Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications

被引:133
作者
Tanigawa, H. [1 ]
Gaganidze, E. [2 ]
Hirose, T. [1 ]
Ando, M. [1 ]
Zinkle, S. J. [3 ]
Lindau, R. [2 ]
Diegele, E. [4 ]
机构
[1] Natl Inst Quantum & Radiol Sci & Technol, Aomori, Japan
[2] Karlsruhe Inst Technol, Karlsruhe, Germany
[3] Univ Tennessee, Knoxville, TN USA
[4] EUROfusion, Garching, Germany
关键词
reduced activation ferritic/martenssitic steel; joining technologies; irradiation effects; 14 MeV neutron irradiation effects; mitigation methodology; FERRITIC-MARTENSITIC STEEL; CYCLE FATIGUE PROPERTIES; MASTER-CURVE ANALYSIS; MATERIALS DESIGN-DATA; IN-BEAM FATIGUE; MECHANICAL-PROPERTIES; F82H STEEL; MICROSTRUCTURAL EVOLUTION; NEUTRON-IRRADIATION; CORROSION BEHAVIOR;
D O I
10.1088/1741-4326/57/9/092004
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Reduced-activation ferritic/martensitic (RAFM) steel is the benchmark structural material for in-vessel components of fusion reactor. The current status of RAFM developments and evaluations is reviewed based on two leading RAFM steels, F82H and EUROFER-97. The applicability of various joining technologies for fabrication of fusion first wall and blanket structures, such as weld or diffusion bonding, is overviewed as well. The technical challenges and potential risks of utilizing RAFM steels as the structural material of in-vessel components are discussed, and possible mitigation methodology is introduced. The discussion suggests that deuterium-tritium fusion neutron irradiation effects currently need to be treated as an ambiguity factor which could be incorporated within the safety factor. The safety factor will be defined by the engineering design criteria which are not yet developed with regard to irradiation effects and some high temperature process, and the operating time condition of the in-vessel component will be defined by the condition at which those ambiguities due to neutron irradiation become too large to be acceptable, or by the critical condition at which 14 MeV fusion neutron irradiation effects is expected to become different from fission neutron irradiation effects.
引用
收藏
页数:13
相关论文
共 101 条
[1]   High temperature deformation and damage behavior of RAFM steels under low cycle fatigue loading: Experiments and modeling [J].
Aktaa, J. ;
Schmitt, R. .
FUSION ENGINEERING AND DESIGN, 2006, 81 (19) :2221-2231
[2]   Mechanical properties of 9Cr martensitic steels and ODS-FeCr alloys after neutron irradiation at 325 °C up to 42 dpa [J].
Alamo, A. ;
Bertin, J. L. ;
Shamardin, V. K. ;
Wident, P. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (54-59) :54-59
[3]   Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773 K up to 5 dpa [J].
Ando, M. ;
Li, M. ;
Tanigawa, H. ;
Grossbeck, M. L. ;
Kim, S. ;
Sawai, T. ;
Shiba, K. ;
Kohno, Y. ;
Kohyama, A. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (122-126) :122-126
[4]   Effect of two-steps heat treatments on irradiation hardening in F82H irradiated at 573 K [J].
Ando, M. ;
Tanigawa, H. ;
Wakai, E. ;
Stoller, R. E. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :315-318
[5]   A LOCAL CRITERION FOR CLEAVAGE FRACTURE OF A NUCLEAR PRESSURE-VESSEL STEEL [J].
不详 .
METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1983, 14 (11) :2277-2287
[6]   Review of candidate welding processes of RAFM steels for ITER test blanket modules and DEMO [J].
Aubert, P. ;
Tavassoli, F. ;
Rieth, M. ;
Diegele, E. ;
Poitevin, Y. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :43-50
[7]   Mechanical and corrosion behaviour of EUROFER 97 steel exposed to Pb-17Li [J].
Benamati, G ;
Fazio, C ;
Ricapito, I .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (2 SUPPL.) :1391-1395
[8]   LOW ACTIVATION MATERIALS FOR FUSION APPLICATIONS [J].
BLOOM, EE ;
CONN, RW ;
DAVIS, JW ;
GOLD, RE ;
LITTLE, R ;
SCHULTZ, KR ;
SMITH, DL ;
WIFFEN, FW .
JOURNAL OF NUCLEAR MATERIALS, 1984, 122 (1-3) :17-26
[9]  
Bucenieks I., 2006, MAGNETOHYDRODYNAMICS, V42, P237
[10]   Materials researches at the Paul Scherrer Institute for developing high power spallation targets [J].
Dai, Yong ;
Wagner, Werner .
JOURNAL OF NUCLEAR MATERIALS, 2009, 389 (02) :288-296