Zobrazeno 1 - 10
of 41
pro vyhledávání: '"Norio Nagata"'
Publikováno v:
TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series C. 64:1854-1859
Publikováno v:
Journal of the Japan Society for Precision Engineering. 64:1831-1835
This paper describes the mechanism of brittle-ductile transition of monocrystal silicon at a high temperature and its feasibility for ductile mode cutting. The micro-cutting tests were carried out at various temperatures, and for various cutting spee
Autor:
Norio Nagata, Tsuyoshi Arakawa
Publikováno v:
Journal of Alloys and Compounds. :864-866
The luminescence properties of A 1 − x Eu x Al 12 O 19 (A = Ca, Sr, Ba) as the β-aluminas type compound was investigated. Judging from the luminescence spectra and Mossbauer spectra, europium ions in these compounds were almost divalent state. The
Publikováno v:
Tetsu-to-Hagane. 81:827-832
Publikováno v:
JSME international journal. Ser. C, Dynamics, control, robotics, design and manufacturing. 37:450-455
For the purpose of reducing the uncomfortable sway motion of high-rise buildings, induced by comparatively strong winds, a tuned active damper (TAD) equipped with a new mechanism has been developed, and installed in the Yokohama Landmark Tower. Throu
Publikováno v:
Zairyo-to-Kankyo. 42:636-640
Publikováno v:
ISIJ International. 33:877-883
Effect of dissolved oxygen concentration on fatigue crack growth behavior of a low alloy pressure vessel steel A533B CI. 1 in high temperature water was investigated. Fatigue tests were conducted at 561 K in water, of which DO concentration ranged fr
Publikováno v:
Journal of the Society of Materials Science, Japan. 41:1648-1654
Effect of water flow rate on fatigue crack growth behavior in high temperature water simulating BWR environments was examined by using a flow rate change test method. Materials used in this work were two types of low alloy pressure vessel steels A533
Publikováno v:
ISIJ International. 31:106-114
Low cycle fatigue behavior of low alloy steels ASTM A508 C1.3(JIS SFVQ1A) and ASTM A533B C1.1(JIS SQV2A) for nuclear reactor pressure vessels was investigated in high temperature pressurized water simulating BWR coolant environments. Total strain ran
Publikováno v:
Zairyo-to-Kankyo. 40:323-329