Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy

Zhu, Pengcheng; Zhao, Yajie; Lin, Yan-Ru; Henry, Jean; Zinkle, Steven J.

doi:10.1016/j.jnucmat.2023.154823

Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy

Journal Article · Sun Nov 19 00:00:00 EST 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154823· OSTI ID:2222632

^[1]; ^[2]; ^[3]; Henry, Jean ^[4]; ^[2]

Univ. of Tennessee, Knoxville, TN (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA-Saclay), Gif-sur-Yvette (France); Univ. Paris-Saclay, Gif-sur-Yvette (France)

Here, a high-purity binary alloy Fe18Cr was subjected to heavy-ion irradiation in order to provide improved understanding of the irradiation effect on radiation hardening associated with dislocation loop and network formation, α’ precipitation. The specimens were irradiated with 8 MeV Fe ions (~2 μm ion range) to midrange doses of 0.37 and 3.7 dpa at 300, 350 and 450 °C using dose rates of ~10^–5–10^–3 dpa/s. Nanoindentation testing was performed to extract the bulk equivalent hardness at low depth from these ion irradiated specimens. High-quality transmission electron microscopy (TEM) images were acquired by utilizing a flash electropolishing method on the Focused Ion Beam (FIB) prepared liftouts. An accurate calculation of the strength factor was provided based on detailed TEM characterization of the irradiated microstructures. A newly refined hardening superposition method was applied to combine the strengthening components from each microstructure. The good agreement between microstructure predicted strength and measured strength further demonstrated the fidelity to use hardening model to quantify the mechanical properties of ion irradiated materials.

View Accepted Manuscript (DOE)

Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA); USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: 89233218CNA000001; AC05-00OR22725; NE0000639; SC0023293

OSTI ID:: 2222632

Alternate ID(s):: OSTI ID: 2282932

Report Number(s):: LA-UR--23-31489

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 588; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (81)

A Statistical Theory of Solid Solution Hardening Labusch, R. physica status solidi (b), Vol. 41, Issue 2 https://doi.org/10.1002/pssb.19700410221	journal	January 1970
Composition and orientation dependence of the interfacial energy in Fe–Cr stainless steel alloys Lu, Song; Hu, Qing‐Miao; Johansson, Börje physica status solidi (b), Vol. 248, Issue 9 https://doi.org/10.1002/pssb.201147123	journal	March 2011
High-temperature phase equilibria in Cr-Cr3Si two-phase alloys Sutlijfand, J- A.; Bewlay, B. P.; Lipsitt, H. A. Journal of Phase Equilibria, Vol. 14, Issue 5 https://doi.org/10.1007/BF02669139	journal	October 1993
Precipitation hardening Ardell, A. J. Metallurgical Transactions A, Vol. 16, Issue 12 https://doi.org/10.1007/BF02670416	journal	December 1985
Large and Small Scale Materials Testing of HT-9 Irradiated in the STIP Irradiation Program Hosemann, P.; Dai, Y.; Stergar, E. Experimental Mechanics, Vol. 51, Issue 7 https://doi.org/10.1007/s11340-010-9419-2	journal	November 2010
The density and distribution of dislocations in deformed copper crystals Livingston, J. D. Acta Metallurgica, Vol. 10, Issue 3 https://doi.org/10.1016/0001-6160(62)90120-7	journal	March 1962
Deformation in an iron-30% chromium alloy aged at 475°c Lagneborg, R. Acta Metallurgica, Vol. 15, Issue 11 https://doi.org/10.1016/0001-6160(67)90065-X	journal	November 1967
Components of the flow stress of iron Dingley, D. J.; McLean, D. Acta Metallurgica, Vol. 15, Issue 5 https://doi.org/10.1016/0001-6160(67)90371-9	journal	May 1967
Effect of self-ion injection in simulation studies of void swelling Brailsford, A. D.; Mansur, L. K. Journal of Nuclear Materials, Vol. 71, Issue 1 https://doi.org/10.1016/0022-3115(77)90194-5	journal	December 1977
Low-dose neutron-irradiation damage in α-iron Robertson, I. M.; Jenkins, M. L.; English, C. A. Journal of Nuclear Materials, Vol. 108-109 https://doi.org/10.1016/0022-3115(82)90489-5	journal	July 1982
A TEM study of neutron-irradiated iron Horton, L. L.; Bentley, J.; Farrell, K. Journal of Nuclear Materials, Vol. 108-109 https://doi.org/10.1016/0022-3115(82)90490-1	journal	July 1982
Microstructural examination of neutron-irradiated simple ferritic alloys Gelles, D. S. Journal of Nuclear Materials, Vol. 108-109 https://doi.org/10.1016/0022-3115(82)90523-2	journal	July 1982
Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA Katoh, Yutai; Kohyama, Akira; Gelles, David S. Journal of Nuclear Materials, Vol. 225 https://doi.org/10.1016/0022-3115(94)00669-5	journal	August 1995
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
The effect of particle shape on dispersion hardening Kelly, P. M. Scripta Metallurgica, Vol. 6, Issue 8 https://doi.org/10.1016/0036-9748(72)90120-2	journal	August 1972
Recent progress in small specimen test technology Lucas, G. E.; Odette, G. R.; Sokolov, M. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01171-6	journal	December 2002
A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels Mathon, M. H.; de Carlan, Y.; Geoffroy, G. Journal of Nuclear Materials, Vol. 312, Issue 2-3 https://doi.org/10.1016/S0022-3115(02)01630-6	journal	February 2003
The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa Porollo, S. I.; Dvoriashin, A. M.; Vorobyev, A. N. Journal of Nuclear Materials, Vol. 256, Issue 2-3 https://doi.org/10.1016/S0022-3115(98)00043-9	journal	August 1998
Indentation size effects in crystalline materials: A law for strain gradient plasticity Nix, William D.; Gao, Huajian Journal of the Mechanics and Physics of Solids, Vol. 46, Issue 3 https://doi.org/10.1016/S0022-5096(97)00086-0	journal	March 1998
Physics and phenomenology of strain hardening: the FCC case Kocks, U. F.; Mecking, H. Progress in Materials Science, Vol. 48, Issue 3 https://doi.org/10.1016/S0079-6425(02)00003-8	journal	January 2003
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
The isotropic shear modulus of multicomponent Fe-base solid solutions Ghosh, G.; Olson, G. B. Acta Materialia, Vol. 50, Issue 10 https://doi.org/10.1016/S1359-6454(02)00096-4	journal	June 2002
High-pressure torsion of pure metals: Influence of atomic bond parameters and stacking fault energy on grain size and correlation with hardness Edalati, Kaveh; Horita, Zenji Acta Materialia, Vol. 59, Issue 17 https://doi.org/10.1016/j.actamat.2011.07.046	journal	October 2011
Impact of He and Cr on defect accumulation in ion-irradiated ultrahigh-purity Fe(Cr) alloys Prokhodtseva, A.; Décamps, B.; Ramar, A. Acta Materialia, Vol. 61, Issue 18 https://doi.org/10.1016/j.actamat.2013.08.007	journal	October 2013
Neutron irradiation effects in Fe and Fe-Cr at 300 °C Chen, Wei-Ying; Miao, Yinbin; Gan, Jian Acta Materialia, Vol. 111 https://doi.org/10.1016/j.actamat.2016.03.060	journal	June 2016
Influence of microstructural parameters on the mechanical properties of oxide dispersion strengthened Fe-14Cr steels Dadé, M.; Malaplate, J.; Garnier, J. Acta Materialia, Vol. 127 https://doi.org/10.1016/j.actamat.2017.01.026	journal	April 2017
On the origin of primary ½ a0 <111> and a0 <100> loops in irradiated Fe(Cr) alloys Schäublin, R.; Décamps, B.; Prokhodtseva, A. Acta Materialia, Vol. 133 https://doi.org/10.1016/j.actamat.2017.02.041	journal	July 2017
Dynamic observation of dual-beam irradiated Fe and Fe-10Cr alloys at 435 °C Lin, Yan-Ru; Chen, Wei-Ying; Li, Meimei Acta Materialia, Vol. 209 https://doi.org/10.1016/j.actamat.2021.116793	journal	May 2021
Effect of heavy ion irradiation dose rate and temperature on α′ precipitation in high purity Fe-18%Cr alloy Zhao, Yajie; Bhattacharya, Arunodaya; Pareige, Cristelle Acta Materialia, Vol. 231 https://doi.org/10.1016/j.actamat.2022.117888	journal	June 2022
A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques Kasada, Ryuta; Takayama, Yoshiyuki; Yabuuchi, Kiyohiro Fusion Engineering and Design, Vol. 86, Issue 9-11 https://doi.org/10.1016/j.fusengdes.2011.03.073	journal	October 2011
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
Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy Kessel, C. E.; Blanchard, J. P.; Davis, A. Fusion Engineering and Design, Vol. 135 https://doi.org/10.1016/j.fusengdes.2017.05.081	journal	October 2018
Modeling the microstructural evolution in bcc-Fe during irradiation using kinetic Monte Carlo computer simulation Soneda, N.; Ishino, S.; Takahashi, A. Journal of Nuclear Materials, Vol. 323, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2003.08.021	journal	December 2003
Observation and analysis of defect cluster production and interactions with dislocations Zinkle, S. J.; Matsukawa, Y. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.298	journal	August 2004
Effect of Cr on the mechanical properties and microstructure of Fe–Cr model alloys after n-irradiation Matijasevic, M.; Almazouzi, A. Journal of Nuclear Materials, Vol. 377, Issue 1 https://doi.org/10.1016/j.jnucmat.2008.02.061	journal	June 2008
Nanoindentation on ion irradiated steels Hosemann, P.; Vieh, C.; Greco, R. R. Journal of Nuclear Materials, Vol. 389, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.02.026	journal	May 2009
On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels Lambrecht, M.; Meslin, E.; Malerba, L. Journal of Nuclear Materials, Vol. 406, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.05.020	journal	November 2010
Study of the deformation mechanisms in a Fe–14% Cr ODS alloy Praud, M.; Mompiou, F.; Malaplate, J. Journal of Nuclear Materials, Vol. 428, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.10.046	journal	September 2012
Issues to consider using nano indentation on shallow ion beam irradiated materials Hosemann, Peter; Kiener, Daniel; Wang, Yongqiang Journal of Nuclear Materials, Vol. 425, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.11.070	journal	June 2012
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
TEM characterization of dislocation loops in irradiated bcc Fe-based steels Yao, B.; Edwards, D. J.; Kurtz, R. J. Journal of Nuclear Materials, Vol. 434, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.12.002	journal	March 2013
Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys Bergner, F.; Pareige, C.; Hernández-Mayoral, M. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.01.024	journal	May 2014
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.023	journal	October 2015
Formulating the strength factor α for improved predictability of radiation hardening Tan, L.; Busby, J. T. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.07.009	journal	October 2015
Irradiation hardening of pure tungsten exposed to neutron irradiation Hu, Xunxiang; Koyanagi, Takaaki; Fukuda, Makoto Journal of Nuclear Materials, Vol. 480 https://doi.org/10.1016/j.jnucmat.2016.08.024	journal	November 2016
Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9%Cr and Fe-14%Cr extruded bars Chauhan, A.; Bergner, F.; Etienne, A. Journal of Nuclear Materials, Vol. 495 https://doi.org/10.1016/j.jnucmat.2017.07.060	journal	November 2017
Ion-irradiation hardening and microstructural evolution in F82H and ferritic alloys Gao, Jin; Yabuuchi, Kiyohiro; Kimura, Akihiko Journal of Nuclear Materials, Vol. 515 https://doi.org/10.1016/j.jnucmat.2018.12.047	journal	March 2019
Microstructural changes and their effect on hardening in neutron irradiated Fe-Cr alloys Bhattacharyya, Dhriti; Yamamoto, Takuya; Wells, Peter Journal of Nuclear Materials, Vol. 519 https://doi.org/10.1016/j.jnucmat.2019.03.022	journal	June 2019
Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose Zheng, Ce; Reese, Elaina R.; Field, Kevin G. Journal of Nuclear Materials, Vol. 523 https://doi.org/10.1016/j.jnucmat.2019.06.019	journal	September 2019
Correlation of microstructural and mechanical properties of neutron irradiated EUROFER97 steel Klimenkov, M.; Jäntsch, U.; Rieth, M. Journal of Nuclear Materials, Vol. 538 https://doi.org/10.1016/j.jnucmat.2020.152231	journal	September 2020
Effect of Cr Concentration on ½<111> to <100> Dislocation Loop Transformation in Fe-Cr alloys Zhang, Yaxuan; Xiao, Ziqi; Bai, Xian-Ming Journal of Nuclear Materials, Vol. 543 https://doi.org/10.1016/j.jnucmat.2020.152592	journal	January 2021
Influence of carbon on the evolution of irradiation defects in tungsten Niu, Yu-Ze; Li, Yu-Hao; Ren, Qing-Yuan Journal of Nuclear Materials, Vol. 579 https://doi.org/10.1016/j.jnucmat.2023.154393	journal	June 2023
Effect of cascade size and damage rate on α’ precipitate stability in Fe-15Cr Thomas, Katey N.; Was, Gary S. Journal of Nuclear Materials, Vol. 585 https://doi.org/10.1016/j.jnucmat.2023.154615	journal	November 2023
Flash electropolishing of BCC Fe and Fe-based alloys Li, Yao; Song, Miao; Zhu, Pengcheng Journal of Nuclear Materials, Vol. 586 https://doi.org/10.1016/j.jnucmat.2023.154672	journal	December 2023
Toward accurate evaluation of bulk hardness from nanoindentation testing at low indent depths Zhu, Pengcheng; Zhao, Yajie; Agarwal, Shradha Materials & Design, Vol. 213 https://doi.org/10.1016/j.matdes.2021.110317	journal	January 2022
Comparing structure-property evolution for PM-HIP and forged alloy 625 irradiated with neutrons to 1 dpa Clement, Caleb; Panuganti, Sowmya; Warren, Patrick H. Materials Science and Engineering: A, Vol. 857 https://doi.org/10.1016/j.msea.2022.144058	journal	November 2022
On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options Agarwal, S.; Lin, Y.; Li, C. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 503 https://doi.org/10.1016/j.nimb.2021.06.018	journal	September 2021
On the α–α′ miscibility gap of Fe–Cr alloys Bonny, G.; Terentyev, D.; Malerba, L. Scripta Materialia, Vol. 59, Issue 11 https://doi.org/10.1016/j.scriptamat.2008.08.008	journal	December 2008
Small-scale mechanical testing on nuclear materials: bridging the experimental length-scale gap Hosemann, Peter Scripta Materialia, Vol. 143 https://doi.org/10.1016/j.scriptamat.2017.04.026	journal	January 2018
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
Dose rate dependence of Cr precipitation in an ion-irradiated Fe 18Cr alloy Reese, Elaina R.; Almirall, Nathan; Yamamoto, Takuya Scripta Materialia, Vol. 146 https://doi.org/10.1016/j.scriptamat.2017.11.040	journal	March 2018
Effect of dose rate on dislocation loop evolution in tungsten: Combination of defect generation rate and elastic interaction Ding, Yifan; Ran, Guang; Li, Yipeng Scripta Materialia, Vol. 222 https://doi.org/10.1016/j.scriptamat.2022.115054	journal	January 2023
Elastic interaction between prismatic dislocation loops and straight dislocations Kroupa, F.; Hirsch, P. B. Discussions of the Faraday Society, Vol. 38 https://doi.org/10.1039/df9643800049	journal	January 1964
Structure and Mössbauer spectra for the Fe–Cr system: From bulk alloy to nanoparticles Petrov, Yu. I.; Shafranovsky, E. A.; Krupyanskii, Yu. F. Journal of Applied Physics, Vol. 91, Issue 1 https://doi.org/10.1063/1.1415367	journal	January 2002
The Effect of Prestressing on the Strength of Neutron‐Irradiated Copper Single Crystals Koppenaal, T. J.; Kuhlmann‐Wilsdorf, D. Applied Physics Letters, Vol. 4, Issue 3 https://doi.org/10.1063/1.1753962	journal	February 1964
Steady-state point-defect diffusion profiles in solids during irradiation Lam, Nghi Q.; Rothman, Steven J.; Sizmanns, Rudolf Radiation Effects, Vol. 23, Issue 1 https://doi.org/10.1080/00337577408232045	journal	January 1974
Irradiation hardening of reactor pressure vessel steels due to the dislocation loop evolution Dubinko, V. I.; Kotrechko, S. A.; Klepikov, V. F. Radiation Effects and Defects in Solids, Vol. 164, Issue 10 https://doi.org/10.1080/10420150903115743	journal	October 2009
Recent progress in understanding reactor pressure vessel steel embrittlement Odette, G. R.; Lucas, G. E. Radiation Effects and Defects in Solids, Vol. 144, Issue 1-4 https://doi.org/10.1080/10420159808229676	journal	June 1998
Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses Yao, Z.; Hernández-Mayoral, M.; Jenkins, M. L. Philosophical Magazine, Vol. 88, Issue 21 https://doi.org/10.1080/14786430802380469	journal	July 2008
Work-hardening and work-softening of face-centred cubic metal crystals Seeger, A.; Diehl, J.; Mader, S. Philosophical Magazine, Vol. 2, Issue 15 https://doi.org/10.1080/14786435708243823	journal	March 1957
Dislocation movement through random arrays of obstacles Foreman, A. J. E.; Makin, M. J. Philosophical Magazine, Vol. 14, Issue 131 https://doi.org/10.1080/14786436608244762	journal	October 1966
The dependence of yield stress on forest dislocation density in copper single crystals Brydges, W. T. Philosophical Magazine, Vol. 15, Issue 137 https://doi.org/10.1080/14786436708221657	journal	May 1967
Modeling of irradiation hardening of iron after low-dose and low-temperature neutron irradiation Hu, Xunxiang; Xu, Donghua; Byun, Thak Sang Modelling and Simulation in Materials Science and Engineering, Vol. 22, Issue 6 https://doi.org/10.1088/0965-0393/22/6/065002	journal	July 2014
Multi-scale simulation of radiation damage accumulation and subsequent hardening in neutron-irradiated α -Fe Dunn, Aaron; Dingreville, Rémi; Capolungo, Laurent Modelling and Simulation in Materials Science and Engineering, Vol. 24, Issue 1 https://doi.org/10.1088/0965-0393/24/1/015005	journal	November 2015
Precision Measurements of the Lattice Constants of Twelve Common Metals Davey, Wheeler P. Physical Review, Vol. 25, Issue 6 https://doi.org/10.1103/PhysRev.25.753	journal	June 1925
Dislocation Movement Through Random Arrays of Obstacles Foreman, A. J. E.; Makin, M. J. Canadian Journal of Physics, Vol. 45, Issue 2 https://doi.org/10.1139/p67-044	journal	February 1967
Latent Hardening and the flow Stress in Copper Single Crystals Jackson, P. J.; Basinski, Z. S. Canadian Journal of Physics, Vol. 45, Issue 2 https://doi.org/10.1139/p67-055	journal	February 1967
The Indentation Size Effect: A Critical Examination of Experimental Observations and Mechanistic Interpretations Pharr, George M.; Herbert, Erik G.; Gao, Yanfei Annual Review of Materials Research, Vol. 40, Issue 1 https://doi.org/10.1146/annurev-matsci-070909-104456	journal	June 2010
An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments Oliver, W. C.; Pharr, G. M. Journal of Materials Research, Vol. 7, Issue 06, p. 1564-1583 https://doi.org/10.1557/JMR.1992.1564	journal	June 1992
Measurement of Thin Film Mechanical Properties Using Nanoindentation Pharr, G. M.; Oliver, W. C. MRS Bulletin, Vol. 17, Issue 7 https://doi.org/10.1557/S0883769400041634	journal	July 1992
Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys Parish, Chad M.; Field, Kevin G.; Certain, Alicia G. Journal of Materials Research, Vol. 30, Issue 9 https://doi.org/10.1557/jmr.2015.32	journal	April 2015

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