The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9

Chen, Tianyi; He, Lingfeng; Cullison, Mack H.; Hay, Charles; Burns, Jatuporn; Wu, Yaqiao; Tan, Lizhen

doi:10.1016/j.actamat.2020.05.020

Title: The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9

Journal Article · Sat May 16 00:00:00 EDT 2020 · Acta Materialia

DOI:https://doi.org/10.1016/j.actamat.2020.05.020· OSTI ID:1649397

^[1];

^[2]; Cullison, Mack H. ^[3]; Hay, Charles ^[3]; Burns, Jatuporn ^[4]; Wu, Yaqiao ^[4];

^[5]

Oregon State Univ., Corvallis, OR (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Oregon State Univ., Corvallis, OR (United States)
Boise State Univ., ID (United States); Center for Advanced Energy Studies, Idaho Falls, ID (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The microstructure and nanomechanical properties of three samples of the modified stainless steel (referred as the alloy D9) were systematically characterized after neutron irradiation in the Advanced Test Reactor. The samples were irradiated to 5.0, 8.2, and 9.2 displacements per atom at 448, 430, and 683°C, respectively. The evolutions of dislocation loops, cavities, and radiation-induced precipitates were quantitatively studied to reveal their dose and temperature dependencies. Nanohardness and nanoindentation creep tests were conducted at room temperature on the irradiated samples. Unexpected radiation hardening was observed in the highest-temperature-irradiated sample due to the formation of an unknown type of Ni- and Si-rich precipitates whose contributions to the radiation and mechanical performances of the alloy were discussed. We provide the radiation-microstructure-property correlations of alloy D9 with new insights, which can benefit the development and optimization of advanced austenitic alloys for future nuclear applications.

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Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1649397

Alternate ID(s):: OSTI ID: 1633356

Journal Information:: Acta Materialia, Vol. 195, Issue n/a; ISSN 1359-6454

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 8 works

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References (55)

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
Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels Busby, J. T.; Was, G. S.; Kenik, E. A. Journal of Nuclear Materials, Vol. 302, Issue 1 https://doi.org/10.1016/S0022-3115(02)00719-5	journal	April 2002
Irradiation-assisted stress corrosion cracking of austenitic alloys in supercritical water Zhou, Rongsheng; West, Elaine A.; Jiao, Zhijie Journal of Nuclear Materials, Vol. 395, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2009.09.010	journal	December 2009
Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals Bruemmer, S. M.; Simonen, E. P.; Scott, P. M. Journal of Nuclear Materials, Vol. 274, Issue 3 https://doi.org/10.1016/S0022-3115(99)00075-6	journal	September 1999
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
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel Zinkle, S. J.; Maziasz, P. J.; Stoller, R. E. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90128-L	journal	November 1993
Relationships between phase stability and void swelling in Fe-Cr-Ni alloys during irradiation Lee, E. H.; Mansur, L. K. Metallurgical Transactions A, Vol. 23, Issue 7 https://doi.org/10.1007/BF02647545	journal	July 1992
Alloying effect of Ni and Cr on irradiated microstructural evolution of type 304 stainless steels Tan, L.; Busby, J. T. Journal of Nuclear Materials, Vol. 443, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.054	journal	November 2013
Overview of microstructural evolution in neutron-irradiated austenitic stainless steels Maziasz, P. J. Journal of Nuclear Materials, Vol. 205 https://doi.org/10.1016/0022-3115(93)90077-C	journal	October 1993
Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels Maziasz, P. J. Journal of Nuclear Materials, Vol. 169 https://doi.org/10.1016/0022-3115(89)90525-4	journal	December 1989
Defect development in neutron irradiated type 316 stainless steel Brager, H. R.; Straalsund, J. L. Journal of Nuclear Materials, Vol. 46, Issue 2 https://doi.org/10.1016/0022-3115(73)90131-1	journal	March 1973
The effect of stress on the microstructure of neutron irradiated type 316 stainless steel Brager, H. R.; Garner, F. A.; Guthrie, G. L. Journal of Nuclear Materials, Vol. 66, Issue 3 https://doi.org/10.1016/0022-3115(77)90119-2	journal	May 1977
Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS Edwards, D. J.; Simonen, E. P.; Garner, F. A. Journal of Nuclear Materials, Vol. 317, Issue 1 https://doi.org/10.1016/S0022-3115(03)00003-5	journal	April 2003
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
Flux and composition dependence of irradiation creep of austenitic alloys irradiated in PFR at ∼420°C Toloczko, M. B.; Garner, F. A.; Standring, J. Journal of Nuclear Materials, Vol. 258-263 https://doi.org/10.1016/S0022-3115(98)00158-5	journal	October 1998
Integrated modeling of second phase precipitation in cold-worked 316 stainless steels under irradiation Mamivand, Mahmood; Yang, Ying; Busby, Jeremy Acta Materialia, Vol. 130 https://doi.org/10.1016/j.actamat.2017.03.025	journal	May 2017
A transmission electron microscopy study of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750 Liu, Xiang; He, Lingfeng; Yan, Huan Journal of Nuclear Materials, Vol. 528 https://doi.org/10.1016/j.jnucmat.2019.151851	journal	January 2020
Radiation swelling of modified austenitic steels Neklyudov, I. M.; Voyevodin, V. N. Russian Physics Journal, Vol. 51, Issue 4 https://doi.org/10.1007/s11182-008-9063-9	journal	April 2008
The evolution of mechanical property change in irradiated austenitic stainless steels Lucas, G. E. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90129-M	journal	November 1993
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
Interactions between displacement cascade and dislocation and their influences on Peierls stress in Fe-20Cr-25Ni alloys Lu, Zizhe; Xu, Liubin; Chen, Tianyi Computational Materials Science, Vol. 160 https://doi.org/10.1016/j.commatsci.2018.12.018	journal	April 2019
Elevated temperature irradiation hardening in austenitic stainless steel Holmes, J. J.; Robbins, R. E.; Brimhall, J. L. Acta Metallurgica, Vol. 16, Issue 7 https://doi.org/10.1016/0001-6160(68)90062-X	journal	July 1968
Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels Pawel, J. E.; Rowcliffe, A. F.; Alexander, D. J. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00218-8	journal	October 1996
Effect of fast-neutron irradiation on mechanical properties of stainless steels: AISI types 304, 316 and 347 Higgy, H. R.; Hammad, F. H. Journal of Nuclear Materials, Vol. 55, Issue 2 https://doi.org/10.1016/0022-3115(75)90151-8	journal	February 1975
Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences Mansur, L. K.; Rowcliffe, A. F.; Nanstad, R. K. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.016	journal	August 2004
Fuels for sodium-cooled fast reactors: US perspective Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.010	journal	September 2007
Austenitic Stainless Steels for Fast Reactors -Irradiation Experiments, Property Evaluation and Microstructural Studies Karthik, V.; Murugan, S.; Parameswaran, P. Energy Procedia, Vol. 7 https://doi.org/10.1016/j.egypro.2011.06.033	journal	January 2011
Comparison of fracture behavior for low-swelling ferritic and austenitic alloys irradiated in the Fast Flux Test Facility (FFTF) to 180 DPA Huang, F. H. Engineering Fracture Mechanics, Vol. 43, Issue 5 https://doi.org/10.1016/0013-7944(92)90004-X	journal	November 1992
Irradiation Performance of Fast Flux Test Facility Drivers Using D9 Alloy Pitner, A. L.; Gneiting, B. C.; Bard, F. E. Nuclear Technology, Vol. 112, Issue 2 https://doi.org/10.13182/NT95-A35173	journal	November 1995
Materials Challenges for Generation IV Nuclear Energy Systems Allen, T. R.; Sridharan, K.; Tan, L. Nuclear Technology, Vol. 162, Issue 3 https://doi.org/10.13182/NT08-A3961	journal	June 2008
Void swelling resistance of phosphorus-modified austenitic stainless steels during HFIR irradiation at 300–500°C to 57 dpa Maziasz, P. J. Journal of Nuclear Materials, Vol. 200, Issue 1 https://doi.org/10.1016/0022-3115(93)90013-O	journal	March 1993
Mechanical property changes induced in structural alloys by neutron irradiations with different helium to displacement ratios Mansur, L. K.; Grossbeck, M. L. Journal of Nuclear Materials, Vol. 155-157 https://doi.org/10.1016/0022-3115(88)90235-8	journal	July 1988
Correlation of Nanoindentation and Conventional Mechanical Property Measurements Rice, Philip M.; Stoller, Roger E. MRS Proceedings, Vol. 649 https://doi.org/10.1557/PROC-649-Q7.11	journal	January 2000
The relationship between hardness and yield stress in irradiated austenitic and ferritic steels Busby, Jeremy T.; Hash, Mark C.; Was, Gary S. Journal of Nuclear Materials, Vol. 336, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.09.024	journal	February 2005
Nano-Scale Indentation Creep Testing at Non-Ambient Temperature Syed Asif, S. A.; Pethica, J. B. The Journal of Adhesion, Vol. 67, Issue 1-4 https://doi.org/10.1080/00218469808011105	journal	May 1998
The effect of grain orientation on nanoindentation behavior of model austenitic alloy Fe-20Cr-25Ni Chen, Tianyi; Tan, Lizhen; Lu, Zizhe Acta Materialia, Vol. 138 https://doi.org/10.1016/j.actamat.2017.07.028	journal	October 2017
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
Microstructural evolution of NF709 (20Cr–25Ni–1.5MoNbTiN) under neutron irradiation Kim, B. K.; Tan, L.; Xu, C. Journal of Nuclear Materials, Vol. 470 https://doi.org/10.1016/j.jnucmat.2015.12.037	journal	March 2016
Evaluation of strain-rate sensitivity of ion-irradiated austenitic steel using strain-rate jump nanoindentation tests Kasada, Ryuta; Konishi, Satoshi; Hamaguchi, Dai Fusion Engineering and Design, Vol. 109-111 https://doi.org/10.1016/j.fusengdes.2015.11.041	journal	November 2016
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
Critical examination of strain-rate sensitivity measurement by nanoindentation methods: Application to severely deformed niobium Alkorta, Jon; Martínez-Esnaola, José Manuel; Gil Sevillano, Javier Acta Materialia, Vol. 56, Issue 4 https://doi.org/10.1016/j.actamat.2007.10.039	journal	February 2008
Thermomechanical treatment for improved neutron irradiation resistance of austenitic alloy (Fe–21Cr–32Ni) Tan, L.; Busby, J. T.; Chichester, H. J. M. Journal of Nuclear Materials, Vol. 437, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.01.333	journal	June 2013
Radiation-induced grain boundary segregation and sensitization of a neutron-irradiated austenitic stainless steel Kenik, E. A.; Inazumi, T.; Bell, G. E. C. Journal of Nuclear Materials, Vol. 183, Issue 3 https://doi.org/10.1016/0022-3115(91)90482-M	journal	August 1991
The interfacial orientation relationship of oxide nanoparticles in a hafnium-containing oxide dispersion-strengthened austenitic stainless steel Miao, Yinbin; Mo, Kun; Cui, Bai Materials Characterization, Vol. 101 https://doi.org/10.1016/j.matchar.2015.01.015	journal	March 2015
Near-surface segregation in irradiated Ni ₃ Si Wagner, W.; Rehn, L. E.; Wiedersich, H. Philosophical Magazine A, Vol. 45, Issue 6 https://doi.org/10.1080/01418618208240910	journal	June 1982
Influence of Silicon and Phosphorus on Radiation-Induced Segregation of Chromium and Nickel in Austenitic Model Alloys Sakaguchi, Norihito; Takahashi, Heishichiro; Ichinose, Hideki MATERIALS TRANSACTIONS, Vol. 46, Issue 3 https://doi.org/10.2320/matertrans.46.440	journal	January 2005
Solute segregation in metals under irradiation Johnson, Robert A.; Lam, Nghi Q. Physical Review B, Vol. 13, Issue 10 https://doi.org/10.1103/PhysRevB.13.4364	journal	May 1976
A model for segregation in dilute alloys during irradiation Murphy, S. M. Journal of Nuclear Materials, Vol. 168, Issue 1-2 https://doi.org/10.1016/0022-3115(89)90561-8	journal	October 1989
Understanding silicon-rich phase precipitation under irradiation in austenitic stainless steels Etienne, A.; Radiguet, B.; Pareige, P. Journal of Nuclear Materials, Vol. 406, Issue 2 https://doi.org/10.1016/j.jnucmat.2010.08.045	journal	November 2010
Radiation-induced segregation in FFTF-irradiated austenitic stainless steels Kenik, E. A.; Hojou, K. Journal of Nuclear Materials, Vol. 191-194 https://doi.org/10.1016/0022-3115(92)90691-D	journal	September 1992
Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation Chen, Tianyi; Aydogan, Eda; Gigax, Jonathan G. Journal of Nuclear Materials, Vol. 467 https://doi.org/10.1016/j.jnucmat.2015.09.016	journal	December 2015
Theoretical evaluation of a mechanism of precipitate-enhanced cavity swelling during irradiation Mansur, L. K. Philosophical Magazine A, Vol. 44, Issue 4 https://doi.org/10.1080/01418618108239554	journal	October 1981
Radiation response of oxide-dispersion-strengthened alloy MA956 after self-ion irradiation Chen, Tianyi; Kim, Hyosim; Gigax, Jonathan G. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 409 https://doi.org/10.1016/j.nimb.2017.05.024	journal	October 2017
On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials Stoller, R. E.; Zinkle, S. J. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00378-0	journal	December 2000
Microstructural defect evolution in neutron – Irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing Tsay, K. V.; Maksimkin, O. P.; Turubarova, L. G. Journal of Nuclear Materials, Vol. 439, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.086	journal	August 2013

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