Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation
Abstract
In this work, ferritic-martensitic (F/M) HT9 along with fully ferritic HT9 specimens were irradiated using self-ions to 600 peak displacement-per-atom (dpa) at 450 °C. To investigate and minimize the carbon contamination effect on void swelling, two identical F/M HT9 specimens were prepared: one without a coating and the other one with a tungsten and silver coating on the surface prior to irradiation. The specimen without a coating showed carbide formation in the matrix, resulting from carbon contamination during irradiation, with no voids observed. The coated sample did not form matrix carbides, and voids were observed within the irradiated region. The same coating was applied to the ferritic HT9, and void swelling results of both the F/M HT9 and the ferritic HT9 alloys were compared after irradiation. The F/M HT9 exhibited a maximum of 2.6% swelling, while the ferritic HT9 showed a maximum of 0.8% swelling at a 400–500 nm depth, equivalent to 334 local dpa. The results were correlated with the instability of carbides in the ferritic HT9 under irradiation. Carbides in the F/M HT9 and the ferritic HT9 are both M23C6, but the matrix carbides in the ferritic HT9 were less stable under the irradiation, compared to the onesmore »
- Authors:
-
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Publication Date:
- Research Org.:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Center for Integrated Nanotechnologies (CINT)
- Sponsoring Org.:
- USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC); USDOE National Nuclear Security Administration (NNSA)
- OSTI Identifier:
- 1762736
- Alternate Identifier(s):
- OSTI ID: 1778605; OSTI ID: 1778773
- Report Number(s):
- LA-UR-20-26535
Journal ID: ISSN 1044-5803
- Grant/Contract Number:
- 89233218CNA000001
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Materials Characterization
- Additional Journal Information:
- Journal Volume: 173; Journal ID: ISSN 1044-5803
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE
Citation Formats
Kim, Hyosim, Gigax, Jonathan Gregory, El-Atwani, Osman, Chancey, Matthew Ryan, Baldwin, Jon Kevin Scott, Wang, Yongqiang, and Maloy, Stuart Andrew. Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation. United States: N. p., 2021.
Web. doi:10.1016/j.matchar.2021.110908.
Kim, Hyosim, Gigax, Jonathan Gregory, El-Atwani, Osman, Chancey, Matthew Ryan, Baldwin, Jon Kevin Scott, Wang, Yongqiang, & Maloy, Stuart Andrew. Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation. United States. https://doi.org/10.1016/j.matchar.2021.110908
Kim, Hyosim, Gigax, Jonathan Gregory, El-Atwani, Osman, Chancey, Matthew Ryan, Baldwin, Jon Kevin Scott, Wang, Yongqiang, and Maloy, Stuart Andrew. Sat .
"Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation". United States. https://doi.org/10.1016/j.matchar.2021.110908. https://www.osti.gov/servlets/purl/1762736.
@article{osti_1762736,
title = {Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation},
author = {Kim, Hyosim and Gigax, Jonathan Gregory and El-Atwani, Osman and Chancey, Matthew Ryan and Baldwin, Jon Kevin Scott and Wang, Yongqiang and Maloy, Stuart Andrew},
abstractNote = {In this work, ferritic-martensitic (F/M) HT9 along with fully ferritic HT9 specimens were irradiated using self-ions to 600 peak displacement-per-atom (dpa) at 450 °C. To investigate and minimize the carbon contamination effect on void swelling, two identical F/M HT9 specimens were prepared: one without a coating and the other one with a tungsten and silver coating on the surface prior to irradiation. The specimen without a coating showed carbide formation in the matrix, resulting from carbon contamination during irradiation, with no voids observed. The coated sample did not form matrix carbides, and voids were observed within the irradiated region. The same coating was applied to the ferritic HT9, and void swelling results of both the F/M HT9 and the ferritic HT9 alloys were compared after irradiation. The F/M HT9 exhibited a maximum of 2.6% swelling, while the ferritic HT9 showed a maximum of 0.8% swelling at a 400–500 nm depth, equivalent to 334 local dpa. The results were correlated with the instability of carbides in the ferritic HT9 under irradiation. Carbides in the F/M HT9 and the ferritic HT9 are both M23C6, but the matrix carbides in the ferritic HT9 were less stable under the irradiation, compared to the ones on the grain boundaries in the F/M HT9. The study shows the impact of chemistry on the void swelling which overpowers the microstructural factors such as grain size and phase.},
doi = {10.1016/j.matchar.2021.110908},
journal = {Materials Characterization},
number = ,
volume = 173,
place = {United States},
year = {Sat Jan 16 00:00:00 EST 2021},
month = {Sat Jan 16 00:00:00 EST 2021}
}
Works referenced in this record:
Materials challenges in nuclear energy
journal, February 2013
- Zinkle, S. J.; Was, G. S.
- Acta Materialia, Vol. 61, Issue 3
Structural materials for fission & fusion energy
journal, November 2009
- Zinkle, Steven J.; Busby, Jeremy T.
- Materials Today, Vol. 12, Issue 11
Designing Radiation Resistance in Materials for Fusion Energy
journal, July 2014
- Zinkle, S. J.; Snead, L. L.
- Annual Review of Materials Research, Vol. 44, Issue 1
Ferritic/martensitic steels for next-generation reactors
journal, September 2007
- Klueh, R. L.; Nelson, A. T.
- Journal of Nuclear Materials, Vol. 371, Issue 1-3
Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors
journal, October 2005
- Klueh, R. L.
- International Materials Reviews, Vol. 50, Issue 5
Microstructural analysis of neutron-irradiated martensitic steels
journal, June 1996
- Kai, J. J.; Klueh, R. L.
- Journal of Nuclear Materials, Vol. 230, Issue 2
Microstructural examination of commercial ferritic alloys at 200 dpa
journal, October 1996
- Gelles, D. S.
- Journal of Nuclear Materials, Vol. 233-237
Development of martensitic steels for high neutron damage applications
journal, December 1996
- Gelles, D. S.
- Journal of Nuclear Materials, Vol. 239
Development of radiation resistant materials for advanced nuclear power plant
journal, May 2006
- Little, E. A.
- Materials Science and Technology, Vol. 22, Issue 5, p. 491-518
Microstructural evolution in irradiated ferritic-martensitic steels: transitions to high dose behaviour
journal, November 1993
- Little, E. A.
- Journal of Nuclear Materials, Vol. 206, Issue 2-3
Ferritic/martensitic steels – overview of recent results
journal, December 2002
- Klueh, R. L.; Gelles, D. S.; Jitsukawa, S.
- Journal of Nuclear Materials, Vol. 307-311
Progress and critical issues of reduced activation ferritic/martensitic steel development
journal, December 2000
- van der Schaaf, B.; Gelles, D. S.; Jitsukawa, S.
- Journal of Nuclear Materials, Vol. 283-287
On mechanisms controlling swelling in ferritic and martensitic alloys
journal, July 1988
- Odette, G. R.
- Journal of Nuclear Materials, Vol. 155-157
Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C
journal, September 2009
- Sencer, B. H.; Kennedy, J. R.; Cole, J. I.
- Journal of Nuclear Materials, Vol. 393, Issue 2
Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF
journal, July 2011
- Sencer, B. H.; Kennedy, J. R.; Cole, J. I.
- Journal of Nuclear Materials, Vol. 414, Issue 2
Phase stability of an HT-9 duct irradiated in FFTF
journal, November 2012
- Anderoglu, O.; Van den Bosch, J.; Hosemann, P.
- Journal of Nuclear Materials, Vol. 430, Issue 1-3
Irradiation Effects of ht-9 Martensitic Steel
journal, June 2013
- Chen, Yiren
- Nuclear Engineering and Technology, Vol. 45, Issue 3
The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels
journal, February 2017
- Getto, E.; Vancoevering, G.; Was, G. S.
- Journal of Nuclear Materials, Vol. 484
Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9
journal, July 2015
- Getto, E.; Jiao, Z.; Monterrosa, A. M.
- Journal of Nuclear Materials, Vol. 462
Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels
journal, November 2016
- Getto, E.; Sun, K.; Monterrosa, A. M.
- Journal of Nuclear Materials, Vol. 480
Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage
journal, July 1983
- Garner, F. A.
- Journal of Nuclear Materials, Vol. 117
Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions
journal, October 2014
- Shao, Lin; Wei, C. -C.; Gigax, J.
- Journal of Nuclear Materials, Vol. 453, Issue 1-3
The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 °C
journal, October 2015
- Gigax, Jonathan G.; Aydogan, Eda; Chen, Tianyi
- Journal of Nuclear Materials, Vol. 465
Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys
journal, October 2015
- Getto, E.; Jiao, Z.; Monterrosa, A. M.
- Journal of Nuclear Materials, Vol. 465
Beam-contamination-induced compositional alteration and its neutron-atypical consequences in ion simulation of neutron-induced void swelling
journal, May 2017
- Gigax, Jonathan G.; Kim, Hyosim; Aydogan, Eda
- Materials Research Letters, Vol. 5, Issue 7
Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials
journal, October 2017
- Shao, Lin; Gigax, Jonathan; Chen, Di
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 409
Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9
journal, April 2019
- Gigax, Jonathan G.; Kim, Hyosim; Aydogan, E.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 444
Resolution of the carbon contamination problem in ion irradiation experiments
journal, December 2017
- Was, G. S.; Taller, S.; Jiao, Z.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 412
Carbon Contamination During Ion Irradiation - Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels
journal, November 2017
- Wang, Jing; Toloczko, Mychailo B.; Kruska, Karen
- Scientific Reports, Vol. 7, Issue 1
Characterization of M2X formed during 5 MeV Fe2+ irradiation
journal, March 2017
- Getto, E.; Sun, K.; Was, G. S.
- Journal of Nuclear Materials, Vol. 485
Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels
journal, January 2016
- Kupriiyanova, Y. E.; Bryk, V. V.; Borodin, O. V.
- Journal of Nuclear Materials, Vol. 468
Grain boundary structure and properties under external influences
journal, September 1986
- Valiev, R. Z.; Gertsman, V. Yu.; Kaibyshev, O. A.
- physica status solidi (a), Vol. 97, Issue 1
Achieving Radiation Tolerance through Non-Equilibrium Grain Boundary Structures
journal, September 2017
- Vetterick, Gregory A.; Gruber, Jacob; Suri, Pranav K.
- Scientific Reports, Vol. 7, Issue 1
Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission
journal, March 2010
- Bai, X. M.; Voter, A. F.; Hoagland, R. G.
- Science, Vol. 327, Issue 5973
Temperature and Dose Dependence of Swelling in 10% and 20% Cold-Worked Type 316 Stainless Steels
journal, November 1983
- Terasawa, Mititaka; Nakahigashi, Shigeo; Koyama, Masahiro
- Journal of Nuclear Science and Technology, Vol. 20, Issue 11
Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions
journal, April 2017
- Aydogan, E.; Chen, T.; Gigax, J. G.
- Journal of Nuclear Materials, Vol. 487
Void swelling of an oxide dispersion strengthened ferritic alloy in a high voltage electron microscope
journal, March 1980
- Snykers, M.
- Journal of Nuclear Materials, Vol. 89, Issue 1
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
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
Evaluation of effective threshold displacement energies and other data required for the calculation of advanced atomic displacement cross-sections
journal, September 2017
- Konobeyev, A. Yu.; Fischer, U.; Korovin, Yu. A.
- Nuclear Energy and Technology, Vol. 3, Issue 3
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations
journal, January 2018
- Zinkle, S. J.; Snead, L. L.
- Scripta Materialia, Vol. 143
Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling
journal, November 2016
- Wang, Jing; Toloczko, Mychailo B.; Bailey, Nathan
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 387
Challenges to the use of ion irradiation for emulating reactor irradiation
journal, April 2015
- Was, Gary S.
- Journal of Materials Research, Vol. 30, Issue 9
Modeling injected interstitial effects on void swelling in self-ion irradiation experiments
journal, April 2016
- Short, M. P.; Gaston, D. R.; Jin, M.
- Journal of Nuclear Materials, Vol. 471
The resistivity recovery of high purity and carbon doped iron following low temperature electron irradiation
journal, January 1983
- Takaki, S.; Fuss, J.; Kuglers, H.
- Radiation Effects, Vol. 79, Issue 1-4
The Ag−C (Silver-Carbon) system
journal, June 1988
- Karakaya, I.; Thompson, W. T.
- Bulletin of Alloy Phase Diagrams, Vol. 9, Issue 3
Tungsten as material for plasma-facing components in fusion devices
journal, August 2011
- Philipps, V.
- Journal of Nuclear Materials, Vol. 415, Issue 1
Solid solution strengthening in Fe-N single crystals
journal, July 1968
- Nakada, Y.; Keh, A. S.
- Acta Metallurgica, Vol. 16, Issue 7
Ab initio calculations of some atomic and point defect interactions involving C and N in Fe
journal, February 2005
- Becquart *, C. S.; Domain, C.; Foct, J.
- Philosophical Magazine, Vol. 85, Issue 4-7
Effect of W and N on mechanical properties of reduced activation ferritic/martensitic EUROFER-based steel grades
journal, April 2018
- Puype, A.; Malerba, L.; De Wispelaere, N.
- Journal of Nuclear Materials, Vol. 502
An assessment by activation analysis of the influence of small nitrogen contents on electron-induced void swelling in Fe-Cr-Ni alloys
journal, July 1990
- Rotman, F.; Fedoroff, M.; Rouchaud, J. C.
- Journal of Nuclear Materials, Vol. 172, Issue 2
Void-swelling in irons and ferritic steels
journal, November 1979
- Little, E. A.
- Journal of Nuclear Materials, Vol. 87, Issue 1