Modeling the long-term evolution of the primary damage in ferritic alloys using coarse-grained methods

被引:57
作者
Becquart, C. S. [1 ]
Barbu, A. [2 ]
Bocquet, J. L. [2 ]
Caturla, M. J. [3 ]
Domain, C. [4 ]
Fu, C-C. [2 ]
Golubov, S. I. [5 ,10 ]
Hou, M. [6 ]
Malerba, L. [7 ]
Ortiz, C. J. [3 ,8 ]
Souidi, A. [9 ]
Stoller, R. E. [10 ]
机构
[1] Univ Lille 1, UMR 8207, Unite Mat & Tech UMET, F-59655 Villeneuve Dascq, France
[2] CEA Saclay, Serv Rech Met Phys, F-91191 Gif Sur Yvette, France
[3] Univ Alicante, Dept Fis Aplicada, E-03690 Alicante, Spain
[4] EDF R&D, Dept MMC, F-77818 Les Renardieres, Moret Sur Loing, France
[5] Univ Tennessee, Ctr Mat Proc, Knoxville, TN 37996 USA
[6] Univ Libre Bruxelles, Phys Solides Irradies & Nanostruct CP234, B-1050 Brussels, Belgium
[7] CEN SCK, Nucl Mat Sci Inst, Struct Mat Grp, B-2400 Mol, Belgium
[8] CIEMAT, Lab Fus Confinamiento Magnet, E-28040 Madrid, Spain
[9] Ctr Univ Saida, Saida 20000, Algeria
[10] Oak Ridge Natl Lab, Mat Sci & Technol Div, Oak Ridge, TN 37831 USA
关键词
KINETIC MONTE-CARLO; NEUTRON-IRRADIATED IRON; HEAVY-ION IRRADIATION; DISPLACEMENT CASCADES; DISLOCATION LOOPS; INTERSTITIAL LOOPS; RADIATION-DAMAGE; DEFECT CLUSTERS; ALPHA-IRON; MICROSTRUCTURAL EVOLUTION;
D O I
10.1016/j.jnucmat.2010.05.019
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Knowledge of the long-term evolution of the microstructure after introduction of primary damage is an essential ingredient in understanding mechanical property changes that occur during irradiation. Within the European integrated project "PERFECT," different techniques have been developed or improved to model microstructure evolution of Fe alloys under irradiation. This review paper aims to present the current state of the art of these techniques, as developed in the project, as well as the main results obtained. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:39 / 54
页数:16
相关论文
共 88 条
[1]   Simulation of damage production and accumulation in vanadium [J].
Alonso, E ;
Caturla, MJ ;
de la Rubia, TD ;
Perlado, JM .
JOURNAL OF NUCLEAR MATERIALS, 2000, 276 (276) :221-229
[2]   Observation of the one-dimensional diffusion of nanometer-sized dislocation loops [J].
Arakawa, K. ;
Ono, K. ;
Isshiki, M. ;
Mimura, K. ;
Uchikoshi, M. ;
Mori, H. .
SCIENCE, 2007, 318 (5852) :956-959
[3]   Influence of self-interstitial mobility on damage accumulation in zirconium under fission irradiation conditions [J].
Arevalo, C. ;
Caturla, M. J. ;
Perlado, J. M. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 362 (2-3) :293-299
[4]  
AREVALO C, 2007, THESIS U POLITECNICA
[5]   Identification of novel diffusion cycles in B2 ordered phases by Monte Carlo simulation [J].
Athenes, M ;
Bellon, P ;
Martin, G .
PHILOSOPHICAL MAGAZINE A-PHYSICS OF CONDENSED MATTER STRUCTURE DEFECTS AND MECHANICAL PROPERTIES, 1997, 76 (03) :565-585
[6]   Synthesis of atom probe experiments on irradiation-induced solute segregation in French ferritic pressure vessel steels [J].
Auger, P ;
Pareige, P ;
Welzel, S ;
Van Duysen, JC .
JOURNAL OF NUCLEAR MATERIALS, 2000, 280 (03) :331-344
[7]  
Barbu A, 2005, PHILOS MAG, V85, P541, DOI 10.1080/0267837041233134616
[8]   2005 TMS microstructural processes in irradiated materials symposium - Preface [J].
Becquart, C ;
Matsui, H ;
Snead, L ;
Wirth, BD .
JOURNAL OF NUCLEAR MATERIALS, 2006, 351 (1-3) :IX-IX
[9]   Modeling the long-term evolution of the primary damage in ferritic alloys using coarse-grained methods [J].
Becquart, C. S. ;
Barbu, A. ;
Bocquet, J. L. ;
Caturla, M. J. ;
Domain, C. ;
Fu, C-C. ;
Golubov, S. I. ;
Hou, M. ;
Malerba, L. ;
Ortiz, C. J. ;
Souidi, A. ;
Stoller, R. E. .
JOURNAL OF NUCLEAR MATERIALS, 2010, 406 (01) :39-54
[10]  
Becquart CS, 2002, PHYS REV B, V66, DOI 10.1103/PhysRevB.66.134104