Post-irradiation plastic deformation in bcc Fe grains investigated by means of 3D dislocation dynamics simulations

被引:18
作者
Gururaj, K. [1 ]
Robertson, C. [2 ]
Fivel, M. [3 ]
机构
[1] Indira Gandhi Ctr Atom Res, Mat Sci Grp, Kalpakkam 603102, Tamil Nadu, India
[2] CEA, DEN, SRMA, F-91191 Gif Sur Yvette, France
[3] UJF, CNRS, Grenoble INP, SIMaP GPM2, F-38402 St Martin Dheres, France
关键词
LOCALIZED DEFORMATION; MECHANICAL-PROPERTIES; FCC; MICROSTRUCTURE; METALS; STEELS; DAMAGE; LOOPS; IRON;
D O I
10.1016/j.jnucmat.2015.01.031
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Post-irradiation tensile straining is investigated by means of three-dimensional dislocation dynamics simulations adapted to body centred cubic Fe. Namely, 1 gm Fe grains are strained at various temperatures in the 100-300 K range, in absence and in presence of radiation-induced defect dispersions. The defect-induced hardening is consistent with the disperse barrier effect up to 5 x 10(21) m(-3) loops and is weakly dependent on the straining temperature. The dislocation-loops interaction rate augments with the accumulated plastic strain, loop density and strength; while it is mainly independent of the number of active slip systems and thermally activated screw dislocation mobility. An additional, radiation-induced hardening mechanism known as dislocation "decoration" is also implemented and tested for comparison. Those results show that the plastic flow localisation transition depends on the total yield point rise rather than on the lone, dispersed loop density. The simulation results are then rationalized through an original micro-mechanical model relating the grain-scale stress-strain behaviour to dislocation sub-structure formation and spreading. That model combines strain dependent and strain independent hardening mechanisms, which both contribute to the associated stress-strain response and plastic flow spreading. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:194 / 204
页数:11
相关论文
共 52 条
[1]   A dislocation dynamics study of the transition from homogeneous to heterogeneous deformation in irradiated body-centered cubic iron [J].
Arsenlis, A. ;
Rhee, M. ;
Hommes, G. ;
Cook, R. ;
Marian, J. .
ACTA MATERIALIA, 2012, 60 (09) :3748-3757
[2]   EFFECT OF DISLOCATION SELF-INTERACTION ON OROWAN STRESS [J].
BACON, DJ ;
KOCKS, UF ;
SCATTERGOOD, RO .
PHILOSOPHICAL MAGAZINE, 1973, 28 (06) :1241-1263
[3]   Status of reduced activation ferritic/martensitic steel development [J].
Baluc, N. ;
Gelles, D. S. ;
Jitsukawa, S. ;
Kimura, A. ;
Klueh, R. L. ;
Odette, G. R. ;
van der Schaaf, B. ;
Yu, Jinnan .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) :33-41
[4]  
Byun T., 2006, Nuclear Engineering and technology, V38, P619
[5]   Strain hardening and long-range internal stress in the localized deformation of irradiated polycrystalline metals [J].
Byun, Thak Sang ;
Hashimoto, Naoyuki .
JOURNAL OF NUCLEAR MATERIALS, 2006, 354 (1-3) :123-130
[6]  
Caillard D., 2003, Thermally Activated Mechanisms in Crystal Plasticity, V8
[7]   The glide of screw dislocations in bcc Fe: Atomistic static and dynamic simulations [J].
Chaussidon, Julien ;
Fivel, Marc ;
Rodney, David .
ACTA MATERIALIA, 2006, 54 (13) :3407-3416
[8]   Internal stress evolution in Fe laths deformed at low temperature analysed by dislocation dynamics simulations [J].
Chaussidon, Julien ;
Robertson, Christian ;
Fivel, Marc ;
Marini, Bernard .
MODELLING AND SIMULATION IN MATERIALS SCIENCE AND ENGINEERING, 2010, 18 (02)
[9]   Dislocation dynamics simulations of plasticity in Fe laths at low temperature [J].
Chaussidon, Julien ;
Robertson, Christian ;
Rodney, David ;
Fivel, Marc .
ACTA MATERIALIA, 2008, 56 (19) :5466-5476
[10]   The mechanical properties of 590 MeV proton irradiated iron [J].
Chen, Y ;
Spätig, P ;
Victoria, M .
JOURNAL OF NUCLEAR MATERIALS, 1999, 271 :128-132