Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation

C. Barcellini; R. W. Harrison; S. Dumbill; S. E. Donnelly; E. Jimenez-Melero

doi:10.1016/j.jnucmat.2018.11.019

Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation

C. Barcellini^*
, R. W. Harrison
, S. Dumbill
, S. E. Donnelly
, E. Jimenez-Melero

^*Corresponding author for this work

Metallurgy and Materials

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

Abstract

We have monitored in situ the lattice defect evolution induced by proton irradiation in 20Cr-25Ni Nb-stabilised stainless steel, used as fuel cladding material in advanced gas-cooled reactors. At 420 °C, the damaged microstructure is mainly characterised by black spots and faulted [Formula presented]〈111〉 Frank loops. Defect saturation is reached at only 0.1dpa. In contrast, at 460 °C and 500 °C proton bombardment induces the formation of a mixture of [Formula presented]〈111〉 Frank loops and perfect [Formula presented]〈110〉 loops. These perfect loops evolve into dislocation lines that form a dense network. This transition coincides with the saturation in the dislocation loop size and number density at 0.8dpa (460 °C) and 0.2dpa (500 °C), respectively. The presence of a high density of dislocation loops and lines at those two temperatures causes a vacancy supersaturation in the matrix, leading to the formation of voids and stacking fault tetrahedra.

Original language	English
Pages (from-to)	90-100
Number of pages	11
Journal	Journal of Nuclear Materials
Volume	514
DOIs	https://doi.org/10.1016/j.jnucmat.2018.11.019
Publication status	Published - Feb 2019

Bibliographical note

Funding Information:
We acknowledge the Engineering and Physical Sciences Research Council for providing funding for this project through the DISTINCTIVE grant ( EP/L014041/1 ), and also for the development of the MIAMI-2 Facility ( EP/M028283/1 ) and access via the UK National Ion Beam Centre . We would also like to thank Dr. S. Walters from the National Nuclear Laboratory for providing the starting material.

Publisher Copyright:
© 2018 Elsevier B.V.

Keywords

Advanced gas-cooled reactor
Austenitic stainless steel
Dislocation analysis
In-situ proton irradiation
Transmission electron microscopy

ASJC Scopus subject areas

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

Access to Document

10.1016/j.jnucmat.2018.11.019

Cite this

@article{e33325d08d0e4d79a49a7eec7cc392f0,

title = "Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation",

abstract = "We have monitored in situ the lattice defect evolution induced by proton irradiation in 20Cr-25Ni Nb-stabilised stainless steel, used as fuel cladding material in advanced gas-cooled reactors. At 420 °C, the damaged microstructure is mainly characterised by black spots and faulted [Formula presented]〈111〉 Frank loops. Defect saturation is reached at only 0.1dpa. In contrast, at 460 °C and 500 °C proton bombardment induces the formation of a mixture of [Formula presented]〈111〉 Frank loops and perfect [Formula presented]〈110〉 loops. These perfect loops evolve into dislocation lines that form a dense network. This transition coincides with the saturation in the dislocation loop size and number density at 0.8dpa (460 °C) and 0.2dpa (500 °C), respectively. The presence of a high density of dislocation loops and lines at those two temperatures causes a vacancy supersaturation in the matrix, leading to the formation of voids and stacking fault tetrahedra.",

keywords = "Advanced gas-cooled reactor, Austenitic stainless steel, Dislocation analysis, In-situ proton irradiation, Transmission electron microscopy",

author = "C. Barcellini and Harrison, \{R. W.\} and S. Dumbill and Donnelly, \{S. E.\} and E. Jimenez-Melero",

note = "Funding Information: We acknowledge the Engineering and Physical Sciences Research Council for providing funding for this project through the DISTINCTIVE grant ( EP/L014041/1 ), and also for the development of the MIAMI-2 Facility ( EP/M028283/1 ) and access via the UK National Ion Beam Centre . We would also like to thank Dr. S. Walters from the National Nuclear Laboratory for providing the starting material. Publisher Copyright: {\textcopyright} 2018 Elsevier B.V.",

year = "2019",

month = feb,

doi = "10.1016/j.jnucmat.2018.11.019",

language = "English",

volume = "514",

pages = "90--100",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

}

TY - JOUR

T1 - Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation

AU - Barcellini, C.

AU - Harrison, R. W.

AU - Dumbill, S.

AU - Donnelly, S. E.

AU - Jimenez-Melero, E.

N1 - Funding Information: We acknowledge the Engineering and Physical Sciences Research Council for providing funding for this project through the DISTINCTIVE grant ( EP/L014041/1 ), and also for the development of the MIAMI-2 Facility ( EP/M028283/1 ) and access via the UK National Ion Beam Centre . We would also like to thank Dr. S. Walters from the National Nuclear Laboratory for providing the starting material. Publisher Copyright: © 2018 Elsevier B.V.

PY - 2019/2

Y1 - 2019/2

N2 - We have monitored in situ the lattice defect evolution induced by proton irradiation in 20Cr-25Ni Nb-stabilised stainless steel, used as fuel cladding material in advanced gas-cooled reactors. At 420 °C, the damaged microstructure is mainly characterised by black spots and faulted [Formula presented]〈111〉 Frank loops. Defect saturation is reached at only 0.1dpa. In contrast, at 460 °C and 500 °C proton bombardment induces the formation of a mixture of [Formula presented]〈111〉 Frank loops and perfect [Formula presented]〈110〉 loops. These perfect loops evolve into dislocation lines that form a dense network. This transition coincides with the saturation in the dislocation loop size and number density at 0.8dpa (460 °C) and 0.2dpa (500 °C), respectively. The presence of a high density of dislocation loops and lines at those two temperatures causes a vacancy supersaturation in the matrix, leading to the formation of voids and stacking fault tetrahedra.

AB - We have monitored in situ the lattice defect evolution induced by proton irradiation in 20Cr-25Ni Nb-stabilised stainless steel, used as fuel cladding material in advanced gas-cooled reactors. At 420 °C, the damaged microstructure is mainly characterised by black spots and faulted [Formula presented]〈111〉 Frank loops. Defect saturation is reached at only 0.1dpa. In contrast, at 460 °C and 500 °C proton bombardment induces the formation of a mixture of [Formula presented]〈111〉 Frank loops and perfect [Formula presented]〈110〉 loops. These perfect loops evolve into dislocation lines that form a dense network. This transition coincides with the saturation in the dislocation loop size and number density at 0.8dpa (460 °C) and 0.2dpa (500 °C), respectively. The presence of a high density of dislocation loops and lines at those two temperatures causes a vacancy supersaturation in the matrix, leading to the formation of voids and stacking fault tetrahedra.

KW - Advanced gas-cooled reactor

KW - Austenitic stainless steel

KW - Dislocation analysis

KW - In-situ proton irradiation

KW - Transmission electron microscopy

UR - https://www.scopus.com/pages/publications/85056863224

U2 - 10.1016/j.jnucmat.2018.11.019

DO - 10.1016/j.jnucmat.2018.11.019

M3 - Article

AN - SCOPUS:85056863224

SN - 0022-3115

VL - 514

SP - 90

EP - 100

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation

Abstract

Bibliographical note

Keywords

ASJC Scopus subject areas

Access to Document

Fingerprint

Cite this