High dose ion irradiation response of large strain extrusion machined ultrafine grain HT-9 steel

Kim, Hyosim; Gigax, Jonathan G.; Chancey, Matthew R.; Efe, Mert.; Baldwin, Jon K.S.; Wang, Yongqiang; Maloy, Stuart A.; El Atwani, Osman

doi:10.1016/j.jnucmat.2025.155697

Title: High dose ion irradiation response of large strain extrusion machined ultrafine grain HT-9 steel

Journal Article · 11 February 2025 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2025.155697 · OSTI ID:2529520

^[1]; Gigax, Jonathan G. ^[1];

^[1]; Efe, Mert. ^[2]; Baldwin, Jon K.S. ^[1]; Wang, Yongqiang ^[1];

^[2];

^[2]

Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Grain size refinement is one of the many methods to improve radiation resistance of steels. In this study, ultrafine grain HT-9 steel (grain size < ~270 nm), a potential candidate material for future nuclear fission reactor designs, was manufactured by large strain extrusion machining (LSEM). Radiation resistance of this ultrafine grain HT-9 steel was tested for the first time at high dose using a 3.5 MeV Fe ion beam up to 500 peak displacements-per-atom (dpa) at 450 °C. Results were characterized using a transmission electron microscopy (TEM). Although previous study on the pristine LSEM HT-9 showed that ultrafine grains are thermally stable up to 700 °C, irradiation induced grain growth was observed after 200 peak dpa. Grain boundary carbides were stable after 200 peak dpa with notable dissolution into the matrix in between 200 and 300 peak dpa. The grain size remained in the ultrafine regime (<350 nm) even after the 500 peak dpa irradiation indicating superior grain stability. LSEM HT-9 showed only 0.14 % swelling after 300 peak dpa (181 average local dpa) but showed a steeper rise after 400 peak dpa (242 average local dpa) reaching 1.57 %. However, the rate of swelling between 300 and 400 peak dpa and 400–500 peak dpa decreased significantly from 0.014 to 0.003 %/dpa. The LSEM HT-9 void swelling trend was compared with the void swelling data of other ion and neutron irradiated HT-9 alloys, and the result was discussed with respect to the irradiation induced grain growth, chemical segregation at the grain boundary and precipitation.

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Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Sponsoring Organization:: USDOE; USDOE National Nuclear Security Administration (NNSA); USDOE Office of Nuclear Energy (NE); USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Fuel Cycle Research and Development Program; USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)

Grant/Contract Number:: 89233218CNA000001; AC05-76RL01830; AC52-06NA25396

OSTI ID:: 2529520

Report Number(s):: LA-UR--25-20580; PNNL-SA-203920

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 607; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (82)

Effect of helium on void formation in nickel Brimhall, J. L.; Simonen, E. P. Journal of Nuclear Materials, Vol. 68, Issue 2 https://doi.org/10.1016/0022-3115(77)90242-2	journal	October 1977
Radiation-induced segregation in binary and ternary alloys Okamoto, P. R.; Rehn, L. E. Journal of Nuclear Materials, Vol. 83, Issue 1 https://doi.org/10.1016/0022-3115(79)90587-7	journal	August 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
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
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
14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation Kai, J. J.; Kulcinski, G. L. Journal of Nuclear Materials, Vol. 175, Issue 3 https://doi.org/10.1016/0022-3115(90)90211-5	journal	December 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
Theory and experimental background on dimensional changes in irradiated alloys Mansur, L. K. Journal of Nuclear Materials, Vol. 216 https://doi.org/10.1016/0022-3115(94)90009-4	journal	October 1994
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
Simultaneous bombardment with helium, hydrogen, and heavy ions to simulate microstructural damage from fission or fusion neutrons Farrell, K.; Lewis, M. B.; Packan, N. H. Scripta Metallurgica, Vol. 12, Issue 12 https://doi.org/10.1016/0036-9748(78)90087-X	journal	December 1978
Point defect annihilation at grain boundaries in gold Dollar, M.; Gleiter, H. Scripta Metallurgica, Vol. 19, Issue 4 https://doi.org/10.1016/0036-9748(85)90118-8	journal	April 1985
Materials processing by simple shear Segal, V. M. Materials Science and Engineering: A, Vol. 197, Issue 2 https://doi.org/10.1016/0921-5093(95)09705-8	journal	July 1995
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
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
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
A study of the interactive effects of strain, strain rate and temperature in severe plastic deformation of copper Brown, Travis L.; Saldana, Christopher; Murthy, Tejas G. Acta Materialia, Vol. 57, Issue 18 https://doi.org/10.1016/j.actamat.2009.07.052	journal	October 2009
Controlling deformation and microstructure on machined surfaces Guo, Yang; Saldana, Christopher; Dale Compton, W. Acta Materialia, Vol. 59, Issue 11 https://doi.org/10.1016/j.actamat.2011.03.076	journal	June 2011
Mechanics of large strain extrusion machining and application to deformation processing of magnesium alloys Efe, Mert; Moscoso, Wilfredo; Trumble, Kevin P. Acta Materialia, Vol. 60, Issue 5 https://doi.org/10.1016/j.actamat.2012.01.018	journal	March 2012
Effect of grain boundary character on sink efficiency Han, W. Z.; Demkowicz, M. J.; Fu, E. G. Acta Materialia, Vol. 60, Issue 18 https://doi.org/10.1016/j.actamat.2012.08.009	journal	October 2012
Controlling texture in magnesium alloy sheet by shear-based deformation processing Sagapuram, Dinakar; Efe, Mert; Moscoso, Wilfredo Acta Materialia, Vol. 61, Issue 18 https://doi.org/10.1016/j.actamat.2013.07.063	journal	October 2013
Response of equal channel angular extrusion processed ultrafine-grained T91 steel subjected to high temperature heavy ion irradiation Song, M.; Wu, Y. D.; Chen, D. Acta Materialia, Vol. 74 https://doi.org/10.1016/j.actamat.2014.04.034	journal	August 2014
In situ studies on radiation tolerance of nanotwinned Cu Chen, Y.; Li, J.; Yu, K. Y. Acta Materialia, Vol. 111 https://doi.org/10.1016/j.actamat.2016.03.039	journal	June 2016
Radiation instability of equal channel angular extruded T91 at ultra-high damage levels Gigax, Jonathan G.; Kim, Hyosim; Chen, Tianyi Acta Materialia, Vol. 132 https://doi.org/10.1016/j.actamat.2017.04.038	journal	June 2017
In-situ irradiation tolerance investigation of high strength ultrafine tungsten-titanium carbide alloy El-Atwani, O.; Cunningham, W. S.; Esquivel, E. Acta Materialia, Vol. 164 https://doi.org/10.1016/j.actamat.2018.10.038	journal	February 2019
Predicting displacement damage for ion irradiation: Origin of the overestimation of vacancy production in SRIM full-cascade calculations Lin, Yan-Ru; Zinkle, Steven J.; Ortiz, Christophe J. Current Opinion in Solid State and Materials Science, Vol. 27, Issue 6 https://doi.org/10.1016/j.cossms.2023.101120	journal	December 2023
Prediction of swelling of 18Cr10NiTi austenitic steel over a wide range of displacement rates Kalchenko, A. S.; Bryk, V. V.; Lazarev, N. P. Journal of Nuclear Materials, Vol. 399, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.01.010	journal	April 2010
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys Was, Gary S.; Wharry, Janelle P.; Frisbie, Brian Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.01.031	journal	April 2011
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
The role of niobium carbide in radiation induced segregation behaviour of type 347 austenitic stainless steel Ahmedabadi, Parag; Kain, Vivekanand; Gupta, Manu Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2011.05.051	journal	August 2011
Radiation-induced segregation in desensitized type 304 austenitic stainless steel Ahmedabadi, Parag; Kain, V.; Arora, K. Journal of Nuclear Materials, Vol. 416, Issue 3 https://doi.org/10.1016/j.jnucmat.2011.06.024	journal	September 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
A systematic study of radiation-induced segregation in ferritic–martensitic alloys Wharry, Janelle P.; Was, Gary S. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.071	journal	November 2013
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
Proton irradiation creep of FM steel T91 Xu, Cheng; Was, Gary S. Journal of Nuclear Materials, Vol. 459 https://doi.org/10.1016/j.jnucmat.2015.01.023	journal	April 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
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
Nanocluster irradiation evolution in Fe-9%Cr ODS and ferritic-martensitic alloys Swenson, M. J.; Wharry, J. P. Journal of Nuclear Materials, Vol. 496 https://doi.org/10.1016/j.jnucmat.2017.08.045	journal	December 2017
Swelling resistance of advanced austenitic alloy A709 and its comparison with 316 stainless steel at high damage levels Kim, Hyosim; Gigax, Jonathan G.; Fan, Jiangyuan Journal of Nuclear Materials, Vol. 527 https://doi.org/10.1016/j.jnucmat.2019.151818	journal	December 2019
Investigation of hardening mechanisms and size effects in proton-irradiated HT-9 steels Ajantiwalay, Tanvi; Nagel, Lauren; Maloy, Stuart Journal of Nuclear Materials, Vol. 548 https://doi.org/10.1016/j.jnucmat.2021.152866	journal	May 2021
Precipitation kinetics of radiation-induced Ni-Mn-Si phases in VVER-1000 reactor pressure vessel steels under low and high flux irradiation Kuleshova, E. A.; Zhuchkov, G. M.; Fedotova, S. V. Journal of Nuclear Materials, Vol. 553 https://doi.org/10.1016/j.jnucmat.2021.153091	journal	September 2021
Void swelling of conventional and composition engineered HT9 alloys after high-dose self-ion irradiation Kim, Hyosim; Gigax, Jonathan G.; Rietema, Connor J. Journal of Nuclear Materials, Vol. 560 https://doi.org/10.1016/j.jnucmat.2021.153492	journal	March 2022
A quantitative method to determine the region not influenced by injected interstitial and surface effects during void swelling in ion-irradiated metals Li, Yongchang; French, Aaron; Hu, Zhihan Journal of Nuclear Materials, Vol. 573 https://doi.org/10.1016/j.jnucmat.2022.154140	journal	January 2023
Formation and dissolution of carbides and precipitates in self-ion irradiated HT9 alloy Pena, Miguel; Hu, Zhihan; Li, Yongchang Journal of Nuclear Materials, Vol. 588 https://doi.org/10.1016/j.jnucmat.2023.154819	journal	January 2024
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
Radiation damage tolerant nanomaterials Beyerlein, I. J.; Caro, A.; Demkowicz, M. J. Materials Today, Vol. 16, Issue 11 https://doi.org/10.1016/j.mattod.2013.10.019	journal	November 2013
Large strain deformation and ultra-fine grained materials by machining Swaminathan, Srinivasan; Shankar, M. Ravi; Lee, Seongyl Materials Science and Engineering: A, Vol. 410-411 https://doi.org/10.1016/j.msea.2005.08.139	journal	November 2005
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
Ion beam irradiation of nanostructures – A 3D Monte Carlo simulation code Borschel, C.; Ronning, C. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 269, Issue 19 https://doi.org/10.1016/j.nimb.2011.07.004	journal	October 2011
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
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
Principles of equal-channel angular pressing as a processing tool for grain refinement Valiev, Ruslan Z.; Langdon, Terence G. Progress in Materials Science, Vol. 51, Issue 7 https://doi.org/10.1016/j.pmatsci.2006.02.003	journal	September 2006
Using high-pressure torsion for metal processing: Fundamentals and applications Zhilyaev, A.; Langdon, T. Progress in Materials Science, Vol. 53, Issue 6 https://doi.org/10.1016/j.pmatsci.2008.03.002	journal	August 2008
Large strain extrusion machining of magnesium alloys for biomedical applications Bertolini, R.; Bruschi, S.; Ghiotti, A. Procedia CIRP, Vol. 71 https://doi.org/10.1016/j.procir.2018.05.080	journal	January 2018
Microstructure refinement of tungsten by surface deformation for irradiation damage resistance Efe, Mert; El-Atwani, Osman; Guo, Yang Scripta Materialia, Vol. 70 https://doi.org/10.1016/j.scriptamat.2013.08.013	journal	January 2014
Emulation of reactor irradiation damage using ion beams Was, G. S.; Jiao, Z.; Getto, E. Scripta Materialia, Vol. 88 https://doi.org/10.1016/j.scriptamat.2014.06.003	journal	October 2014
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
Micro- and mesoscale mechanical properties of an ultra-fine grained CrFeMnNi high entropy alloy produced by large strain machining Gigax, Jonathan G.; El-Atwani, Osman; McCulloch, Quinn Scripta Materialia, Vol. 178 https://doi.org/10.1016/j.scriptamat.2019.11.042	journal	March 2020
Voids in Irradiated Stainless Steel Cawthorne, C.; Fulton, E. J. Nature, Vol. 216, Issue 5115 https://doi.org/10.1038/216575a0	journal	November 1967
Defect annihilation at grain boundaries in alpha-Fe Scientific Reports, Vol. 3, Issue 1 https://doi.org/10.1038/srep01450	journal	March 2013
Irradiation-induced grain growth and defect evolution in nanocrystalline zirconia with doped grain boundaries Dey, Sanchita; Mardinly, John; Wang, Yongqiang Physical Chemistry Chemical Physics, Vol. 18, Issue 25 https://doi.org/10.1039/C6CP01763K	journal	January 2016
A thermal spike model of grain growth under irradiation Kaoumi, D.; Motta, A. T.; Birtcher, R. C. Journal of Applied Physics, Vol. 104, Issue 7 https://doi.org/10.1063/1.2988142	journal	January 2008
Investigating the Machinability of AISI 420 Stainless Steel Using Factorial Design El-Tamimi, A. M.; El-Hossainy, T. M. Materials and Manufacturing Processes, Vol. 23, Issue 4 https://doi.org/10.1080/10426910801974838	journal	April 2008
Grain size threshold for enhanced irradiation resistance in nanocrystalline and ultrafine tungsten El-Atwani, O.; Hinks, J. A.; Greaves, G. Materials Research Letters, Vol. 5, Issue 5 https://doi.org/10.1080/21663831.2017.1292326	journal	February 2017
Segregation in irradiated alloys: The inverse Kirkendall effect and the effect of constitution on void swelling Marwick, A. D. Journal of Physics F: Metal Physics, Vol. 8, Issue 9 https://doi.org/10.1088/0305-4608/8/9/008	journal	September 1978
Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission Bai, X. M.; Voter, A. F.; Hoagland, R. G. Science, Vol. 327, Issue 5973 https://doi.org/10.1126/science.1183723	journal	March 2010
Grain Growth in Nanocrystalline Metal Thin Films under In Situ Ion-Beam Irradiation Kaoumi, D.; Motta, A. T.; Birtcher, R. C. Journal of ASTM International, Vol. 4, Issue 8 https://doi.org/10.1520/JAI100743	journal	January 2007
Low-cost manufacturing process for nanostructured metals and alloys Brown, Travis L.; Swaminathan, Srinivasan; Chandrasekar, Srinivasan Journal of Materials Research, Vol. 17, Issue 10 https://doi.org/10.1557/JMR.2002.0362	journal	October 2002
Bulk nanostructured materials by large strain extrusion machining Moscoso, W.; Shankar, M. R.; Mann, J. B. Journal of Materials Research, Vol. 22, Issue 1 https://doi.org/10.1557/jmr.2007.0021	journal	January 2007
Irradiation damage of single crystal, coarse-grained, and nanograined copper under helium bombardment at 450 °C Han, Weizhong; Fu, E. G.; Demkowicz, Michael J. Journal of Materials Research, Vol. 28, Issue 20 https://doi.org/10.1557/jmr.2013.283	journal	October 2013
A Novel Microshear Geometry for Exploring the Influence of Void Swelling on the Mechanical Properties Induced by MeV Heavy Ion Irradiation Gigax, Jonathan G.; Chancey, Matthew R.; Xie, Dongyue Materials, Vol. 15, Issue 12 https://doi.org/10.3390/ma15124253	journal	June 2022
Effect of Production Bias on Radiation-Induced Segregation in Ni-Cr Alloys Gencturk, Merve; Ozturk, Abdurrahman; Ahmed, Karim Materials, Vol. 16, Issue 23 https://doi.org/10.3390/ma16237475	journal	December 2023
Dissolution of M₂₃C₆ and New Phase Re-Precipitation in Fe Ion-Irradiated RAFM Steel Yang, Zheng; Jin, Shuoxue; Song, Ligang Metals, Vol. 8, Issue 5 https://doi.org/10.3390/met8050349	journal	May 2018
Stable, Ductile and Strong Ultrafine HT-9 Steels via Large Strain Machining El-Atwani, Osman; Kim, Hyosim; Gigax, Jonathan G. Nanomaterials, Vol. 11, Issue 10 https://doi.org/10.3390/nano11102538	journal	September 2021
Limitations of Thermal Stability Analysis via In-Situ TEM/Heating Experiments El-Atwani, Osman; Kim, Hyosim; Harvey, Cayla Nanomaterials, Vol. 11, Issue 10 https://doi.org/10.3390/nano11102541	journal	September 2021
Irradiation Effects of ht-9 Martensitic Steel Chen, Yiren Nuclear Engineering and Technology, Vol. 45, Issue 3 https://doi.org/10.5516/NET.07.2013.706	journal	June 2013

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36 MATERIALS SCIENCE
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Ultrafine grain

Title: High dose ion irradiation response of large strain extrusion machined ultrafine grain HT-9 steel

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