Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses

被引:160
作者
Meslin, E. [1 ,2 ]
Lambrecht, M. [3 ]
Hernandez-Mayoral, M. [4 ]
Bergner, F. [5 ]
Malerba, L. [3 ]
Pareige, P. [2 ]
Radiguet, B. [2 ]
Barbu, A. [1 ]
Gomez-Briceno, D. [4 ]
Ulbricht, A. [5 ]
Almazouzi, A. [3 ]
机构
[1] CEA Saclay, Serv Rech Met Phys, F-91191 Gif Sur Yvette, France
[2] Univ Rouen, Equipe Rech Technol, UMR CNRS 6634, Grp Phys Mat, F-76801 St Etienne, France
[3] CEN SCK, Nucl Mat Sci Inst, B-2400 Mol, Belgium
[4] CIEMAT, Div Struct Mat, E-28040 Madrid, Spain
[5] Forschungszentrum Dresden Rossendorf, Inst Safety Res, D-01314 Dresden, Germany
关键词
RPV steels; Microstructure; Neutron irradiation; Radiation damage; APT; TEM; PAS; SANS; ATOM-PROBE; FE-CU; MICROSTRUCTURAL EVOLUTION; POSITRON-ANNIHILATION; COPPER PRECIPITATION; ALPHA-IRON; REACTOR; ELECTRON; SCATTERING; EMBRITTLEMENT;
D O I
10.1016/j.jnucmat.2009.12.021
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Understanding the behavior of reactor pressure vessel (RPV) steels under irradiation is a mandatory task that has to be elucidated in order to be able to operate safely a nuclear power plant or to extend its lifetime. To build up predictive tools, a substantial experimental data base is needed at the nanometre scale to extract quantitative information on neutron-irradiated materials and to validate the theoretical models. To reach this experimental goal, ferritic model alloys and French RPV steel were neutron irradiated in a test reactor at an irradiation flux of 9 x 10(17) nm(-2) s, doses from 0.18 to 1.3 x 10(24) nm(-2) and 300 degrees C. The main goal of this paper is to report the characterization of the radiation-induced microstructural change in the materials by using the state-of-the-art of characterization techniques available in Europe at the nanometre scale. Possibilities, limitations and complementarities of the techniques to each other are highlighted. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:73 / 83
页数:11
相关论文
共 56 条
[1]   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
[2]   Small-angle neutron scattering study of neutron-irradiated iron and an iron-nickel alloy [J].
Bergner, F. ;
Ulbricht, A. ;
Hernandez-Mayoral, M. ;
Pranzas, P. K. .
JOURNAL OF NUCLEAR MATERIALS, 2008, 374 (1-2) :334-337
[3]   Comparative small-angle neutron scattering study of neutron-irradiated Fe, Fe-based alloys and a pressure vessel steel [J].
Bergner, F. ;
Lambrecht, M. ;
Ulbricht, A. ;
Almazouzi, A. .
JOURNAL OF NUCLEAR MATERIALS, 2010, 399 (2-3) :129-136
[4]   Microstructural characterization of irradiation-induced Cu-enriched clusters in reactor pressure vessel steels [J].
Carter, RG ;
Soneda, N ;
Dohi, K ;
Hyde, JM ;
English, CA ;
Server, WL .
JOURNAL OF NUCLEAR MATERIALS, 2001, 298 (03) :211-224
[5]   Million-atom molecular dynamics simulations of magnetic iron [J].
Derlet, P. M. ;
Dudarev, S. L. .
PROGRESS IN MATERIALS SCIENCE, 2007, 52 (2-3) :299-318
[6]  
Ebrahimi F., 1988, NUREG/CR-5063
[7]  
MEA-2268
[8]  
EDINGTON JW, 1965, PRACTICAL ELECT MICR
[9]   Studies of defects and defect agglomerates by positron annihilation spectroscopy [J].
Eldrup, M ;
Singh, BN .
JOURNAL OF NUCLEAR MATERIALS, 1997, 251 :132-138
[10]   Dose dependence of defect accumulation in neutron irradiated copper and iron [J].
Eldrup, M ;
Singh, BN ;
Zinkle, SJ ;
Byun, TS ;
Farrell, K .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :912-917