Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors

Ion irradiation is often used to simulate the effects of neutron irradiation due to reduced activation of materials and vastly increased dose rates. However, the low penetration depth of ions requires the development of small-scale mechanical testing techniques, such as nanoindentation and microcomp...

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Main Authors:	A. Prasitthipayong, D. Frazer, A. Kareer, M.D. Abad, A. Garner, B. Joni, T. Ungar, G. Ribarik, M. Preuss, L. Balogh, S.J. Tumey, A.M. Minor, P. Hosemann
Format:	Article
Language:	English
Published:	Elsevier 2018-08-01
Series:	Nuclear Materials and Energy
Online Access:	http://www.sciencedirect.com/science/article/pii/S235217911830022X

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spelling	doaj-f6095ed5f3454878b851e58c08537a1f2020-11-24T23:11:09ZengElsevierNuclear Materials and Energy2352-17912018-08-01163445Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactorsA. Prasitthipayong0D. Frazer1A. Kareer2M.D. Abad3A. Garner4B. Joni5T. Ungar6G. Ribarik7M. Preuss8L. Balogh9S.J. Tumey10A.M. Minor11P. Hosemann12Department of Materials Science and Engineering, University of California, Berkeley, CA, USA; Corresponding author.Department of Nuclear Engineering, University of California, Berkeley, CA, USADepartment of Materials, University of Oxford, Parks road, Oxford OX1 3PH, UKDepartment of Nuclear Engineering, University of California, Berkeley, CA, USAMaterials Performance Center, University of Manchester, Oxford Road, Manchester M13 9PL, UKDepartment of Materials Physics, Eötvös Loránd University Budapest, PO Box 32, Budapest H-1518, HungaryMaterials Performance Center, University of Manchester, Oxford Road, Manchester M13 9PL, UK; Department of Materials Physics, Eötvös Loránd University Budapest, PO Box 32, Budapest H-1518, HungaryDepartment of Materials Physics, Eötvös Loránd University Budapest, PO Box 32, Budapest H-1518, HungaryMaterials Performance Center, University of Manchester, Oxford Road, Manchester M13 9PL, UKDepartment of Mechanical and Materials Engineering, Queen's University, Kingston, ON K7L 3N6, CanadaCenter of Accelerator Mass Spectrometry, Lawrence Livermore National Laboratory, Livermore, CA, USADepartment of Materials Science and Engineering, University of California, Berkeley, CA, USA; National Center for Electron Microscopy, The Molecular Foundry, Lawrence Berkeley National Laboratory, Berkeley, CA, USADepartment of Nuclear Engineering, University of California, Berkeley, CA, USAIon irradiation is often used to simulate the effects of neutron irradiation due to reduced activation of materials and vastly increased dose rates. However, the low penetration depth of ions requires the development of small-scale mechanical testing techniques, such as nanoindentation and microcompression, in order to measure mechanical properties of the irradiated material. In this study, several candidate structural alloys for Gen-IV reactors (800H, T91, nanocrystalline T91 and 14YWT) were irradiated with 70 MeV Fe9+ ions at 452 °C to an average damage of 20.68 dpa. Both the nanoindentation and microcompression techniques revealed significant irradiation hardening and an increase in yield stress after irradiation in austenitic 800H and ferritic-martensitic T91 alloys. Ion irradiation was observed to have minimal effect on the mechanical properties of nanocrystalline T91 and oxide dispersion strengthened 14YWT. These observations are further supported by line broadening analysis of X-ray diffraction measurements, which show a significantly smaller increase in dislocation density in the 14YWT and nanocrystalline T91 alloys after irradiation. In addition, good agreement was observed between cross-sectional nanoindentation and the damage profile from SRIM calculations.http://www.sciencedirect.com/science/article/pii/S235217911830022X
collection	DOAJ
language	English
format	Article
sources	DOAJ
author	A. Prasitthipayong D. Frazer A. Kareer M.D. Abad A. Garner B. Joni T. Ungar G. Ribarik M. Preuss L. Balogh S.J. Tumey A.M. Minor P. Hosemann
spellingShingle	A. Prasitthipayong D. Frazer A. Kareer M.D. Abad A. Garner B. Joni T. Ungar G. Ribarik M. Preuss L. Balogh S.J. Tumey A.M. Minor P. Hosemann Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors Nuclear Materials and Energy
author_facet	A. Prasitthipayong D. Frazer A. Kareer M.D. Abad A. Garner B. Joni T. Ungar G. Ribarik M. Preuss L. Balogh S.J. Tumey A.M. Minor P. Hosemann
author_sort	A. Prasitthipayong
title	Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
title_short	Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
title_full	Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
title_fullStr	Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
title_full_unstemmed	Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
title_sort	micro mechanical testing of candidate structural alloys for gen-iv nuclear reactors
publisher	Elsevier
series	Nuclear Materials and Energy
issn	2352-1791
publishDate	2018-08-01
description	Ion irradiation is often used to simulate the effects of neutron irradiation due to reduced activation of materials and vastly increased dose rates. However, the low penetration depth of ions requires the development of small-scale mechanical testing techniques, such as nanoindentation and microcompression, in order to measure mechanical properties of the irradiated material. In this study, several candidate structural alloys for Gen-IV reactors (800H, T91, nanocrystalline T91 and 14YWT) were irradiated with 70 MeV Fe9+ ions at 452 °C to an average damage of 20.68 dpa. Both the nanoindentation and microcompression techniques revealed significant irradiation hardening and an increase in yield stress after irradiation in austenitic 800H and ferritic-martensitic T91 alloys. Ion irradiation was observed to have minimal effect on the mechanical properties of nanocrystalline T91 and oxide dispersion strengthened 14YWT. These observations are further supported by line broadening analysis of X-ray diffraction measurements, which show a significantly smaller increase in dislocation density in the 14YWT and nanocrystalline T91 alloys after irradiation. In addition, good agreement was observed between cross-sectional nanoindentation and the damage profile from SRIM calculations.
url	http://www.sciencedirect.com/science/article/pii/S235217911830022X
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Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors

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