Zobrazeno 1 - 10
of 69
pro vyhledávání: '"Fracture (geology)"'
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
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
Publikováno v:
Journal of Nuclear Materials. 498:176-186
Creep strength enhanced ferritic (CSEF) P91 steel were subjected to room temperature tensile test for quasi-static (less than 10−1/s) strain rate by using the Instron Vertical Tensile Testing Machine. Effect of different type of notch geometry, not
Publikováno v:
Journal of Nuclear Materials. 554:153082
In this paper, the expansion deformation behavior of zirconium alloy claddings with different hydrogen concentrations was evaluated by the advanced expansion due to compression (A-EDC) test and ring tensile test. The results showed that in the A-EDC
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
Autor:
Makoto Hasegawa, Kazutoshi Tokunaga, Takeshi Toyama, Kazuo Nakamura, Satoru Matsuo, Hiroaki Kurishita
Publikováno v:
Journal of Nuclear Materials. 553:153054
Fracture toughness of the divertor armor in ITER needs to be elucidated for prediction of the response of armor materials to intense heat loading. The present study has been performed to establish a method for inserting a well, defined fatigue precra
Publikováno v:
Journal of Nuclear Materials. 496:313-324
The effect of prior single tensile overloading on the stress corrosion cracking behavior of cold rolled 316L in a simulated PWR water environment at 310 °C was investigated. SCC growth retardation by overloading was observed in cold rolled 316L spec
Publikováno v:
Journal of Nuclear Materials. 550:152933
Wire arc additive manufacturing (WAAM) with many superior characteristics, such as high deposition rate, low cost, free shape, and environmental friendliness has attracted much attention and will be used in the nuclear industry. A 308 L stainless ste
Publikováno v:
Journal of Nuclear Materials. 549:152911
The test results of tensile round bars from austenitic stainless steel of 18Cr-10Ni-Ti grade (Russian analog of AISI 321 steel) irradiated during 45 years in Pressure Water Reactor of WWER-440 type with various damage doses are represented over wide
Autor:
Shilei Han, Zongjian Chai, Guangpu Yang, Kuan Zhang, Hongbin Liao, Xiaoyu Wang, Ming Zhang, Pengyuan Lee, Haiying Fu, Qiang Wang, Wu Xinghua, Danhua Liu, Liwen Zhang, Jiming Chen
Publikováno v:
Journal of Nuclear Materials. 547:152811
Besides fusion structural materials themselves, research and development of small specimen test technologies (SSTTs) are also important for their joints for mechanical properties evaluation on resistance to neutron irradiation. Because the specimens