Deformation and fracture of carbonaceous materials using in situ micro-mechanical testing

被引:24
作者
Liu, Dong [1 ,2 ]
Flewitt, Peter E. J. [1 ]
机构
[1] Univ Bristol, HH Wills Phys Lab, Tyndall Ave, Bristol BS8 1TL, Avon, England
[2] Univ Oxford, Dept Mat, Parks Rd, Oxford OX1 3PH, England
基金
英国工程与自然科学研究理事会;
关键词
NUCLEAR GRAPHITE; MECHANICAL-PROPERTIES; NEUTRON-IRRADIATION; CARBONS; MICROSTRUCTURE; BEHAVIOR; DAMAGE; MODEL; FILMS;
D O I
10.1016/j.carbon.2016.11.084
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
The local mechanical properties of vitreous carbon and another three porous graphite materials have been investigated using a novel in situ micro-cantilever bending approach. Vitreous carbon is used for validation of the micro-mechanical measurements. Filter graphite is a single phase material with similar to 52 vol % porosity. Gilsocarbon graphite is a nuclear-grade graphite that is currently used in the advanced gascooled reactors in the UK with similar to 20 vol% porosity in the filler particles and matrix; Pile Grade-A graphite (PGA) was extracted from a fuel brick within a Magnox reactor core with 15% weight loss due to neutron irradiation and CO2 radiolytic oxidation. The 'true' material properties obtained at micro-scale are found to be of much higher value than those measured at the macro-scale due to different failure controlling mechanisms. In particular for the PGA graphite, the micro-mechanical tests allowed the mechanical properties of the filler particles and matrix to be measured separately. The filler particles showed a higher stiffness and flexural strength compared with the matrix indicating the different influence of neutron irradiation on these two constituents. It is demonstrated here that the local mechanical properties of carbonaceous materials with various complex microstructures and even following neutron irradiation can be successfully" evaluated. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:261 / 274
页数:14
相关论文
共 47 条
  • [1] Hardening of self ion implanted tungsten and tungsten 5-wt% rhenium
    Armstrong, D. E. J.
    Yi, X.
    Marquis, E. A.
    Roberts, S. G.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 432 (1-3) : 428 - 436
  • [2] Nanoindentation and micro-mechanical fracture toughness of electrodeposited nanocrystalline Ni-W alloy films
    Armstrong, D. E. J.
    Haseeb, A. S. M. A.
    Roberts, S. G.
    Wilkinson, A. J.
    Bade, K.
    [J]. THIN SOLID FILMS, 2012, 520 (13) : 4369 - 4372
  • [3] Armstrong D.E.J., 2011, J MATER RES, V24, P3268
  • [4] BAKER DE, 1970, NUCL ENG DES, V14, P413, DOI 10.1016/0029-5493(70)90160-3
  • [5] Microstructural modelling of nuclear graphite using multi-phase models
    Berre, C.
    Fok, S. L.
    Marsden, B. J.
    Mummery, P. M.
    Marrow, T. J.
    Neighbour, G. B.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2008, 380 (1-3) : 46 - 58
  • [6] ANALYSIS OF THE DIMENSIONAL CHANGES AND STRUCTURAL-CHANGES IN POLYCRYSTALLINE GRAPHITE UNDER FAST-NEUTRON IRRADIATION
    BROCKLEHURST, JE
    KELLY, BT
    [J]. CARBON, 1993, 31 (01) : 155 - 178
  • [7] A microstructurally based fracture model for polygranular graphites
    Burchell, TD
    [J]. CARBON, 1996, 34 (03) : 297 - 316
  • [8] Vitreous Carbon - A New Form of Carbon
    Cowlard, F. C.
    Lewis, J. C.
    [J]. JOURNAL OF MATERIALS SCIENCE, 1967, 2 (06) : 507 - 512
  • [9] Micro-scale testing of ductile and brittle cantilever beam specimens in situ with a dual beam workstation
    Darnbrough, J. E.
    Liu, D.
    Flewitt, P. E. J.
    [J]. MEASUREMENT SCIENCE AND TECHNOLOGY, 2013, 24 (05)
  • [10] Sharp indentation behavior of carbon/carbon composites and varieties of carbon
    Diss, P
    Lamon, J
    Carpentier, L
    Loubet, JL
    Kapsa, P
    [J]. CARBON, 2002, 40 (14) : 2567 - 2579