao, Z.; Jenkins, M. L.; Hernández-Mayoral, M.
  • Philosophical Magazine, Vol. 90, Issue 35-36
  • DOI: 10.1080/14786430903430981

Dynamic observations of heavy-ion damage in Fe and Fe–Cr alloys
journal, May 2009


Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys
journal, September 2017


Effects of alloying elements (Mo, Si) in an austenitic stainless steel on dislocation loop nucleation under ion irradiation
journal, December 1993


Depth distribution of Frank loop defects formed in ion-irradiated stainless steel and its dependence on Si addition
journal, December 2015

  • Chen, Dongyue; Murakami, Kenta; Dohi, Kenji
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 365
  • DOI: 10.1016/j.nimb.2015.08.029

Segregation behavior in proton- and heavy-ion-irradiated ferritic–martensitic alloys
journal, June 2011


Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys
journal, March 2013


Modelling the diffusion of self-interstitial atom clusters in Fe-Cr alloys
journal, January 2008


Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses
journal, July 2008


Mechanism of Formation and Growth of 100 Interstitial Loops in Ferritic Materials
journal, June 2002


Direct observation of the coalescence process between nanoscale dislocation loops with different Burgers vectors
journal, January 2011


Theory of transitions in dose dependence of radiation effects in structural alloys
journal, November 1993


Correlation of neutron and heavy-ion damage
journal, November 1978


Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
journal, June 2017


Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors
journal, December 2012

  • Anderoglu, Osman; Byun, Thak Sang; Toloczko, Mychailo
  • Metallurgical and Materials Transactions A, Vol. 44, Issue S1
  • DOI: 10.1007/s11661-012-1565-y

The evolution of mechanical property change in irradiated austenitic stainless steels
journal, November 1993


On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials
journal, December 2000


Modeling the microstructure–mechanical property relationship for a 12Cr–2W–V–Mo–Ni power plant steel
journal, November 2003


The relationship between hardness and yield stress in irradiated austenitic and ferritic steels
journal, February 2005


Low-activation ferritic and martensitic steels for fusion application
journal, October 1996


Effect of Cr on the mechanical properties and microstructure of Fe–Cr model alloys after n-irradiation
journal, June 2008


Phase stability of an HT-9 duct irradiated in FFTF
journal, November 2012


α′ precipitation in neutron-irradiated Fe–Cr alloys
journal, March 2014


Intra granular precipitation and grain boundary segregation under neutron irradiation in a low purity Fe–Cr based alloy
journal, June 2012


Cr precipitation in neutron irradiated industrial purity Fe–Cr model alloys
journal, January 2013


Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys
journal, July 2015


Behaviour of P, Si, Ni impurities and Cr in self ion irradiated Fe–Cr alloys – Comparison to neutron irradiation
journal, January 2015


Works referencing / citing this record:

α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys
journal, June 2019