Zobrazeno 1 - 10
of 50
pro vyhledávání: '"Fracture (geology)"'
Autor:
Jianguo Yang, Rong Liu, Yanming He, Wang Weizhen, He Huamin, Wenjian Zheng, Zengliang Gao, Chuanyang Lu
Publikováno v:
Journal of Nuclear Materials. 519:292-301
This study analyzed the effect of phase transformation on the creep behavior and deformation mechanism of SA508 Gr.3 steel used for nuclear reactor pressure vessels (RPVs). The creep tests were conducted on the steel at the temperatures from 650 to 8
Publikováno v:
Journal of Nuclear Materials. 518:409-418
The Master Curve approach allows the full characterisation of the ductile to brittle transition region (DBTR) of ferritic steels to be performed with a reduced number of tests. In this paper, the approach has been combined with the application of the
Publikováno v:
Journal of Nuclear Materials. 517:225-233
Local stress concentration sites and/or microstructural inhomogeneities result in the nucleation and initiation of adiabatic shear bands (ASB). This paper reports the influence of impurities for the initiation and evolution of ASBs in U-2.5 wt%Nb all
Publikováno v:
Journal of Nuclear Materials. 510:437-445
Effect of tempering time on fatigue crack behavior of China Low Activation Martensitic (CLAM) steel was studied at room temperature in air. The fatigue crack growth rates subjected to the tempering time range of 90–9000 min were investigated. The r
Publikováno v:
Journal of Nuclear Materials. 509:667-678
The assessment of the post-cracking behaviour of the reactor core components requires knowledge of the fracture properties, such as the fracture toughness, KIC, and work of fracture, γf, of irradiated graphite. The measurement of these properties is
Publikováno v:
Journal of Nuclear Materials. 508:440-450
In this paper, we focus mainly on evaluating the anisotropy evolution in Zircaloy-4 tubes with respect to hydrogen pickup which tends to affect the deformation behavior and fracture elongation due to embrittlement phenomenon induced by Zr hydrides. T
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
Publikováno v:
Journal of Nuclear Materials. 508:371-384
Increasing fracture toughness and modifying the ductile-brittle transition temperature of a tungsten-alloy relative to pure tungsten has been shown to be feasible by ductile-phase toughening (DPT) of tungsten for future plasma-facing materials for fu
Publikováno v:
Journal of Nuclear Materials
The work focuses on the investigation of the influence of neutron irradiation on the fracture mechanical properties of ITER specification-conform, stress-relieved tungsten bar. The irradiation of miniaturized Three-Point Bend specimens was performed
Publikováno v:
Journal of Nuclear Materials. 505:73-84
In this paper, Low Cycle Fatigue (LCF) and Creep-Fatigue Interaction (CFI) behavior of 9Cr-0.5Mo-1.8 W-V-Nb heat-resistant steel (ASME Grade P92 steel) at elevated temperature of 600 °C are investigated. Strain controlled LCF tests are conducted in