Zobrazeno 91 - 100
of 344
pro vyhledávání: '"Fracture (geology)"'
Publikováno v:
Journal of Nuclear Materials. 435:222-230
The fracture strength of δ-zirconium hydrides embedded in a zirconium matrix was determined at temperatures between 25 °C and 250 °C by ring tensile tests using Zircaloy-2 tubes. Essentially all of the present hydrides in the tubes were re-oriente
Publikováno v:
Journal of Nuclear Materials. 432:78-86
Creep-to-rupture experiments were performed on 9%-Cr ferritic–martensitic steel P92 in the CRISLA facility. The specimens of P92 were examined at 650 °C and static tensile stress between 75 and 325 MPa in both stagnant lead with 10 −6 mass% diss
Autor:
Masatoshi Futakawa, Motoki Ooi, Fujio Maekawa, Masahide Harada, Makoto Teshigawara, Tetsuya Kai
Publikováno v:
Journal of Nuclear Materials. 431:212-217
A plan of 2nd moderator fabrication in JSNS is under way. In terms of low thermal expansion, invar joints, such as Invar-Al and Invar-SS316L joints, were developed by friction welding method as a component of hydrogen transfer line. Mechanical tests
Autor:
Véronique Rabeau, P. Wident, J. Garnier, Benjamin Fournier, Tomáš Kruml, L. Ziolek, J. Malaplate, M. Ratti, Ivo Kubena, J.M. Gentzbittel, A.-L. Rouffie, A. Steckmeyer, Ivan Tournié
Publikováno v:
Journal of Nuclear Materials. 430:142-149
Ferritic 14%Cr and 18%Cr ODS steels produced at CEA in round bars or plates were tested mechanically. The present paper reports results obtained in tension, impact, fatigue, creep and toughness tests. These tests were carried out at various temperatu
Publikováno v:
Journal of Nuclear Materials. 427:364-377
Stainless steels are widely used in primary circuits of pressurized water reactors (PWRs). Operating experience with the various grades of stainless steels over several decades of years has generally been excellent. Nevertheless, stress corrosion fai
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2012, 426 (1-3), pp.71-77. ⟨10.1016/j.jnucmat.2012.03.040⟩
Journal of Nuclear Materials, Elsevier, 2012, 426 (1-3), pp.71-77. ⟨10.1016/j.jnucmat.2012.03.040⟩
The liquid–metal-induced fracture mode of T91 martensitic steel was investigated by using transmission electron microscopy techniques to characterize the microstructure and crack network in specimens obtained from focused-ion beam machining at and
Publikováno v:
Journal of Nuclear Materials. 420:226-234
The high temperature deformation and fracture behaviour of 316L stainless steel under high strain rate loading conditions are investigated by means of a split Hopkinson pressure bar. Impact tests are performed at strain rates ranging from 1 × 103 s
Publikováno v:
Journal of Nuclear Materials. 418:223-232
Pile grade A (PGA) graphite is used as a moderator in UK gas cooled nuclear reactors. This is a polygranular, aggregate material with quasi-brittle behaviour. When exposed to the service environment the material is subject to radiolytic oxidation tha
Autor:
Toshiharu Fujisawa, Fujio Abe, Masaki Inoue, Akihiko Kimura, Shigeharu Ukai, Somei Ohnuki, J. Isselin, Ryuta Kasada, Takanari Okuda
Publikováno v:
Journal of Nuclear Materials. 417:185-188
The effect of aging on the ductile to brittle transition behavior of recrystallized high-Cr ODS ferritic steels were investigated using small-punch test technique. In order to reduce the anisotropy of microstructure in the as-received ODS steels, the
Publikováno v:
Journal of Nuclear Materials. 417:383-386
In this study, the evaluation of shear strength for joined SiC ceramics was conducted by using a torsion test. Two specimen types based on F734-95 ASTM Standard and one proposed for miniature test specimen in this study were prepared. The effects of