Low cycle fatigue behaviour of TZM molybdenum alloy in divertor water coolant

被引:7
|
作者
Maday, MF
机构
[1] Dipartimento Innovazione, Divisione Materiali Avanzati, ENEA, 00100, Rome
关键词
D O I
10.1016/S0022-3115(96)00130-4
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Load controlled low cycle fatigue (LCF) tests on TZM Mo-alloy have been conducted up to specimen rupture, using two triangular load waveforms of 17 and 20 kN amplitudes, and in high temperature water (250 degrees C), either deaerated or containing separate additions of oxygen (10(-5) M/l), hydrogen (10(-3) M/l) and hydrogen peroxide (10(-4)-10(-5) M/l), in order to simulate the coolant chemistry inside the divertor tubings during fusion reactor operation. Extensions of TZM fatigue lives, compared to those obtained in the 20 kN experiments. were found to occur in all aqueous environments under the 17 kN cyclic load amplitude test, which induced a lower total strain range. It was also observed that, independently of the stressing conditions, the environments in terms of their deleterious effects on the LCF performances of TZM alloys, could be ranked in the following order: oxygenated water < deaerated water < hydrogenated water. Conflicting results were conversely obtained in hydrogen peroxide solutions, where the fatigue resistance was the lowest under 20 kN loading, but became the highest at a reduced amplitude of 17 kN. On the basis of visual assessments, and TZM open circuit potential values, continuously recorded during testing against an Ag/AgCl reference electrode, an idea about the corrosion behaviour of TZM alloy in high temperature water environments was proposed. Qualitative fractographic analysis was performed by scanning electron microscopy (SEM), to identify the predominant failure modes and suggest, in connection with the electrochemical evaluations, candidate cracking mechanisms, which accounted, reasonably, for the fatigue life data.
引用
收藏
页码:1397 / 1402
页数:6
相关论文
共 50 条
  • [1] Correlations between the electrochemical behaviour and surface film composition of TZM alloy exposed to divertor water coolant environments
    Maday, MF
    Giorgi, R
    DikonimosMakris, T
    JOURNAL OF NUCLEAR MATERIALS, 1997, 246 (01) : 70 - 76
  • [2] High temperature fatigue behaviour of TZM molybdenum alloy under mechanical and thermomechanical cyclic loads
    Shi, HJ
    Niu, LS
    Korn, C
    Pluvinage, G
    JOURNAL OF NUCLEAR MATERIALS, 2000, 278 (2-3) : 328 - 333
  • [3] FATIGUE CRACK GROWTH BEHAVIORS AT ELEVATED TEMPERATURE IN MOLYBDENUM AND TZM ALLOY
    Miyashita, Yukio
    Ameno, Hiroaki
    Mutoh, Yoshihau
    Nagata, Kosoku
    PROCEEDINGS OF THE 7TH INTERNATIONAL CONFERENCE ON MECHANICS AND MATERIALS IN DESIGN (M2D2017), 2017, : 517 - 518
  • [4] Low cycle fatigue behaviour of Inconel® alloy 783
    A. Nagesha
    Sunil Goyal
    M. Valsan
    K. Bhanu Sankara Rao
    Sarwan K. Mannan
    Transactions of the Indian Institute of Metals, 2010, 63 : 575 - 579
  • [5] Low cycle fatigue behaviour of InconelA® alloy 783
    Nagesha, A.
    Goyal, Sunil
    Valsan, M.
    Rao, K. Bhanu Sankara
    Mannan, Sarwan K.
    TRANSACTIONS OF THE INDIAN INSTITUTE OF METALS, 2010, 63 (2-3): : 575 - 579
  • [6] Low cycle fatigue behaviour of HAYNES 230 alloy
    Fahrmann, M. G.
    Srivastava, S. K.
    MATERIALS AT HIGH TEMPERATURES, 2014, 31 (03) : 221 - 225
  • [7] EFFECT OF HELIUM ON FATIGUE BEHAVIOR OF MOLYBDENUM-BASE-ALLOY TZM
    MICHEL, DJ
    SERPAN, CZ
    SMITH, HH
    PIEPER, AG
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 (NOV): : 144 - 145
  • [8] LOW CYCLE FATIGUE BEHAVIOUR OF LOW ALLOY STEEL PRESSURE VESSELS
    TAYLOR, TE
    BRITISH WELDING JOURNAL, 1967, 14 (12): : 641 - &
  • [9] Effect of zirconia on low cycle fatigue and energy absorption of molybdenum alloy
    Song, Wanli
    Xu, Liujie
    Li, Na
    Zhou, Yucheng
    Sun, Tielong
    Li, Zhou
    Shen, Huahai
    Wei, Shizhong
    JOURNAL OF ALLOYS AND COMPOUNDS, 2021, 867 (867)
  • [10] Effect of helium on the fatigue behavior of the molybdenum base alloy TZM at 900°C
    Michel, D.J.
    Serpan Jr, C.Z.
    Smith, H.H.
    Pieper, A.G.
    Nuclear Technology, 1 (79-87):