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Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation

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Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation. / Degueldre, Claude; Fahy, James ; Kolosov, Oleg Victor et al.
In: Journal of Materials Engineering and Performance, Vol. 27, No. 5, 05.2018, p. 2081-2088.

Research output: Contribution to Journal/MagazineJournal articlepeer-review

Harvard

Degueldre, C, Fahy, J, Kolosov, OV, Wilbraham, RJ, Döbeli, M, Renevier, N, Ball, J & Ritter, S 2018, 'Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation', Journal of Materials Engineering and Performance, vol. 27, no. 5, pp. 2081-2088. https://doi.org/10.1007/s11665-018-3323-9

APA

Degueldre, C., Fahy, J., Kolosov, O. V., Wilbraham, R. J., Döbeli, M., Renevier, N., Ball, J., & Ritter, S. (2018). Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation. Journal of Materials Engineering and Performance, 27(5), 2081-2088. https://doi.org/10.1007/s11665-018-3323-9

Vancouver

Degueldre C, Fahy J, Kolosov OV, Wilbraham RJ, Döbeli M, Renevier N et al. Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation. Journal of Materials Engineering and Performance. 2018 May;27(5):2081-2088. Epub 2018 Apr 9. doi: 10.1007/s11665-018-3323-9

Author

Degueldre, Claude ; Fahy, James ; Kolosov, Oleg Victor et al. / Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation. In: Journal of Materials Engineering and Performance. 2018 ; Vol. 27, No. 5. pp. 2081-2088.

Bibtex

@article{32cb4c431101454f8b4dd6d8c6c38892,
title = "Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation",
abstract = "The production of helium bubbles in advanced gas-cooled reactor (AGR) cladding could represent a significant hazard for both the mechanical stability and long-term storage of such materials. However, the high radioactivity of AGR cladding after operation presents a significant barrier to the scientific study of the mechanical properties of helium incorporation, said cladding typically being analyzed in industrial hot cells. An alternative non-active approach is to implant He2+ into unused AGR cladding material via an accelerator. Here, a feasibility study of such a process, using sequential implantations of helium in AGR cladding steel with decreasing energy is carried out to mimic the buildup of He (e.g., 50 appm) that would occur for in-reactor AGR clad in layers of the order of 10 µm in depth, is described. The implanted sample is subsequently analyzed by scanning electron microscopy, nanoindentation, atomic force and ultrasonic force microscopies. As expected, the irradiated zones were affected by implantation damage (< 1 dpa). Nonetheless, such zones undergo only nanoscopic swelling and a small hardness increase (~ 10%), with no appreciable decrease in fracture strength. Thus, for this fluence and applied conditions, the integrity of the steel cladding is retained despite He2+ implantation.",
keywords = "atomic force microscopy, hardness, helium implantation, nanoindentation , stainless steel ",
author = "Claude Degueldre and James Fahy and Kolosov, {Oleg Victor} and Wilbraham, {Richard James} and Max D{\"o}beli and Nathalie Renevier and Jonathan Ball and Stefan Ritter",
year = "2018",
month = may,
doi = "10.1007/s11665-018-3323-9",
language = "English",
volume = "27",
pages = "2081--2088",
journal = "Journal of Materials Engineering and Performance",
issn = "1059-9495",
publisher = "Springer New York",
number = "5",

}

RIS

TY - JOUR

T1 - Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation

AU - Degueldre, Claude

AU - Fahy, James

AU - Kolosov, Oleg Victor

AU - Wilbraham, Richard James

AU - Döbeli, Max

AU - Renevier, Nathalie

AU - Ball, Jonathan

AU - Ritter, Stefan

PY - 2018/5

Y1 - 2018/5

N2 - The production of helium bubbles in advanced gas-cooled reactor (AGR) cladding could represent a significant hazard for both the mechanical stability and long-term storage of such materials. However, the high radioactivity of AGR cladding after operation presents a significant barrier to the scientific study of the mechanical properties of helium incorporation, said cladding typically being analyzed in industrial hot cells. An alternative non-active approach is to implant He2+ into unused AGR cladding material via an accelerator. Here, a feasibility study of such a process, using sequential implantations of helium in AGR cladding steel with decreasing energy is carried out to mimic the buildup of He (e.g., 50 appm) that would occur for in-reactor AGR clad in layers of the order of 10 µm in depth, is described. The implanted sample is subsequently analyzed by scanning electron microscopy, nanoindentation, atomic force and ultrasonic force microscopies. As expected, the irradiated zones were affected by implantation damage (< 1 dpa). Nonetheless, such zones undergo only nanoscopic swelling and a small hardness increase (~ 10%), with no appreciable decrease in fracture strength. Thus, for this fluence and applied conditions, the integrity of the steel cladding is retained despite He2+ implantation.

AB - The production of helium bubbles in advanced gas-cooled reactor (AGR) cladding could represent a significant hazard for both the mechanical stability and long-term storage of such materials. However, the high radioactivity of AGR cladding after operation presents a significant barrier to the scientific study of the mechanical properties of helium incorporation, said cladding typically being analyzed in industrial hot cells. An alternative non-active approach is to implant He2+ into unused AGR cladding material via an accelerator. Here, a feasibility study of such a process, using sequential implantations of helium in AGR cladding steel with decreasing energy is carried out to mimic the buildup of He (e.g., 50 appm) that would occur for in-reactor AGR clad in layers of the order of 10 µm in depth, is described. The implanted sample is subsequently analyzed by scanning electron microscopy, nanoindentation, atomic force and ultrasonic force microscopies. As expected, the irradiated zones were affected by implantation damage (< 1 dpa). Nonetheless, such zones undergo only nanoscopic swelling and a small hardness increase (~ 10%), with no appreciable decrease in fracture strength. Thus, for this fluence and applied conditions, the integrity of the steel cladding is retained despite He2+ implantation.

KW - atomic force microscopy

KW - hardness

KW - helium implantation

KW - nanoindentation

KW - stainless steel

U2 - 10.1007/s11665-018-3323-9

DO - 10.1007/s11665-018-3323-9

M3 - Journal article

VL - 27

SP - 2081

EP - 2088

JO - Journal of Materials Engineering and Performance

JF - Journal of Materials Engineering and Performance

SN - 1059-9495

IS - 5

ER -