DEVELOPMENT OF REDUCED-ACTIVATION MARTENSITIC 9CR STEELS FOR FUSION-REACTOR

被引:29
|
作者
ABE, F
NODA, T
ARAKI, H
OKADA, M
机构
关键词
FUSION REACTORS; REDUCED ACTIVATION; FERRITIC-MARTENSITIC STEELS; 9CR STEELS; MICROSTRUCTURAL EVOLUTION; TOUGHNESS; HIGH-TEMPERATURE; STRENGTH; CREEP; IRRADIATION HARDENING; TUNGSTEN ADDITIONS; VANADIUM ADDITIONS; CHROMIUM ADDITIONS;
D O I
10.3327/jnst.31.279
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
In order to develop reduced-activation ferritic/martensitic steels potentially suitable for fusion reactor applications, the effect of principal alloying elements Cr, W and V on the microstructural evolution, toughness and high-temperature creep strength was systematically investigated for relatively simple Cr-W-V steels. Based on the results on the simple steels, two kinds of martensitic 9Cr steels with low and high levels of W were alloy-designed: 9Cr-1WVTa and 9Cr-3WVTa. They exhibited excellent toughness and high-temperature strength. Irradiation hardening was the smaller for the reduced-activation 9Cr-1WVTa and 9Cr-3WVTa steels than for the conventional 9Cr-1MoVNb and it was smaller for the low W steel than for the high W steel. It is concluded that from the aspect of toughness the 9Cr-1WVTa steel is the most promising alloy for the first wall and blanket structures which will be operated at low temperatures below 773 K (500-degrees-C). Another 9Cr-3WVTa steel is the most promising in terms of high-temperature creep strength for the future power reactor structures which will be operated at temperatures higher than 773 K.
引用
收藏
页码:279 / 292
页数:14
相关论文
共 50 条
  • [1] Effect of alloying on the properties of 9Cr low activation martensitic steels
    Ma, Rong
    Yang, Yafeng
    Yan, Qingzhi
    Yang, Ying
    Li, Xinggang
    Ge, Changchun
    ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2010, 23 (06) : 451 - 460
  • [2] Microstructural Modifications due to Tungsten and Tantalum in 9Cr Reduced Activation Ferritic Martensitic Steels on Creep Exposure
    Mythili, R.
    Ravikirana
    Vanaja, J.
    Laha, K.
    Saroja, S.
    Jayakumar, T.
    Mathew, M. D.
    Rajendrakumar, E.
    6TH INTERNATIONAL CONFERENCE ON CREEP, FATIGUE AND CREEP-FATIGUE INTERACTION, 2013, 55 : 295 - 299
  • [3] EFFECT OF NEUTRON-IRRADIATION ON YIELD STRESS AND DUCTILITY OF REDUCED-ACTIVATION MARTENSITIC 9CR-WVTA STEELS
    ABE, F
    NARUI, M
    KAYANO, H
    MATERIALS TRANSACTIONS JIM, 1993, 34 (11): : 1053 - 1060
  • [4] Effect of thermomechanical treatment on 9Cr ferritic-martensitic steels
    Tan, L.
    Busby, J. T.
    Maziasz, P. J.
    Yamamoto, Y.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 441 (1-3) : 713 - 717
  • [5] Tensile Flow Behavior of 9Cr-2WVTa Reduced-Activation Ferritic/Martensitic Steel
    Najafi, Hamidreza
    JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 2016, 138 (03):
  • [6] Interfacial plasticity mediated by lath boundaries in reduced-activation ferritic/martensitic steels
    Ghaffarian, Hadi
    Na, Ye-Eun
    Jang, Dongchan
    JOURNAL OF NUCLEAR MATERIALS, 2022, 559
  • [7] Effect of Microstructures and Tempering Heat Treatment on the Mechanical Properties of 9Cr-2W Reduced-Activation Ferritic-Martensitic Steel
    Park, Min-Gu
    Moon, Joonoh
    Lee, Tae-Ho
    Kang, Nam Hyun
    Kim, Hyoung Chan
    Lee, Chang-Hoon
    KOREAN JOURNAL OF METALS AND MATERIALS, 2015, 53 (05): : 312 - 319
  • [8] A fusion relevant data-driven engineering void swelling model for 9Cr tempered martensitic steels
    Yamamoto, Takuya
    Odette, G. Robert
    JOURNAL OF NUCLEAR MATERIALS, 2023, 576
  • [9] Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications
    Tanigawa, H.
    Gaganidze, E.
    Hirose, T.
    Ando, M.
    Zinkle, S. J.
    Lindau, R.
    Diegele, E.
    NUCLEAR FUSION, 2017, 57 (09)
  • [10] Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors
    Tan, L.
    Snead, L. L.
    Katoh, Y.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 478 : 42 - 49