Void swelling of conventional and composition engineered HT9 alloys after high-dose self-ion irradiation

Kim, Hyosim; Gigax, Jonathan Gregory; Rietema, Connor J.; El Atwani, Osman; Chancey, Matthew Ryan; Baldwin, Jon Kevin Scott; Wang, Yongqiang; Maloy, Stuart Andrew

doi:10.1016/j.jnucmat.2021.153492

Title: Void swelling of conventional and composition engineered HT9 alloys after high-dose self-ion irradiation

Journal Article · 23 December 2021 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2021.153492 · OSTI ID:1839354

^[1];

^[2]; Rietema, Connor J. ^[3];

^[1];

^[2];

^[1];

^[1]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Center for Integrated Nanotechnologies (CINT)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Colorado School of Mines, Golden, CO (United States)

Ferritic/martensitic (F/M) steels are being considered as potential structural materials for next generation nuclear reactors, and variants of the alloy HT9 are some of the most promising candidates. In this study, two conventional and two composition engineered HT9 alloys were irradiated using 3.5 MeV Fe²⁺ up to 600 peak displacement-per-atom (dpa) at 450 °C. Void swelling and microstructure evolution were characterized for each alloy and compared. The two conventional HT9 alloys (INL and ACO3) showed similar void swelling behavior due to their similar elemental composition and processing conditions. The INL HT9 exhibited a maximum of 2.4% swelling and the ACO3 HT9 showed a maximum of 2.8% swelling at 342 and 393 average local dpa, respectively. On the other hand, the two-composition engineered HT9 alloys with varying N contents (10 ppm for low N and 440 ppm for high N) showed disparate swelling behavior. The low N HT9 exhibited a maximum of 4.6% swelling, while the high N HT9 showed a maximum of 0.7% swelling at 342 average local dpa. Changes in the N content also affected Ni/Si rich G-phase formation. The low N HT9 showed a larger size and lower density of G-phase precipitates compared with the high N HT9 after 600 peak dpa irradiation. This study compares the void swelling behavior of the ion irradiated four current HT9 alloys to extremely high doses, with the void swelling data from neutron irradiated HT9 alloys. Furthermore, the comparison lends critical insights into how well these current alloys can withstand high neutron fluxes in future reactors, especially since the low N and high N HT9 alloys have never been exposed to such high doses before.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: 89233218CNA000001

OSTI ID:: 1839354

Report Number(s):: LA-UR--21-27368

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 560; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (54)

The effect of minor constituents on swelling in stainless steel Leitnaker, J. M.; Bloom, E. E.; Stiegler, J. O. Journal of Nuclear Materials, Vol. 49, Issue 1 https://doi.org/10.1016/0022-3115(73)90061-5	journal	November 1973
Void-swelling in irons and ferritic steels Little, E. A. Journal of Nuclear Materials, Vol. 87, Issue 1 https://doi.org/10.1016/0022-3115(79)90122-3	journal	November 1979
Void swelling of an oxide dispersion strengthened ferritic alloy in a high voltage electron microscope Snykers, M. Journal of Nuclear Materials, Vol. 89, Issue 1 https://doi.org/10.1016/0022-3115(80)90011-2	journal	March 1980
Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage Garner, F. A. Journal of Nuclear Materials, Vol. 117 https://doi.org/10.1016/0022-3115(83)90023-5	journal	July 1983
The size effect in radiation-induced segregation of solutes in binary metallic alloys Kornblit, L.; Ignatiev, A. Journal of Nuclear Materials, Vol. 126, Issue 1 https://doi.org/10.1016/0022-3115(84)90535-X	journal	September 1984
Microstructure of 9 Cr-1 MoVNb steel irradiated to 36 dpa at elevated temperatures in HFIR Vitek, J. M.; Klueh, R. L. Journal of Nuclear Materials, Vol. 122, Issue 1-3 https://doi.org/10.1016/0022-3115(84)90606-8	journal	May 1984
Effects of nitrogen and carbon on void swelling in electron-irradiated austenitic stainless steel Nakata, Kiyotomo; Katano, Yoshio; Masaoka, Isao Journal of Nuclear Materials, Vol. 122, Issue 1-3 https://doi.org/10.1016/0022-3115(84)90673-1	journal	May 1984
Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR Maziasz, P. J.; Klueh, R. L.; Vitek, J. M. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/0022-3115(86)90120-0	journal	November 1986
An assessment by activation analysis of the influence of small nitrogen contents on electron-induced void swelling in Fe-Cr-Ni alloys Rotman, F.; Fedoroff, M.; Rouchaud, J. C. Journal of Nuclear Materials, Vol. 172, Issue 2 https://doi.org/10.1016/0022-3115(90)90434-O	journal	July 1990
Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix Dubuisson, P.; Gilbon, D.; Séran, J. L. Journal of Nuclear Materials, Vol. 205 https://doi.org/10.1016/0022-3115(93)90080-I	journal	October 1993
Hardness of 12Cr8Mo ferritic steels irradiated by Ni ions Ohta, J.; Ohmura, T.; Kako, K. Journal of Nuclear Materials, Vol. 225 https://doi.org/10.1016/0022-3115(95)00016-X	journal	August 1995
Microstructural analysis of neutron-irradiated martensitic steels Kai, J. J.; Klueh, R. L. Journal of Nuclear Materials, Vol. 230, Issue 2 https://doi.org/10.1016/0022-3115(96)00165-1	journal	June 1996
Microstructural examination of commercial ferritic alloys at 200 dpa Gelles, D. S. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00222-X	journal	October 1996
Low-activation ferritic and martensitic steels for fusion application Kohyama, A.; Hishinuma, A.; Gelles, D. S. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00327-3	journal	October 1996
Irradiation creep and void swelling of two LMR heats of HT9 at ∼ 400°C and 165 dpa Toloczko, M. B.; Garner, F. A. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00413-8	journal	October 1996
Development of martensitic steels for high neutron damage applications Gelles, D. S. Journal of Nuclear Materials, Vol. 239 https://doi.org/10.1016/S0022-3115(96)00474-6	journal	December 1996
Interaction of solutes with irradiation-induced defects of electron-irradiated dilute iron alloys Abe, H.; Kuramoto, E. Journal of Nuclear Materials, Vol. 271-272 https://doi.org/10.1016/S0022-3115(98)00741-7	journal	May 1999
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure Garner, F. A.; Toloczko, M. B.; Sencer, B. H. Journal of Nuclear Materials, Vol. 276, Issue 1-3 https://doi.org/10.1016/S0022-3115(99)00225-1	journal	January 2000
Structural materials for fission & fusion energy Zinkle, Steven J.; Busby, Jeremy T. Materials Today, Vol. 12, Issue 11 https://doi.org/10.1016/S1369-7021(09)70294-9	journal	November 2009
Materials challenges in nuclear energy Zinkle, S. J.; Was, G. S. Acta Materialia, Vol. 61, Issue 3 https://doi.org/10.1016/j.actamat.2012.11.004	journal	February 2013
Effect of nickel on point defects diffusion in Fe – Ni alloys Anento, N.; Serra, A.; Osetsky, Y. Acta Materialia, Vol. 132 https://doi.org/10.1016/j.actamat.2017.05.010	journal	June 2017
Assessment of neutron irradiation effects on RAFM steels Gaganidze, Ermile; Aktaa, Jarir Fusion Engineering and Design, Vol. 88, Issue 3 https://doi.org/10.1016/j.fusengdes.2012.11.020	journal	March 2013
Effect of irradiation-induced plastic flow localization on ductile crack resistance behavior of a 9%Cr tempered martensitic steel Chaouadi, R. Journal of Nuclear Materials, Vol. 372, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2007.04.044	journal	January 2008
Ferritic/martensitic steels for next-generation reactors Klueh, R. L.; Nelson, A. T. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.005	journal	September 2007
Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C Sencer, B. H.; Kennedy, J. R.; Cole, J. I. Journal of Nuclear Materials, Vol. 393, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.06.010	journal	September 2009
Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF Sencer, B. H.; Kennedy, J. R.; Cole, J. I. Journal of Nuclear Materials, Vol. 414, Issue 2 https://doi.org/10.1016/j.jnucmat.2011.03.050	journal	July 2011
Phase stability of an HT-9 duct irradiated in FFTF Anderoglu, O.; Van den Bosch, J.; Hosemann, P. Journal of Nuclear Materials, Vol. 430, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.06.038	journal	November 2012
Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions Shao, Lin; Wei, C. -C.; Gigax, J. Journal of Nuclear Materials, Vol. 453, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.002	journal	October 2014
Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa Toloczko, M. B.; Garner, F. A.; Voyevodin, V. N. Journal of Nuclear Materials, Vol. 453, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.011	journal	October 2014
Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys Getto, E.; Jiao, Z.; Monterrosa, A. M. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.05.016	journal	October 2015
The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 °C Gigax, Jonathan G.; Aydogan, Eda; Chen, Tianyi Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.05.025	journal	October 2015
Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels Getto, E.; Sun, K.; Monterrosa, A. M. Journal of Nuclear Materials, Vol. 480 https://doi.org/10.1016/j.jnucmat.2016.08.015	journal	November 2016
Radiation response of alloy T91 at damage levels up to 1000 peak dpa Gigax, J. G.; Chen, T.; Kim, Hyosim Journal of Nuclear Materials, Vol. 482 https://doi.org/10.1016/j.jnucmat.2016.10.003	journal	December 2016
The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels Getto, E.; Vancoevering, G.; Was, G. S. Journal of Nuclear Materials, Vol. 484 https://doi.org/10.1016/j.jnucmat.2016.12.006	journal	February 2017
Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions Aydogan, E.; Chen, T.; Gigax, J. G. Journal of Nuclear Materials, Vol. 487 https://doi.org/10.1016/j.jnucmat.2017.02.006	journal	April 2017
Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel Zheng, Ce; Auger, Maria A.; Moody, Michael P. Journal of Nuclear Materials, Vol. 491 https://doi.org/10.1016/j.jnucmat.2017.04.040	journal	August 2017
Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation Kim, Hyosim; Gigax, Jonathan G.; El-Atwani, Osman Materials Characterization, Vol. 173 https://doi.org/10.1016/j.matchar.2021.110908	journal	March 2021
SRIM – The stopping and range of ions in matter (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 https://doi.org/10.1016/j.nimb.2010.02.091	journal	June 2010
On the use of SRIM for computing radiation damage exposure 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 https://doi.org/10.1016/j.nimb.2013.05.008	journal	September 2013
Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling Wang, Jing; Toloczko, Mychailo B.; Bailey, Nathan Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 387 https://doi.org/10.1016/j.nimb.2016.09.015	journal	November 2016
Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials Shao, Lin; Gigax, Jonathan; Chen, Di Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 409 https://doi.org/10.1016/j.nimb.2017.05.026	journal	October 2017
Resolution of the carbon contamination problem in ion irradiation experiments Was, G. S.; Taller, S.; Jiao, Z. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 412 https://doi.org/10.1016/j.nimb.2017.08.039	journal	December 2017
Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9 Gigax, Jonathan G.; Kim, Hyosim; Aydogan, E. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 444 https://doi.org/10.1016/j.nimb.2018.12.051	journal	April 2019
Evaluation of effective threshold displacement energies and other data required for the calculation of advanced atomic displacement cross-sections Konobeyev, A. Yu.; Fischer, U.; Korovin, Yu. A. Nuclear Energy and Technology, Vol. 3, Issue 3 https://doi.org/10.1016/j.nucet.2017.08.007	journal	September 2017
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations Zinkle, S. J.; Snead, L. L. Scripta Materialia, Vol. 143 https://doi.org/10.1016/j.scriptamat.2017.06.041	journal	January 2018
Nitrogen effects on radiation response in 12Cr ferritic/martensitic alloys Aydogan, E.; Gigax, J. G.; Parker, S. S. Scripta Materialia, Vol. 189 https://doi.org/10.1016/j.scriptamat.2020.08.005	journal	December 2020
Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel Rietema, C. J.; Hassan, M. M.; Anderoglu, O. Scripta Materialia, Vol. 197 https://doi.org/10.1016/j.scriptamat.2021.113787	journal	May 2021
Carbon Contamination During Ion Irradiation - Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels Wang, Jing; Toloczko, Mychailo B.; Kruska, Karen Scientific Reports, Vol. 7, Issue 1 https://doi.org/10.1038/s41598-017-15669-y	journal	November 2017
Predicting structural material degradation in advanced nuclear reactors with ion irradiation Taller, Stephen; VanCoevering, Gerrit; Wirth, Brian D. Scientific Reports, Vol. 11, Issue 1 https://doi.org/10.1038/s41598-021-82512-w	journal	February 2021
Ab initio calculations of some atomic and point defect interactions involving C and N in Fe Becquart *, C. S.; Domain, C.; Foct, J. Philosophical Magazine, Vol. 85, Issue 4-7 https://doi.org/10.1080/02678370412331320152	journal	February 2005
Beam-contamination-induced compositional alteration and its neutron-atypical consequences in ion simulation of neutron-induced void swelling Gigax, Jonathan G.; Kim, Hyosim; Aydogan, Eda Materials Research Letters, Vol. 5, Issue 7 https://doi.org/10.1080/21663831.2017.1323808	journal	May 2017
Designing Radiation Resistance in Materials for Fusion Energy Zinkle, S. J.; Snead, L. L. Annual Review of Materials Research, Vol. 44, Issue 1 https://doi.org/10.1146/annurev-matsci-070813-113627	journal	July 2014
Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors Klueh, R. L. International Materials Reviews, Vol. 50, Issue 5 https://doi.org/10.1179/174328005X41140	journal	October 2005
Challenges to the use of ion irradiation for emulating reactor irradiation Was, Gary S. Journal of Materials Research, Vol. 30, Issue 9 https://doi.org/10.1557/jmr.2015.73	journal	April 2015

Similar Records

Microstructural Characterization of High Dose Irradiated HT9

Technical Report · 2019 · OSTI ID:1565803

Gigax, Jonathan Gregory; Kim, Hyosim

Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation

Journal Article · 2021 · Materials Characterization · OSTI ID:1762736

Kim, Hyosim; Gigax, Jonathan Gregory; El-Atwani, Osman; +4 more

Transient failure behavior of HT9

Technical Report · 1994 · OSTI ID:10173288

Huang, F H

Related Subjects

36 MATERIALS SCIENCE

Title: Void swelling of conventional and composition engineered HT9 alloys after high-dose self-ion irradiation

Citation Formats

References (54)

Similar Records

Related Subjects