Water corrosion resistance of ODS ferritic-martensitic steel tubes

被引:5
|
作者
Narita, Takeshi [1 ]
Ukai, Shigeharu [1 ]
Kaito, Takeji [1 ]
Ohtsuka, Satoshi [1 ]
Matsuda, Yasuji [2 ]
机构
[1] Japan Atom Energy Agcy, Oarai, Ibaraki 3111393, Japan
[2] Sumitomo Met Technol Inc, Amagasaki, Hyogo 6600856, Japan
关键词
F0800 (fusion reactor materials); C0500 (cladding materials); F0200 (fast reactor materials); S1000; (steels; ferritic/martensitic; low activation) spent fuel pool cooling system; water corrosion; pH; alkaline corrosion resistance; alloy elements;
D O I
10.3327/jnst.45.99
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
A water corrosion test was conducted on oxide dispersion strengthened (ODS) steels in consideration of the spent fuel-pool cooling condition. The two types of ODS steel tubes tested were 9Cr-ODS and 12Cr-ODS. A test temperature of 333K was selected for the test by considering the environment of spent fuel-pool cooling system. The water corrosion test was performed for 1000h under a degassed and Cl-controlled water environment at pH values of 8.4, 10 and 12. The result demonstrated that at a pH value of 12, the weight losses of 9Cr- and 12Cr-ODS are larger than those of PNC-FMS and PNC316. The test specimens lose their metallic gloss and a slightly blackish surface is observed. It is considered that 9Cr-ODS and 12Cr-ODS claddings keep their strength and are comparable to that of conventional austenitic stainless steel and ferritic-martensitic stainless steel claddings in consideration of the spent-fuel-pool cooling condition.
引用
收藏
页码:99 / 102
页数:4
相关论文
共 50 条
  • [1] Corrosion Resistance of Chromium-Coated Ferritic-Martensitic Steel in Supercritical Water
    Zhang, Xiaoxin
    Yan, Qingzhi
    Yang, Ying
    Hong, Zhiyuan
    Zhang, Lefu
    Ge, Changchun
    CORROSION, 2015, 71 (01) : 50 - 56
  • [2] Fatigue behaviour of ODS ferritic-martensitic Eurofer steel
    Kubena, I.
    Kruml, T.
    Spaetig, P.
    Baluc, N.
    Oksiuta, Z.
    Petrenec, M.
    Obrtlik, K.
    Polak, J.
    FATIGUE 2010, 2010, 2 (01): : 717 - 724
  • [3] Effect of irradiation temperature on microstructure of ferritic-martensitic ODS steel
    Klimenkov, M.
    Lindau, R.
    Jaentsch, U.
    Moeslang, A.
    JOURNAL OF NUCLEAR MATERIALS, 2017, 493 : 426 - 435
  • [4] Corrosion of ferritic-martensitic steel HT9 in supercritical water
    Ren, X.
    Sridharan, K.
    Allen, T. R.
    JOURNAL OF NUCLEAR MATERIALS, 2006, 358 (2-3) : 227 - 234
  • [5] Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water
    Bischoff, Jeremy
    Motta, Arthur T.
    JOURNAL OF NUCLEAR MATERIALS, 2012, 424 (1-3) : 261 - 276
  • [6] ANNEALING EFFECTS ON THE MICROSTRUCTURE OF FERRITIC-MARTENSITIC ODS-EUROFER STEEL
    Renzetti, R. A.
    Sandim, H. R. Z.
    Padilha, A. F.
    Raabe, D.
    Lindau, R.
    Moeslang, A.
    FUSION SCIENCE AND TECHNOLOGY, 2011, 60 (1T) : 22 - 26
  • [7] Corrosion behavior of ferritic-martensitic steel P92 in supercritical water
    Zhu, Fa-Wen
    Zhang, Le-Fu
    Tang, Rui
    Qiao, Pei-Peng
    Bao, Yi-Chen
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2010, 44 (08): : 979 - 983
  • [8] Corrosion behavior of ferritic-martensitic steel T91 in supercritical water
    Chen, Yun
    Sridharan, Kumar
    Allen, Todd
    CORROSION SCIENCE, 2006, 48 (09) : 2843 - 2854
  • [9] Corrosion of ferritic-martensitic steels in steam and supercritical water
    Bischoff, Jeremy
    Motta, Arthur T.
    Eichfeld, Chad
    Comstock, Robert J.
    Cao, Guoping
    Allen, Todd R.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 441 (1-3) : 604 - 611
  • [10] Annealing behavior of ferritic-martensitic 9%Cr-ODS-Eurofer steel
    Sandim, H. R. Z.
    Renzetti, R. A.
    Padilha, A. F.
    Raabe, D.
    Klimenkov, M.
    Lindau, R.
    Moeslang, A.
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2010, 527 (15): : 3602 - 3608