The European effort towards the development of a demo structural material:: Irradiation behaviour of the European reference RAFM steel EUROFER

被引:39
作者
Lucon, E
Benoit, P
Jacquet, P
Diegele, E
Lässer, R
Alamo, A
Coppola, R
Gillemot, F
Jung, P
Lind, A
Messoloras, S
Novosad, P
Lindau, R
Preininger, D
Klimiankou, M
Petersen, C
Rieth, M
Materna-Morris, E
Schneider, HC
Rensman, JW
van der Schaaf, B
Singh, BK
Spaetig, P
机构
[1] CEN SCK, B-2400 Mol, Belgium
[2] EFDA Close Support Unit, D-85748 Garching, Germany
[3] CEA Saclay, F-91191 Gif Sur Yvette, France
[4] ENEA Casaccia, FIS, I-00100 Rome, Italy
[5] AEKI Atom Res Inst, H-1121 Budapest, Hungary
[6] Forschungszentrum Juelich, D-52425 Julich, Germany
[7] Studsvik Eco & Safety AB, SE-61182 Nykoping, Sweden
[8] Natl Ctr Sci Res Demokritos, Athens 15310, Greece
[9] Nucl Res Inst, CZ-25068 Rez, Czech Republic
[10] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
[11] NRG, Petten, Netherlands
[12] Riso Natl Lab, Mat Res Dept, DK-4000 Roskilde, Denmark
[13] Assoc EURATOM Swiss Confederat, FTM, CRPP, Ecole Polytech Fed Lausanne,PSI, CH-5232 Villigen, Switzerland
关键词
reduced activation ferritic/martensitic steels; EUROFER; irradiation; post-irradiation examination; theoretical study;
D O I
10.1016/j.fusengdes.2005.08.044
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Worldwide programs aimed at developing materials for future fusion plants are presently concentrating on reduced activation ferritic/martensitic (RAFM) steels. In Europe, a Fusion Long Term Programme is being carried out under the coordination of European Fusion Development Agreement (EFDA) Close Support Unit (Garching, Germany); in the framework of this programme, extensive research is currently in progress for the development and full qualification of the European reference 9Cr RAFM steel, designated EUROFER. This paper focuses on the work being performed within the EFDA Technology Workprogram TTMS-001 task "Irradiation Perfonnance of EUROFER", aimed at defining the post-irradiation mechanical and microstructural characteristics of the material, through irradiations, post-irradiation examinations (PlEs) and theoretical studies. An overview of the progress made will be given, as well as an anticipation of future research activities. (c) 2005 Elsevier B.V. All rights reserved.
引用
收藏
页码:917 / 923
页数:7
相关论文
共 21 条
[1]   CORROSION OF INSULATING LAYERS ON MANET STEEL IN FLOWING PB-17LI [J].
BORGSTEDT, HU ;
GLASBRENNER, H ;
PERIC, Z .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :1501-1503
[2]   LOWER ACTIVATION MATERIALS AND MAGNETIC FUSION-REACTORS [J].
CONN, RW ;
BLOOM, EE ;
DAVIS, JW ;
GOLD, RE ;
LITTLE, R ;
SCHULTZ, KR ;
SMITH, DL ;
WIFFEN, FW .
NUCLEAR TECHNOLOGY-FUSION, 1984, 5 (03) :291-310
[3]   SANS and TEM study of Y2O3 particle distributions in oxide-dispersion strengthened EUROFER martensitic steel for fusion reactors [J].
Coppola, R. ;
Klimiankou, M. ;
Lindau, R. ;
May, R. P. ;
Valli, M. .
PHYSICA B-CONDENSED MATTER, 2004, 350 (1-3) :E545-E548
[4]   Helium bubble evolution in F82H-mod -: correlation between SANS and TEM [J].
Coppola, R ;
Klimiankou, M ;
Magnani, M ;
Möslang, A ;
Valli, M .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :1057-1061
[5]   Polarised SANS study of microstructural evolution under neutron irradiation in a martensitic steel for fusion reactors [J].
Coppola, R ;
Dewhurst, CD ;
Lindau, R ;
May, RP ;
Möslang, A ;
Valli, M .
PHYSICA B-CONDENSED MATTER, 2004, 345 (1-4) :225-230
[6]   Survey of in-vessel candidate materials for fusion power plants - the European materials R&D programme [J].
Gasparotto, M ;
Andreani, R ;
Boccaccini, LV ;
Cardella, A ;
Federici, G ;
Giancarli, L ;
Le Marois, G ;
Maisonnier, D ;
Malang, S ;
Moeslang, A ;
Poitevin, Y ;
van der Schaaf, B ;
Victoria, M .
FUSION ENGINEERING AND DESIGN, 2003, 66-68 :129-137
[7]   MICROSTRUCTURAL DEVELOPMENT IN REDUCED-ACTIVATION FERRITIC ALLOYS IRRADIATED TO 200-DPA AT 420-DEGREES-C [J].
GELLES, DS .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :714-719
[8]   Microstructural analysis of neutron-irradiated martensitic steels [J].
Kai, JJ ;
Klueh, RL .
JOURNAL OF NUCLEAR MATERIALS, 1996, 230 (02) :116-123
[9]   ELEVATED-TEMPERATURE TENSILE PROPERTIES OF IRRADIATED 9 CR-1 MOVNB STEEL [J].
KLUEH, RL ;
VITEK, JM .
JOURNAL OF NUCLEAR MATERIALS, 1985, 132 (01) :27-31
[10]   TENSILE PROPERTIES OF 9CR-1MOVNB AND 12CR-1MOVW STEELS IRRADIATED TO 23-DPA AT 390 TO 550-DEGREES-C [J].
KLUEH, RL ;
VITEK, JM .
JOURNAL OF NUCLEAR MATERIALS, 1991, 182 :230-239