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

A. Prasitthipayong, D. Frazer, A. Kareer, M. D. Abad, A. Garner, B. Joni, T. Ungár, G. Ribárik, M. Preuss, L. Balogh, S. J. Tumey, A. M. Minor, P. Hosemann

Research output: Contribution to journalArticle

8 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)34-45
Number of pages12
JournalNuclear Materials and Energy
Volume16
DOIs
Publication statusPublished - Aug 1 2018

Fingerprint

Mechanical testing
nuclear reactors
Nanoindentation
Nuclear reactors
nanoindentation
Irradiation
Ion bombardment
ion irradiation
irradiation
mechanical properties
Ions
Nanocrystalline alloys
damage
Mechanical properties
Neutron irradiation
neutron irradiation
hardening
Oxides
Yield stress
Hardening

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science (miscellaneous)
  • Nuclear Energy and Engineering

Cite this

Prasitthipayong, A., Frazer, D., Kareer, A., Abad, M. D., Garner, A., Joni, B., ... Hosemann, P. (2018). Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors. Nuclear Materials and Energy, 16, 34-45. https://doi.org/10.1016/j.nme.2018.05.018

Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors. / Prasitthipayong, A.; Frazer, D.; Kareer, A.; Abad, M. D.; Garner, A.; Joni, B.; Ungár, T.; Ribárik, G.; Preuss, M.; Balogh, L.; Tumey, S. J.; Minor, A. M.; Hosemann, P.

In: Nuclear Materials and Energy, Vol. 16, 01.08.2018, p. 34-45.

Research output: Contribution to journalArticle

Prasitthipayong, A, Frazer, D, Kareer, A, Abad, MD, Garner, A, Joni, B, Ungár, T, Ribárik, G, Preuss, M, Balogh, L, Tumey, SJ, Minor, AM & Hosemann, P 2018, 'Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors', Nuclear Materials and Energy, vol. 16, pp. 34-45. https://doi.org/10.1016/j.nme.2018.05.018
Prasitthipayong, A. ; Frazer, D. ; Kareer, A. ; Abad, M. D. ; Garner, A. ; Joni, B. ; Ungár, T. ; Ribárik, G. ; Preuss, M. ; Balogh, L. ; Tumey, S. J. ; Minor, A. M. ; Hosemann, P. / Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors. In: Nuclear Materials and Energy. 2018 ; Vol. 16. pp. 34-45.
@article{e42bc5b613da4a0aa90ba111b5b35db8,
title = "Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors",
abstract = "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.",
author = "A. Prasitthipayong and D. Frazer and A. Kareer and Abad, {M. D.} and A. Garner and B. Joni and T. Ung{\'a}r and G. Rib{\'a}rik and M. Preuss and L. Balogh and Tumey, {S. J.} and Minor, {A. M.} and P. Hosemann",
year = "2018",
month = "8",
day = "1",
doi = "10.1016/j.nme.2018.05.018",
language = "English",
volume = "16",
pages = "34--45",
journal = "Nuclear Materials and Energy",
issn = "2352-1791",
publisher = "Elsevier Limited",

}

TY - JOUR

T1 - Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors

AU - Prasitthipayong, A.

AU - Frazer, D.

AU - Kareer, A.

AU - Abad, M. D.

AU - Garner, A.

AU - Joni, B.

AU - Ungár, T.

AU - Ribárik, G.

AU - Preuss, M.

AU - Balogh, L.

AU - Tumey, S. J.

AU - Minor, A. M.

AU - Hosemann, P.

PY - 2018/8/1

Y1 - 2018/8/1

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=85048783969&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85048783969&partnerID=8YFLogxK

U2 - 10.1016/j.nme.2018.05.018

DO - 10.1016/j.nme.2018.05.018

M3 - Article

AN - SCOPUS:85048783969

VL - 16

SP - 34

EP - 45

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

SN - 2352-1791

ER -