Comparative Mechanical Properties Analysis of Triple Ion-Beam Irradiated and Neutron Irradiated Potential Plasma Facing Components

Howard, Cameron Boyd; Frazer, David M.; Choi, B. William; Lupinacci, Amanda; Parker, Stephen Scott; Hsiung, Luke; Kimura, Akihiko; Fluss, Michael J.; Hosemann, Peter

doi:10.1007/s11837-025-07218-0

Title: Comparative Mechanical Properties Analysis of Triple Ion-Beam Irradiated and Neutron Irradiated Potential Plasma Facing Components

Journal Article · 03 March 2025 · JOM. Journal of the Minerals, Metals & Materials Society

DOI: https://doi.org/10.1007/s11837-025-07218-0 · OSTI ID:2526290

^[1]; Frazer, David M. ^[1]; Choi, B. William ^[2]; Lupinacci, Amanda ^[3]; Parker, Stephen Scott ^[4]; Hsiung, Luke ^[2]; Kimura, Akihiko ^[5]; Fluss, Michael J. ^[2]; Hosemann, Peter ^[3]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
University of California, Berkeley, CA (United States)
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Kyoto University (Japan)

Several classes of materials are being proposed for use in fusion reactors including oxide dispersion strengthened (ODS) and reduced activation ferritic-martensitic (RAF/M) steels to withstand the severe and harsh conditions. In this work, the mechanical properties of a Fe-16Cr-4Al-2W-0.3Ti-0.3Y₂O₃ (K3) (ODS) ferritic steel and a Fe-8.9Cr-1.1W-0.47Mn-0.2V-0.14Ta-0.11C (Eurofer 97) (RAF/M) steel) after triple ion beam irradiation were locally evaluated utilizing in-situ micro-pillar compression tests, and continuous stiffness/quasi-static nanoindentation. No change in mechanical properties was observed in the K3 ODS steel. However, the Eurofer 97 RAF/M steel exhibited radiation-induced effects via increases in yield strength. Micro-pillar techniques were expanded to neutron-irradiated materials via an in-situ testing technique employing lift-out methods on Fe-14Cr-0.9Ti-0.3Mo-0.25Y₂O₃ (MA957) ODS ferritic steel. Both the non-irradiated and irradiated compressive yield stresses of the MA 957 micro-pillars were in good agreement with bulk yield stress values reported in the literature, suggesting that the lift-out micro-pillar compression testing technique is a promising method. The demonstration of these techniques on ion beam and neutron irradiated ODS steels and ion beam RAF/M steels gives information to inform models of the material degradation during use in a fusion device.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2526290

Report Number(s):: INL/JOU--22-69297

Journal Information:: JOM. Journal of the Minerals, Metals & Materials Society, Journal Name: JOM. Journal of the Minerals, Metals & Materials Society Journal Issue: 4 Vol. 77; ISSN 1047-4838; ISSN 1543-1851

Publisher:: SpringerCopyright Statement

Country of Publication:: United States

Language:: English

References (42)

Testing Thin Films by Microcompression: Benefits and Limits Wörgötter, H.; Kiener, D.; Purswani, J. M. BHM Berg- und Hüttenmännische Monatshefte, Vol. 153, Issue 7 https://doi.org/10.1007/s00501-008-0386-1	journal	July 2008
The relation between load and penetration in the axisymmetric boussinesq problem for a punch of arbitrary profile Sneddon, Ian N. International Journal of Engineering Science, Vol. 3, Issue 1 https://doi.org/10.1016/0020-7225(65)90019-4	journal	May 1965
Mechanical properties of materials in fusion reactor first-wall and blanket systems Bloom, E. E. Journal of Nuclear Materials, Vol. 85-86 https://doi.org/10.1016/0022-3115(79)90358-1	journal	December 1979
Interactions between fusion materials R&D and other technologies Kohyama, A.; Seki, M.; Abe, K. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00156-2	journal	December 2000
Perspective of ODS alloys application in nuclear environments Ukai, Shigeharu; Fujiwara, Masayuki Journal of Nuclear Materials, Vol. 307-311, p. 749-757 https://doi.org/10.1016/S0022-3115(02)01043-7	journal	December 2002
Irradiation creep of various ferritic alloys irradiated at ∼400°C in the PFR and FFTF reactors Toloczko, M. B.; Garner, F. A.; Eiholzer, C. R. Journal of Nuclear Materials, Vol. 258-263 https://doi.org/10.1016/S0022-3115(98)00165-2	journal	October 1998
Operating temperature windows for fusion reactor structural materials Zinkle, S. J.; Ghoniem, N. M. Fusion Engineering and Design, Vol. 51-52, p. 55-71 https://doi.org/10.1016/S0920-3796(00)00320-3	journal	November 2000
A review of nanoindentation continuous stiffness measurement technique and its applications Li, Xiaodong; Bhushan, Bharat Materials Characterization, Vol. 48, Issue 1 https://doi.org/10.1016/S1044-5803(02)00192-4	journal	February 2002
JANNUS: experimental validation at the scale of atomic modelling Serruys, Yves; Ruault, Marie-Odile; Trocellier, Patrick Comptes Rendus. Physique, Vol. 9, Issue 3-4 https://doi.org/10.1016/j.crhy.2007.10.015	journal	April 2008
Fissile core and Tritium-Breeding Blanket: structural materials and their requirements Boutard, Jean-Louis; Alamo, Ana; Lindau, Rainer Comptes Rendus Physique, Vol. 9, Issue 3-4 https://doi.org/10.1016/j.crhy.2007.11.004	journal	April 2008
Repeatability of irradiation damage and of recovery by post-irradiation annealing of EUROFER base steels Schneider, H. -C.; Petersen, C.; Povstyanko, A. V. Fusion Engineering and Design, Vol. 124 https://doi.org/10.1016/j.fusengdes.2017.04.066	journal	November 2017
Materials for the plasma-facing components of fusion reactors Bolt, H.; Barabash, V.; Krauss, W. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.005	journal	August 2004
Synergistic effect of helium and hydrogen for defect evolution under multi-ion irradiation of Fe–Cr ferritic alloys Tanaka, T.; Oka, K.; Ohnuki, S. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.051	journal	August 2004
Materials to deliver the promise of fusion power – progress and challenges Bloom, E. E.; Zinkle, S. J.; Wiffen, F. W. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.141	journal	August 2004
Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957 Toloczko, M. B.; Gelles, D. S.; Garner, F. A. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.296	journal	August 2004
The European integrated materials and technology programme in fusion Andreani, R.; Diegele, E.; Laesser, R. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.339	journal	August 2004
Assessment of ODS-14%Cr ferritic alloy for high temperature applications Alamo, A.; Lambard, V.; Averty, X. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.05.004	journal	August 2004
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys Klueh, R. L.; Shingledecker, J. P.; Swindeman, R. W. Journal of Nuclear Materials, Vol. 341, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2005.01.017	journal	May 2005
Critical questions in materials science and engineering for successful development of fusion power Bloom, E. E.; Busby, J. T.; Duty, C. E. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.02.007	journal	August 2007
Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation Yutani, K.; Kishimoto, H.; Kasada, R. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.016	journal	August 2007
An exploratory study to determine applicability of nano-hardness and micro-compression measurements for yield stress estimation Hosemann, P.; Swadener, J. G.; Kiener, D. Journal of Nuclear Materials, Vol. 375, Issue 1 https://doi.org/10.1016/j.jnucmat.2007.11.004	journal	March 2008
Microstructural characterization of Y2O3 ODS–Fe–Cr model alloys de Castro, V.; Leguey, T.; Muñoz, A. Journal of Nuclear Materials, Vol. 386-388 https://doi.org/10.1016/j.jnucmat.2008.12.136	journal	April 2009
JANNUS: A multi-irradiation platform for experimental validation at the scale of the atomistic modelling Serruys, Y.; Trocellier, P.; Miro, S. Journal of Nuclear Materials, Vol. 386-388 https://doi.org/10.1016/j.jnucmat.2008.12.262	journal	April 2009
HRTEM study of oxide nanoparticles in K3-ODS ferritic steel developed for radiation tolerance Hsiung, L.; Fluss, M.; Tumey, S. Journal of Nuclear Materials, Vol. 409, Issue 2 https://doi.org/10.1016/j.jnucmat.2010.09.014	journal	February 2011
Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325°C up to 78dpa Henry, J.; Averty, X.; Alamo, A. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.203	journal	October 2011
Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40–110dpa at 400–750°C in FFTF Toloczko, M. B.; Garner, F. A.; Maloy, S. A. Journal of Nuclear Materials, Vol. 428, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.04.005	journal	September 2012
Structural and chemical matrix evolution following neutron irradiation in a MA957 oxide dispersion strengthened material Ribis, J. Journal of Nuclear Materials, Vol. 434, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.11.038	journal	March 2013
Nano-cluster stability following neutron irradiation in MA957 oxide dispersion strengthened material Ribis, J.; Lozano-Perez, S. Journal of Nuclear Materials, Vol. 444, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.010	journal	January 2014
Comparative study of helium effects on EU-ODS EUROFER and EUROFER97 by nanoindentation and TEM Roldán, M.; Fernández, P.; Rams, J. Journal of Nuclear Materials, Vol. 460 https://doi.org/10.1016/j.jnucmat.2015.02.025	journal	May 2015
Hydrogen-induced crack nucleation in tensile testing of EUROFER 97 and ODS-EUROFER steels at elevated temperature Malitckii, Evgenii; Yagodzinskyy, Yuriy; Hänninen, Hannu Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.08.016	journal	November 2015
Irradiation hardening of Fe–9Cr-based alloys and ODS Eurofer: Effect of helium implantation and iron-ion irradiation at 300 °C including sequence effects Heintze, C.; Bergner, F.; Hernández-Mayoral, M. Journal of Nuclear Materials, Vol. 470 https://doi.org/10.1016/j.jnucmat.2015.12.041	journal	March 2016
Nanoindentation and in situ microcompression in different dose regimes of proton beam irradiated 304 SS Reichardt, A.; Lupinacci, A.; Frazer, D. Journal of Nuclear Materials, Vol. 486 https://doi.org/10.1016/j.jnucmat.2017.01.036	journal	April 2017
Helium-ion microscopy, helium-ion irradiation and nanoindentation of Eurofer 97 and ODS Eurofer Bergner, F.; Hlawacek, G.; Heintze, C. Journal of Nuclear Materials, Vol. 505 https://doi.org/10.1016/j.jnucmat.2017.07.054	journal	July 2018
Load partitioning between ferrite/martensite and dispersed nanoparticles of a 9Cr ferritic/martensitic (F/M) ODS steel at high temperatures Zhang, Guangming; Mo, Kun; Miao, Yinbin Materials Science and Engineering: A, Vol. 637 https://doi.org/10.1016/j.msea.2015.04.037	journal	June 2015
Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I): Improvement of Mechanical Properties by Recrystallization Processing Ukai, Shigeharu; Nishida, Toshio; Okada, Hirokazu Journal of Nuclear Science and Technology, Vol. 34, Issue 3 https://doi.org/10.1080/18811248.1997.9733658	journal	March 1997
Development of Oxide Dispersion Strengthened Steels for FBR Core Application, (II) Ukai, Shigeharu; Nishida, Toshio; Okuda, Takanari Journal of Nuclear Science and Technology, Vol. 35, Issue 4 https://doi.org/10.1080/18811248.1998.9733859	journal	April 1998
The development of structural materials for fusion reactors Ehrlich, Karl Philosophical Transactions of the Royal Society of London. Series A: Mathematical, Physical and Engineering Sciences, Vol. 357, Issue 1752 https://doi.org/10.1098/rsta.1999.0343	journal	March 1999
Formation mechanism and the role of nanoparticles in Fe-Cr ODS steels developed for radiation tolerance Hsiung, Luke L.; Fluss, Michael J.; Tumey, Scott J. Physical Review B, Vol. 82, Issue 18 https://doi.org/10.1103/PhysRevB.82.184103	journal	November 2010
What is the Young's Modulus of Silicon? Hopcroft, Matthew A.; Nix, William D.; Kenny, Thomas W. Journal of Microelectromechanical Systems, Vol. 19, Issue 2 https://doi.org/10.1109/JMEMS.2009.2039697	journal	April 2010
Irradiated Materials Measurement Technology Gilbert, E. R.; Chin, B. A. Effects of Radiation on Materials https://doi.org/10.1520/STP28243S	book	January 1981
Void Swelling Resistance in Fe-Cr Alloys at 200 DPA Gelles, D. S. MRS Proceedings, Vol. 373 https://doi.org/10.1557/PROC-373-69	journal	January 1994
Fabrication technology for ODS Alloy MA957 Hamilton, M. L.; Gelles, D. S.; Lobsinger, R. J. https://doi.org/10.2172/752167	report	March 2000

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Title: Comparative Mechanical Properties Analysis of Triple Ion-Beam Irradiated and Neutron Irradiated Potential Plasma Facing Components

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