Zobrazeno 1 - 10
of 65
pro vyhledávání: '"Fracture (geology)"'
Autor:
A. Ya. Varovin, Boris Margolin, Е.V. Yurchenko, А.М. Morozov, S.V. Rogozkin, А.А. Nikitin, V. I. Kostylev
Publikováno v:
Journal of Nuclear Materials. 508:123-138
Radiation embrittlement of materials of support structures (SS) for reactor pressure vessel (RPV) of WWER types is considered. The features of radiation embrittlement of SS materials are connected with low irradiation temperature no exceeding 90 °C
Autor:
Khalid Hattar, Assel Aitkaliyeva, Lauren Nagel, John J. Mecholsky, Stuart A. Maloy, Tanvi Ajantiwalay
Publikováno v:
Journal of Nuclear Materials. 548:152866
Ferritic/martensitic steels, such as HT-9, are known for their complex microstructural features and mechanical properties. In this paper, in-situ micro-tensile tests and traditional fractography methods were utilized to study the fracture behavior of
Autor:
V. A. Potapova, V. A. Shvetsova, Valeriy Smirnov, A. J. Minkin, A. A. Sorokin, Boris Margolin
Publikováno v:
Journal of Nuclear Materials. 480:15-24
The experimental data on the fatigue crack growth rate (FCGR) have been obtained for austenitic steel of 18Cr-10Ni-Ti grade (Russian analog of AISI 321 steel) irradiated up to neutron dose of 150 dpa with various radiation swelling. The performed stu
Autor:
A. J. Minkin, V. A. Potapova, V. A. Shvetsova, Boris Margolin, A. A. Sorokin, Valeriy Smirnov
Publikováno v:
Journal of Nuclear Materials. 480:52-68
The radiation swelling effect on the fracture properties of irradiated austenitic steels under static loading has been studied and analyzed from the mechanical and physical viewpoints. Experimental data on the stress-strain curves, fracture strain, f
Autor:
Sylvain Meille, Cyril Langlois, Isabelle Zacharie-Aubrun, Ronan Henry, Thierry Blay, Smail Chalal, Nicolas Tarisien, Jean-Marie Gatt, Xavière Iltis
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, 2020, 536, ⟨10.1016/j.jnucmat.2020.152179⟩
Journal of Nuclear Materials, 2020, 536, ⟨10.1016/j.jnucmat.2020.152179⟩
Micro-cantilevers were prepared with a dual beam microscope SEM/FIB on different fresh and irradiated Pressurized Water Reactor (PWR) UO2 fuels. Their local fracture properties (fracture toughness and fracture stress) and Young's moduli were determin
Autor:
Keith R Hallam, Peter E J Flewitt, J. E. Darnbrough, Gillian E. Smith, Branko Šavija, Eleni Sarakinou, Peter J Heard, Erik Schlangen
Publikováno v:
Journal of Nuclear Materials, 499
Šavija, B, Smith, G E, Heard, P J, Sarakinou, E, Darnbrough, J E, Hallam, K R, Schlangen, E & Flewitt, P E J 2018, ' Modelling deformation and fracture of Gilsocarbon graphite subject to service environments ', Journal of Nuclear Materials, vol. 499, pp. 18-28 . https://doi.org/10.1016/j.jnucmat.2017.10.076
Šavija, B, Smith, G E, Heard, P J, Sarakinou, E, Darnbrough, J E, Hallam, K R, Schlangen, E & Flewitt, P E J 2018, ' Modelling deformation and fracture of Gilsocarbon graphite subject to service environments ', Journal of Nuclear Materials, vol. 499, pp. 18-28 . https://doi.org/10.1016/j.jnucmat.2017.10.076
Commercial graphites are used for a wide range of applications. For example, Gilsocarbon graphite is used within the reactor core of advanced gas-cooled reactors (AGRs, UK) as a moderator. In service, the mechanical properties of the graphite are cha
Publikováno v:
Journal of Nuclear Materials. 461:112-121
IASCC (Irradiation Assisted Stress Corrosion Cracking) crack initiation tests have been carried out on thimble tube material retrieved from a Belgian PWR. The crack initiation tests were carried out by constant load testing of thimble tube specimens
Autor:
R.N. Singh, J.K. Chakravartty, Priti Kotak Shah, J.S. Dubey, R.S. Shriwastaw, Anil Bhandekar, M.P. Dhotre, K.M. Pandit, S. Anantharaman
Publikováno v:
Journal of Nuclear Materials. 458:319-325
Fracture toughness of irradiated Zr–2.5Nb alloy pressure tube, fabricated by the cold pilgering and stress relieving route, was evaluated using disk compact tension type specimens. These specimens were punched out from the irradiated pressure tube
Publikováno v:
Journal of Nuclear Materials. 444:206-213
The temperature dependence of fracture toughness in HT9 steel irradiated to 3–145 dpa at 380–503 °C was investigated using miniature three-point bend (TPB) fracture specimens. A miniature-specimen reuse technique has been established: the tested
Publikováno v:
Journal of Nuclear Materials. 444:373-384
Tensile properties of austenitic stainless steels used for pressure vessel internals of WWER type reactors (18Cr–10Ni–Ti steel and its weld metal) in the initial and irradiated conditions were investigated. Based on the presented original investi