Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization

Miao Song; Calvin R. Lear; Chad M. Parish; Mi Wang; Gary S. Was

doi:10.1016/j.jnucmat.2018.08.035

Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization

Miao Song, Calvin R. Lear, Chad M. Parish, Mi Wang, Gary S. Was

Nuclear Energy Materials Microanalysis

Research output: Contribution to journal › Article › peer-review

30 Scopus citations

Abstract

Thirteen austenitic stainless steels, nickel-base alloys, and ferritic alloys were irradiated using 2 MeV protons at 360 °C to a damage level of 2.5 displacements per atom (dpa). Comprehensive microstructural characterization was performed for irradiation-induced features, including dislocation loops, voids, precipitates, and radiation induced segregation (RIS). Dislocation loops formed in all alloys except 14YWT, while voids were observed in alloys 316 L, 310, C22, and 14YWT. Irradiation-induced formation of γ′ precipitates was observed in alloys 316 L, 310, 800, and 690; the irradiation-enhanced, long-range ordered Ni₂Cr phase (Pt₂Mo-type) was observed in alloys 690, C22, 625, 625Plus, 625DA, and 725; and G-phase was observed in alloy T92. No irradiation-induced precipitates were observed in alloys X750, 718 or 14YWT. Precipitation of the γ′ phase can be understood through segregation and clustering of Si, Al, and Ti. Overall, austenitic stainless steels are generally susceptible to irradiation damage in the form of loops, voids, precipitates, and RIS. Ni-base alloys have this same type of dislocation loops and RIS behaviors but are more resistant to void swelling. Ferritic alloys showed better resistance to loop formation, void swelling and irradiation-induced precipitation. From the degree of irradiation-induced microstructural change, alloy T92 was identified as the most radiation resistant among these alloys.

Original language	English
Pages (from-to)	396-413
Number of pages	18
Journal	Journal of Nuclear Materials
Volume	510
DOIs	https://doi.org/10.1016/j.jnucmat.2018.08.035
State	Published - Nov 2018

Funding

The authors acknowledge the financial support by EPRI (contracts 10002164 and 10002154 ), and DOE (contract 4000136101 ). This work was also supported by DOE NE under DOE Idaho Operations Office Contract DE-AC07-051D14517 as part of a Nuclear Science User Facilities experiment. The authors gratefully acknowledge O. Toader, T. Kubley and E. Uberseder at the Michigan Ion Beam Laboratory and D. Woodley at University of Michigan for their assistance with the proton irradiations. The authors also thank Dr. Lizhen Tan at ORNL for providing the ferritic steels in this study. M.S also acknowledges Dr. K. Sun for help with the TEM, and Dr. Z. Jiao for stimulating discussion at University of Michigan. Access to the microscopes of the Michigan Center for Materials Characterization (MC 2 ) at University of Michigan is also acknowledged.

Funders	Funder number
DOE NE	DE-AC07-051D14517
U.S. Department of Energy	4000136101
Electric Power Research Institute	10002154, 10002164

Keywords

Microstructure
Nickel-base alloy
Precipitate
Radiation damage
Structure material

Access to Document

10.1016/j.jnucmat.2018.08.035

Cite this

@article{da81edd180c84cdc94b0a1d5b41decd5,

title = "Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization",

abstract = "Thirteen austenitic stainless steels, nickel-base alloys, and ferritic alloys were irradiated using 2 MeV protons at 360 °C to a damage level of 2.5 displacements per atom (dpa). Comprehensive microstructural characterization was performed for irradiation-induced features, including dislocation loops, voids, precipitates, and radiation induced segregation (RIS). Dislocation loops formed in all alloys except 14YWT, while voids were observed in alloys 316 L, 310, C22, and 14YWT. Irradiation-induced formation of γ′ precipitates was observed in alloys 316 L, 310, 800, and 690; the irradiation-enhanced, long-range ordered Ni2Cr phase (Pt2Mo-type) was observed in alloys 690, C22, 625, 625Plus, 625DA, and 725; and G-phase was observed in alloy T92. No irradiation-induced precipitates were observed in alloys X750, 718 or 14YWT. Precipitation of the γ′ phase can be understood through segregation and clustering of Si, Al, and Ti. Overall, austenitic stainless steels are generally susceptible to irradiation damage in the form of loops, voids, precipitates, and RIS. Ni-base alloys have this same type of dislocation loops and RIS behaviors but are more resistant to void swelling. Ferritic alloys showed better resistance to loop formation, void swelling and irradiation-induced precipitation. From the degree of irradiation-induced microstructural change, alloy T92 was identified as the most radiation resistant among these alloys.",

keywords = "Microstructure, Nickel-base alloy, Precipitate, Radiation damage, Structure material",

author = "Miao Song and Lear, {Calvin R.} and Parish, {Chad M.} and Mi Wang and Was, {Gary S.}",

note = "Publisher Copyright: {\textcopyright} 2018 Elsevier B.V.",

year = "2018",

month = nov,

doi = "10.1016/j.jnucmat.2018.08.035",

language = "English",

volume = "510",

pages = "396--413",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

}

TY - JOUR

T1 - Radiation tolerance of commercial and advanced alloys for core internals

T2 - a comprehensive microstructural characterization

AU - Song, Miao

AU - Lear, Calvin R.

AU - Parish, Chad M.

AU - Wang, Mi

AU - Was, Gary S.

PY - 2018/11

Y1 - 2018/11

N2 - Thirteen austenitic stainless steels, nickel-base alloys, and ferritic alloys were irradiated using 2 MeV protons at 360 °C to a damage level of 2.5 displacements per atom (dpa). Comprehensive microstructural characterization was performed for irradiation-induced features, including dislocation loops, voids, precipitates, and radiation induced segregation (RIS). Dislocation loops formed in all alloys except 14YWT, while voids were observed in alloys 316 L, 310, C22, and 14YWT. Irradiation-induced formation of γ′ precipitates was observed in alloys 316 L, 310, 800, and 690; the irradiation-enhanced, long-range ordered Ni2Cr phase (Pt2Mo-type) was observed in alloys 690, C22, 625, 625Plus, 625DA, and 725; and G-phase was observed in alloy T92. No irradiation-induced precipitates were observed in alloys X750, 718 or 14YWT. Precipitation of the γ′ phase can be understood through segregation and clustering of Si, Al, and Ti. Overall, austenitic stainless steels are generally susceptible to irradiation damage in the form of loops, voids, precipitates, and RIS. Ni-base alloys have this same type of dislocation loops and RIS behaviors but are more resistant to void swelling. Ferritic alloys showed better resistance to loop formation, void swelling and irradiation-induced precipitation. From the degree of irradiation-induced microstructural change, alloy T92 was identified as the most radiation resistant among these alloys.

AB - Thirteen austenitic stainless steels, nickel-base alloys, and ferritic alloys were irradiated using 2 MeV protons at 360 °C to a damage level of 2.5 displacements per atom (dpa). Comprehensive microstructural characterization was performed for irradiation-induced features, including dislocation loops, voids, precipitates, and radiation induced segregation (RIS). Dislocation loops formed in all alloys except 14YWT, while voids were observed in alloys 316 L, 310, C22, and 14YWT. Irradiation-induced formation of γ′ precipitates was observed in alloys 316 L, 310, 800, and 690; the irradiation-enhanced, long-range ordered Ni2Cr phase (Pt2Mo-type) was observed in alloys 690, C22, 625, 625Plus, 625DA, and 725; and G-phase was observed in alloy T92. No irradiation-induced precipitates were observed in alloys X750, 718 or 14YWT. Precipitation of the γ′ phase can be understood through segregation and clustering of Si, Al, and Ti. Overall, austenitic stainless steels are generally susceptible to irradiation damage in the form of loops, voids, precipitates, and RIS. Ni-base alloys have this same type of dislocation loops and RIS behaviors but are more resistant to void swelling. Ferritic alloys showed better resistance to loop formation, void swelling and irradiation-induced precipitation. From the degree of irradiation-induced microstructural change, alloy T92 was identified as the most radiation resistant among these alloys.

KW - Microstructure

KW - Nickel-base alloy

KW - Precipitate

KW - Radiation damage

KW - Structure material

UR - http://www.scopus.com/inward/record.url?scp=85051983530&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2018.08.035

DO - 10.1016/j.jnucmat.2018.08.035

M3 - Article

AN - SCOPUS:85051983530

SN - 0022-3115

VL - 510

SP - 396

EP - 413

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization

Abstract

Funding

Keywords

Access to Document

Other files and links

Fingerprint

Cite this