Zobrazeno 1 - 10
of 29
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
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. 501:200-207
In order to analyze the fracture toughness and fracture behavior (J-R curves) of China Low Activation Martensitic (CLAM) steel under the design service temperature of Test Blanket Module of the International Thermonuclear Experimental Reactor, the qu
Publikováno v:
Journal of Nuclear Materials. 553:152950
The objective of the present study was to provide new relevant information on creep behaviour and fracture processes in a sponge-based modified Zr1%Nb cladding alloy (modified E110 alloy) in the α-Zr and (α+β)-Zr phase regions. To this end, consta
Publikováno v:
Journal of Nuclear Materials. 553:153004
While it is well known that ceramic UO 2 fuel cracks early in its life in a nuclear reactor, it is very difficult to collect in-reactor data regarding fuel cracking initiation and propagation to validate fracture models in fuel performance codes. Mos
Publikováno v:
Journal of Nuclear Materials. 496:182-192
Axial fracture toughness of cold worked and stress relieved Zr-2.5Nb pressure tube material containing deuterium between 5 and 200wppm was determined as per ASTM E−1820-15 between 25 and 300 °C using 17 mm wide Curved Compact Tension samples. For