Effects of Te on intergranular embrittlement of a Ni-16Mo-7Cr alloy

被引：35
作者：
Cheng, Hongwei [1 ,2 ]
Han, Fenfen [1 ]
Jia, Yanyan [1 ]
Li, Zhijun [1 ]
Zhou, Xingtai [1 ]
机构：
[1] Chinese Acad Sci, Shanghai Inst Appl Phys, Thorium Molten Salts Reactor Ctr, Shanghai 201800, Peoples R China
[2] Univ Chinese Acad Sci, Beijing 100049, Peoples R China
来源：
JOURNAL OF NUCLEAR MATERIALS | 2015年 / 461卷
关键词：
MOLTEN-SALT REACTOR; FUEL-CYCLE; TEMPERATURE; BEHAVIOR; CRACKING; NICKEL; TH;
D O I：
10.1016/j.jnucmat.2015.01.049
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Te was deposited on the surface of a Ni-16Mo-7Cr alloy by thermal evaporation at 700 degrees C, and the effect of Te on the intergranular cracking behavior and the tensile properties of the alloy was investigated. The results show that the reaction products formed on the surface of the alloy, the diffusion depth of Te in the alloy, and the yield strength of the alloy attacked by Teat room temperature are not changed remarkably with Te content increasing, whereas the ultimate tensile strength and elongation of the alloy is decreased distinctly. The primary surface reaction product are mainly composed of Ni3Te2, CrTe, and MoTe2, and the diffusion depth of Te in the alloys is about 50 mu m. The intergranular embrittlement mechanism of the alloy induced by Te of is also discussed in this paper. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码：122 / 128
页数：7
相关论文
共 24 条
  • [1] CHEMISTRY AND THERMODYNAMICS OF MOLTEN-SALT REACTOR-FUELS
    BAES, CF
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1974, 51 (01) : 149 - 162
  • [2] ON TELLURIDES OF NICKEL
    BARSTAD, J
    GRONVOLD, F
    ROST, E
    VESTERSJO, E
    [J]. ACTA CHEMICA SCANDINAVICA, 1966, 20 (10): : 2865 - +
  • [3] Briggs R., 1972, ORNL4812
  • [4] Molten fluorides for nuclear applications
    Delpech, Sylvie
    Cabet, Celine
    Slima, Cyrine
    Picard, Gerard S.
    [J]. MATERIALS TODAY, 2010, 13 (12) : 34 - 41
  • [5] Characteristics of hydrogen embrittlement, stress corrosion cracking and tempered martensite embrittlement in high-strength steels
    Eliaz, N
    Shachar, A
    Tal, B
    Eliezer, D
    [J]. ENGINEERING FAILURE ANALYSIS, 2002, 9 (02) : 167 - 184
  • [6] Potential of activated carbon adsorption processes for the remediation of nuclear effluents: a recent literature
    Foo, K. Y.
    Hameed, B. H.
    [J]. DESALINATION AND WATER TREATMENT, 2012, 41 (1-3) : 72 - 78
  • [7] A road map for the realization of global-scale thorium breeding fuel cycle by single molten-fluoride flow
    Furukawa, Kazuo
    Arakawa, Kazuto
    Erbay, L. Berrin
    Ito, Yasuhiko
    Kato, Yoshio
    Kiyavitskaya, Hanna
    Lecocq, Alfred
    Mitachi, Koshi
    Moir, Ralph
    Numata, Hiroo
    Pleasant, J. Paul
    Sato, Yuzuru
    Shimazu, Yoichiro
    Simonenco, Vadim A.
    Sood, Din Dayal
    Urban, Carlos
    Yoshioka, Ritsuo
    [J]. ENERGY CONVERSION AND MANAGEMENT, 2008, 49 (07) : 1832 - 1848
  • [8] Gabbard C.H., 1970, TM2978 ORNL, P11
  • [9] Gehlbach R.E., 1972, ORNL4832, P79
  • [10] Molten salt actinide recycler and transforming system without and with Th-U support: Fuel cycle flexibility and key material properties
    Ignatiev, V.
    Feynberg, O.
    Gnidoi, I.
    Merzlyakov, A.
    Surenkov, A.
    Uglov, V.
    Zagnitko, A.
    Subbotin, V.
    Sannikov, I.
    Toropov, A.
    Afonichkin, V.
    Bovet, A.
    Khokhlov, V.
    Shishkin, V.
    Kormilitsyn, M.
    Lizin, A.
    Osipenko, A.
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 64 : 408 - 420
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