E. Gaganidze, N. Meena, L. Chauhan, Q. Yuan, J. Aktaa
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引用次数: 0
Abstract
The fracture-mechanical behavior of a uniaxially rolled ITER grade tungsten plate has been investigated up to test temperatures of 700°C. To study the influence of the anisotropic grain microstructure on the Ductile-to-Brittle Transition Temperature (DBTT) and failure mechanism, fracture toughness testing has been performed for four specimen extraction orientations: longitudinal - long transverse (L-T), long transverse - longitudinal (T-L), longitudinal - short transverse (L-S) and long transverse - short transverse (T-S). The DBTTs were at around 250°C and 300°C in L-T and T-L orientations, respectively. In the case of L-S and T-S orientations, the crack deflection prevented unambiguous identification of the DBTT. An upper bound of the DBTT for L-S and T-S orientations was estimated in the range of 300-350°C. Transgranular cleavage was a dominant fracture mode for L-T and T-L orientations at low test temperatures. In contrast to this, for L-S and T-S orientations strong deflections of the crack towards the rolling direction have been recognized which are linked to the anisotropic grain microstructure of the plate material. At the highest test temperatures, no failure of the specimens has been observed up to severe deflection levels which is linked to an extended blunting of the crack starter notch tip and related suppression of the crack initiation and propagation.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.