Deformation mechanisms of zirconium alloys after irradiation studied by dislocation dynamics simulations and in situ straining experiments in TEM

Autor: Fabien Onimus, Laurent Dupuy, Frédéric Mompiou, Marine Gaumé, Wassim Kassem

Publikováno v: Zirconium in the Nuclear Industry: 19th International Symposium
Zirconium in the Nuclear Industry: 19th International Symposium, ASTM STP 1622, ASTM International, 24 p., 2021, 13: 978-0-8031-7690-4. ⟨10.1520/STP162220190036⟩
Zirconium in the Nuclear Industry: 19th International Symposium, ASTM International, pp.319-342, 2021, ⟨10.1520/STP162220190036⟩

Symposium held in Manchester, United Kingdom; International audience; Zirconium alloys, used in the nuclear industry, are subjected to neutron irradiation that affects their mechanical properties. At the microscopic scale, neutron irradiation creates

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d7a879d3506ca8854f90468dbc74472c
https://hal.science/hal-03380264/file/ArticleASTM2019_Onimus17jan20_short.pdf

A novel displacement cascade driven irradiation creep mechanism in α-zirconium: A molecular dynamics study

Autor: Fabien Onimus, Nargisse Khiara, Yves Bréchet, Jean-Pierre Raskin, Jean-Paul Crocombette, Wassim Kassem, Laurent Dupuy, Thomas Pardoen

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2020, 541, pp.152336-. ⟨10.1016/j.jnucmat.2020.152336⟩
Journal of Nuclear Materials, Vol. 541, p. 152336 (2020)
Journal of Nuclear Materials, 2020, 541, pp.152336. ⟨10.1016/j.jnucmat.2020.152336⟩

Zirconium alloys used in nuclear reactors undergo irradiation creep, which consists of a visco-plastic deformation activated by irradiation occurring under constant load. However, the fundamental underlying mechanisms have not been unraveled yet. A n

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a770b85671cfe3a1f2b65d8876f54d49
https://hal.archives-ouvertes.fr/hal-03491637

Creep behavior of submicron copper films under irradiation

Autor: Fabien Onimus, Jean-Pierre Raskin, Pierre Lapouge, Thomas Pardoen, Michaël Coulombier, Yves Bréchet

Publikováno v: Acta Materialia
Acta Materialia, Elsevier, 2017, 131, pp.77-87. ⟨10.1016/j.actamat.2017.03.056⟩
Acta Materialia, 2017, 131, pp.77-87. ⟨10.1016/j.actamat.2017.03.056⟩
Acta Materialia, Vol. 131, p. 77-87 (2017)

The creep behavior under heavy ion irradiation of 200 nm and 500 nm thick annealed Cu films is characterized using on chip uniaxial microtensile test structures. The tests are performed at room temperature with an applied stress between 100 and 250 M

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b5d58d430967c1ed348e74265fd59c5e
https://doi.org/10.1016/j.actamat.2017.03.056

Glide and cross-slip of a -dislocations in Zr and Ti

Autor: M. Gaumé, D. Caillard, Fabien Onimus

Publikováno v: Acta Materialia
Acta Materialia, 2018, 155, pp.23-34. ⟨10.1016/j.actamat.2018.05.038⟩
Acta Materialia, Elsevier, 2018, 155, pp.23-34. 〈10.1016/j.actamat.2018.05.038〉
Acta Materialia, Elsevier, 2018, 155, pp.23-34. ⟨10.1016/j.actamat.2018.05.038⟩

International audience; Slip systems involving dislocations with Burgers vectors have been studied in hexagonal close packed Zr and Ti, by means of in situ straining experiments in a transmission electron microscope, at various temperatures and as a

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fe1faa5e5659c51e881004d44cd0adc7
https://hal.science/hal-01814959

Strain-Path Change Tests and Physically Based Polycrystalline Modeling of the Behavior of Recrystallized Zirconium Alloys

Autor: J. Garnier, Fabien Onimus, Matthew Bono, Florent Bourlier, D. Gilbon, Antoine Ambard, Annie Soniak-Defresne, Roger Limon

Publikováno v: Zirconium in the Nuclear Industry: 18th International Symposium
Zirconium in the Nuclear Industry: 18th International Symposium, ASTM STP (1597), ASTM International, pp.180-213, 2018, ⟨10.1520/STP159720160092⟩

International audience; Zirconium alloys used as cladding tubes for the fuel of Pressurized Water Reactors can undergo high applied stress during power transients. In these conditions, biaxial loading may lead to plastic deformation of the cladding.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::72893c1fc2f31da46e7bd435a187cf97
https://doi.org/10.1520/stp159720160092