TY - JOUR
T1 - A novel displacement cascade driven irradiation creep mechanism in α-zirconium
T2 - a molecular dynamics study
AU - Khiara, Nargisse
AU - Onimus, Fabien
AU - Dupuy, Laurent
AU - Kassem, Wassim
AU - Crocombette, Jean-Paul
AU - Pardoen, Thomas
AU - Raskin, Jean-Pierre
AU - Bréchet, Yves
PY - 2020/12/1
Y1 - 2020/12/1
N2 - 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 new high-stress irradiation creep mechanism for recrystallized Zircaloy-4 has recently been proposed based on in situ ion irradiation deformation experiments. A displacement cascade is assumed to induce a direct unpinning of a dislocation from an irradiation defect if the cascade occurs within an effective volume around the pinning point. In the present work, a systematic molecular dynamics study was performed to investigate the effect of a 20 keV cascade occurring near -screw dislocation pinned on an interstitial -loop. The direct release of dislocations by displacement cascades is predicted by the simulations. This release is more likely around the pinning points and with increasing stress, in agreement with experimental observations. The effective volume is roughly estimated for three stress levels equal to 0.89τc, 0.93τc and 0.97τc, with τc being the critical stress for unpinning (without irradiation). A mechanism is proposed suggesting that unpinning occurs when the displacement cascade encompasses, at its peak of damage, the two pinning points of the dislocation. A methodology requiring acceptable computation time has been implemented to estimate the effective volume for various cascade energies and loop characteristics, faithfully reproducing the MD results. The mean pinning lifetime calculated using the model provides values of the same order of magnitudes as in the in situ deformation experiments under ion irradiation at high stress levels.
AB - 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 new high-stress irradiation creep mechanism for recrystallized Zircaloy-4 has recently been proposed based on in situ ion irradiation deformation experiments. A displacement cascade is assumed to induce a direct unpinning of a dislocation from an irradiation defect if the cascade occurs within an effective volume around the pinning point. In the present work, a systematic molecular dynamics study was performed to investigate the effect of a 20 keV cascade occurring near -screw dislocation pinned on an interstitial -loop. The direct release of dislocations by displacement cascades is predicted by the simulations. This release is more likely around the pinning points and with increasing stress, in agreement with experimental observations. The effective volume is roughly estimated for three stress levels equal to 0.89τc, 0.93τc and 0.97τc, with τc being the critical stress for unpinning (without irradiation). A mechanism is proposed suggesting that unpinning occurs when the displacement cascade encompasses, at its peak of damage, the two pinning points of the dislocation. A methodology requiring acceptable computation time has been implemented to estimate the effective volume for various cascade energies and loop characteristics, faithfully reproducing the MD results. The mean pinning lifetime calculated using the model provides values of the same order of magnitudes as in the in situ deformation experiments under ion irradiation at high stress levels.
KW - Creep
KW - Irradiation
KW - Molecular dynamics
KW - Zirconium
UR - http://www.scopus.com/inward/record.url?scp=85089413825&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2020.152336
DO - 10.1016/j.jnucmat.2020.152336
M3 - Article
AN - SCOPUS:85089413825
SN - 0022-3115
VL - 541
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 152336
ER -