Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel

Zheng, Ce; Auger, Maria A.; Moody, Michael P.; Kaoumi, Djamel

doi:10.1016/j.jnucmat.2017.04.040

Title: Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel

Abstract

In this study, Ferritic/Martensitic (F/M) HT9 steel was irradiated to 20 displacements per atom (dpa) at 600 nm depth at 420 and 440 °C, and to 1, 10 and 20 dpa at 600 nm depth at 470 °C using 5 MeV Fe++ ions. The characterization was conducted using ChemiSTEM and Atom Probe Tomography (APT), with a focus on radiation induced segregation and precipitation. Ni and/or Si segregation at defect sinks (grain boundaries, dislocation lines, carbide/matrix interfaces) together with Ni, Si, Mn rich G-phase precipitation were observed in self-ion irradiated HT9 except in very low dose case (1 dpa at 470 °C). Some G-phase precipitates were found to nucleate heterogeneously at defect sinks where Ni and/or Si segregated. In contrast to what was previously reported in the literature for neutron irradiated HT9, no Cr-rich α' phase, χ-phases, η phase and voids were found in self-ion irradiated HT9. The difference of observed microstructures is probably due to the difference of irradiation dose rate between ion irradiation and neutron irradiation. In addition, the average size and number density of G-phase precipitates were found to be sensitive to both irradiation temperature and dose. With the same irradiation dose, the average size of G-phase increasedmore »« less

Authors:

; Auger, Maria A.; Moody, Michael P.; Kaoumi, Djamel

Publication Date:: Tue Aug 01 00:00:00 EDT 2017

Research Org.:: Univ. of Michigan, Ann Arbor, MI (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1353271

Alternate Identifier(s):: OSTI ID: 1426234

Grant/Contract Number:: NE0000639

Resource Type:: Published Article

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Name: Journal of Nuclear Materials Journal Volume: 491 Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Subject:: 36 MATERIALS SCIENCE; F/M steel, HT9, Ion irradiation, Radiation-induced segregation & precipitation, G-phase, ChemiSTEM, APT

Citation Formats


                    Zheng, Ce, Auger, Maria A., Moody, Michael P., and Kaoumi, Djamel. Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel.  Netherlands: N. p., 2017. 
Web.  doi:10.1016/j.jnucmat.2017.04.040.

Copy to clipboard


                    Zheng, Ce, Auger, Maria A., Moody, Michael P., & Kaoumi, Djamel. Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel.  Netherlands.  https://doi.org/10.1016/j.jnucmat.2017.04.040

Copy to clipboard


                    Zheng, Ce, Auger, Maria A., Moody, Michael P., and Kaoumi, Djamel. Tue .  
"Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel".  Netherlands.  https://doi.org/10.1016/j.jnucmat.2017.04.040.

Copy to clipboard


                    
@article{osti_1353271,

  title        = {Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel},

  author       = {Zheng, Ce and Auger, Maria A. and Moody, Michael P. and Kaoumi, Djamel},

  abstractNote = {In this study, Ferritic/Martensitic (F/M) HT9 steel was irradiated to 20 displacements per atom (dpa) at 600 nm depth at 420 and 440 °C, and to 1, 10 and 20 dpa at 600 nm depth at 470 °C using 5 MeV Fe++ ions. The characterization was conducted using ChemiSTEM and Atom Probe Tomography (APT), with a focus on radiation induced segregation and precipitation. Ni and/or Si segregation at defect sinks (grain boundaries, dislocation lines, carbide/matrix interfaces) together with Ni, Si, Mn rich G-phase precipitation were observed in self-ion irradiated HT9 except in very low dose case (1 dpa at 470 °C). Some G-phase precipitates were found to nucleate heterogeneously at defect sinks where Ni and/or Si segregated. In contrast to what was previously reported in the literature for neutron irradiated HT9, no Cr-rich α' phase, χ-phases, η phase and voids were found in self-ion irradiated HT9. The difference of observed microstructures is probably due to the difference of irradiation dose rate between ion irradiation and neutron irradiation. In addition, the average size and number density of G-phase precipitates were found to be sensitive to both irradiation temperature and dose. With the same irradiation dose, the average size of G-phase increased whereas the number density decreased with increasing irradiation temperature. Within the same irradiation temperature, the average size increased with increasing irradiation dose.},

  doi          = {10.1016/j.jnucmat.2017.04.040},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 491,

  place        = {Netherlands},

  year         = {Tue Aug 01 00:00:00 EDT 2017},

  month        = {Tue Aug 01 00:00:00 EDT 2017}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Publisher's Version of Record
https://doi.org/10.1016/j.jnucmat.2017.04.040

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 30 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Works referencing / citing this record:

α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys
journal, June 2019

Aydogan, E.; Martinez, E.; March, K.
Scientific Reports, Vol. 9, Issue 1
DOI: 10.1038/s41598-019-44508-5

Similar Records in DOE PAGES and OSTI.GOV collections:

Radiation-induced swelling and radiation-induced segregation & precipitation in dual beam irradiated Ferritic/Martensitic HT9 steel

Journal Article Zheng, C. ; Kaoumi, D., E-mail: djamelkaoumi@gmail.com - Materials Characterization

Highlights: • The depth-dependence of radiation-induced cavities was characterized in self-ion irradiated HT9 co-implanted with He. • The injected interstitial effect was revealed to suppress cavity swelling in the vicinity of the damage peak. • ChemiSTEM elemental maps revealed the segregation of Ni at cavity surfaces and its possible synergistic influence on swelling was discussed. - Abstract: Ferritic/Martensitic HT9 steel was irradiated at 432 °C to 16.6 displacements per atom (dpa) (at the depth of 600 nm) using a defocused beam of 5 MeV Fe{sup ++} ions, while co-implanted with 3.22 appm He at the same depth. The helium concentrationmore »« less
https://doi.org/10.1016/J.MATCHAR.2017.10.019
Void swelling of conventional and composition engineered HT9 alloys after high-dose self-ion irradiation

Journal Article Kim, Hyosim ; Gigax, Jonathan Gregory ; Rietema, Connor J. ; ... - Journal of Nuclear Materials

Ferritic/martensitic (F/M) steels are being considered as potential structural materials for next generation nuclear reactors, and variants of the alloy HT9 are some of the most promising candidates. In this study, two conventional and two composition engineered HT9 alloys were irradiated using 3.5 MeV Fe²⁺ up to 600 peak displacement-per-atom (dpa) at 450 °C. Void swelling and microstructure evolution were characterized for each alloy and compared. The two conventional HT9 alloys (INL and ACO3) showed similar void swelling behavior due to their similar elemental composition and processing conditions. The INL HT9 exhibited a maximum of 2.4% swelling and the ACO3more »« less
https://doi.org/10.1016/j.jnucmat.2021.153492

Full Text Available
Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys

Technical Report Stubbins, James ; Heuser, Brent ; Hosemann, Peter ; ...

This final technical report summarizes the research performed during October 2014 and December 2017, with a focus on investigating the radiation-induced microstructural and mechanical property modifications in optimized advanced alloys for sodium-cooled fast reactor (SFR) structural applications. To accomplish these objectives, the radiation responses of several different advanced alloys, including austenitic steel Alloy 709 (A709) and 316H, and ferritic/ martensitic Fe–9Cr steels T91 and G92, were investigated using a combination of microstructure characterizations and nanoindentation measurements. Different types of irradiation, including ex situ bulk ion irradiation and in situ transmission electron microscopy (TEM) ion irradiation, were employed in this study.more »« less
https://doi.org/10.2172/1434640

Full Text Available
Microchemical evolution of irradiated additive-manufactured HT9

Journal Article Xiu, Pengyuan ; Massey, Caleb ; Green, Theresa Mary Kelsy ; ... - Journal of Nuclear Materials

The microstructural responses under 5 MeV Fe2⁺ single-ion-beam irradiation of three conditions of additive-manufactured (AM) HT9 steel using a powder-based directed energy deposition (DED) technique with and without postbuild heat treatments were investigated. Besides the observed dislocation loop formation and the absence of cavities at the irradiation condition of 50 dpa at 460 °C, Ni/Si/Mn-rich precipitates are found to form in all three conditions of AM-HT9, whereas Cu-rich clusters that arise from Cu uptake from the DED process are only observed in the heat-treated conditions, and not in the as-built (ASB) condition. Coprecipitation of the Cu- and Ni/Si/Mn-rich clusters occurmore »« less
https://doi.org/10.1016/j.jnucmat.2021.153410

Full Text Available
Aging and Embrittlement of High Fluence Stainless Steels

Technical Report Was, gary ; Jiao, Zhijie ; der ven, Anton Van ; ...

Irradiation of austenitic stainless steels results in the formation of dislocation loops, stacking fault tetrahedral, Ni-Si clusters and radiation-induced segregation (RIS). Of these features, it is the formation of precipitates which is most likely to impact the mechanical integrity at high dose. Unlike dislocation loops and RIS, precipitates exhibit an incubation period that can extend from 10 to 46 dpa, above which the cluster composition changes and a separate phase, (G-phase) forms. Both neutron and heavy ion irradiation showed that these clusters develop slowly and continue to evolve beyond 100 dpa. Overall, this work shows that the irradiated microstructure featuresmore »« less
https://doi.org/10.2172/1060508

Full Text Available

Similar Records

Title: Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel

Abstract

Citation Formats

α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys journal, June 2019

α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys
journal, June 2019