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

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Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation. / Barcellini, Chiara; Harrison, Robert; Dumbill, S; Donnelly, S. E.; Jimenez-Melero, Enrique.

In: Journal of Nuclear Materials, Vol. 514, 01.02.2019, p. 90-100.

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Barcellini, Chiara ; Harrison, Robert ; Dumbill, S ; Donnelly, S. E. ; Jimenez-Melero, Enrique. / Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation. In: Journal of Nuclear Materials. 2019 ; Vol. 514. pp. 90-100.

Bibtex

@article{9f7de291a66a41f8a3407d901aa87b53,
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 a_0/3 111 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 a_0/3 111 Frank loops andperfect a_0/2 110 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 = "Austenitic stainless steel, in-situ proton irradiation, dislocation analysis, Transmission electron microscopy, advanced gas-cooled reactor",
author = "Chiara Barcellini and Robert Harrison and S Dumbill and Donnelly, {S. E.} and Enrique Jimenez-Melero",
year = "2019",
month = feb,
day = "1",
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 BV",

}

RIS

TY - JOUR

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

AU - Barcellini, Chiara

AU - Harrison, Robert

AU - Dumbill, S

AU - Donnelly, S. E.

AU - Jimenez-Melero, Enrique

PY - 2019/2/1

Y1 - 2019/2/1

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 a_0/3 111 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 a_0/3 111 Frank loops andperfect a_0/2 110 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 a_0/3 111 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 a_0/3 111 Frank loops andperfect a_0/2 110 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 - Austenitic stainless steel

KW - in-situ proton irradiation

KW - dislocation analysis

KW - Transmission electron microscopy

KW - advanced gas-cooled reactor

U2 - 10.1016/j.jnucmat.2018.11.019

DO - 10.1016/j.jnucmat.2018.11.019

M3 - Article

VL - 514

SP - 90

EP - 100

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -