Zobrazeno 1 - 10
of 220
pro vyhledávání: '"G.E. Lucas"'
Autor:
G.E. Lucas
Publikováno v:
Journal of Nuclear Materials. 407:59-69
This paper attempts to summarize the lifetime contributions of Prof. G. Robert Odette to our understanding of the effects of neutron irradiation on reactor pressure vessel steel embrittlement. These contributions span the entire range of phenomena th
Autor:
Hideki Matsui, J.-W Rensman, Takuya Yamamoto, Philippe Spätig, Anton Möslang, G.E. Lucas, G.R. Odette
Publikováno v:
Journal of Nuclear Materials. :1549-1556
Small specimen test technology (SSTT) has long been an integral part of fusion materials development. Past work has led to an array of techniques that not only have provided a means of efficiently using available irradiation volumes but have also led
Autor:
H. Kishimoto, Takuya Yamamoto, W.J. Yang, Mikhail A. Sokolov, J.-W Rensman, Philippe Spätig, G.E. Lucas, G.R. Odette
Publikováno v:
Journal of Nuclear Materials. :1243-1247
Reference CRPP-ARTICLE-2008-019doi:10.1016/j.jnucmat.2004.04.255View record in Web of Science Record created on 2008-11-27, modified on 2017-05-12
Publikováno v:
Metallurgical and Materials Transactions A. 34:1043-1054
The kinetics of breakdown of Cu-Ag polycrystalline multilayers during aging at elevated temperatures was investigated. Microlaminates with Cu:Ag layer thicknesses of 2:2, 1:4, 4:1, and 4:0.1 µm were aged for 10 minutes to 192 hours (t), at temperatu
Publikováno v:
Journal of Nuclear Materials. :1643-1648
New innovative small specimen test techniques are described. Finite element simulations show that combinations of cone indentation pile-up geometry and load–penetration depth relations can be used to determine both the yield stress and strain-harde
Autor:
G.E. Lucas, G.R. Odette
Publikováno v:
JOM. 53:18-22
Neutron irradiation embrittlement could limit the service life of some of the reactor-pressure vessels in existing commercial nuclear-power plants. Improved understanding the of the underlying causes of embrittlement has provided regulators and power
Publikováno v:
Journal of Nuclear Materials. :637-641
A constitutive model for low-to-intermediate temperatures, strains, and strain rates is developed for the program heat of V–4Cr–4Ti. The basic form of the model is derived from more general dislocation-based models of yield stress and strain hard
Publikováno v:
Journal of Nuclear Materials. :987-991
The shear punch test was developed to address the need of the fusion reactor structural materials community for small scale mechanical properties tests. It has been demonstrated that effective shear strength data obtained from the shear punch test ca
Publikováno v:
Journal of Nuclear Materials. :518-522
Effects of irradiation and crossrolling on fracture toughness–temperature curves of the program heat of the V–4Cr–4Ti were evaluated. The alloy undergoes normal stress controlled cleavage fracture at low temperatures and ductile tearing fractur
Publikováno v:
Journal of Nuclear Materials. :992-996
The confocal microscopy (CM)–fracture reconstruction (FR) method, coupled with scanning electron microscopy (SEM) fractography, was used to measure the critical notch deformation conditions at cleavage initiation for two subsized Charpy V-notch (CV