Zobrazeno 1 - 10
of 28
pro vyhledávání: '"Masami Shindo"'
Publikováno v:
JSME International Journal Series A. 45:104-109
A series of weldability and creep tests of the weld metals were conducted to develop a filler metal with excellent weldability and high creep strength of the weldments of Ni-Cr-W superalloy. Contents of minor elements have a large effect on susceptib
Autor:
Yukio Itabashi, S. Shimakawa, H Amezawa, Masami Shindo, Teruo Kikuchi, H Mimura, Hirokazu Tsuji, Yuji Kurata
Publikováno v:
Journal of Nuclear Materials. :386-390
In addition to post-irradiation creep tests, in-pile creep tests were performed using newly developed technology with in situ measurement under different neutron spectra. The in-pile creep properties of type 304 stainless steel at 550°C appear to de
Autor:
Yuji Kurata, Tatsuhiko Tanabe, Keijiro Hiraga, Masami Shindo, Tomio Suzuki, Isao Mutoh, Hirokazu Tsuji
Publikováno v:
Journal of Nuclear Science and Technology. 36:1160-1166
Creep tests of base metal, weld metal and welded joint of Hastelloy XR, which had the same chemical composition as Hastelloy XR produced for an intermediate heat exchanger of the High-Temperature Engineering Test Reactor, were conducted in simulated
Publikováno v:
Journal of Nuclear Materials. 246:196-205
The creep rupture properties in air environment were studied at 900, 1000 and 1050°C for bar, plate and seamless tube materials of a NiCrW superalloy developed for use at service temperatures around 1000°C. The long-term creep rupture strengt
Publikováno v:
Scopus-Elsevier
The relationship between creep rupture lives and cavitation damage is examined in a welded Ni-base alloy, Hastelloy XR, in an impure He gas at 1123–1273 K. The rupture lives of the welded joints are almost the same as those of the base metal at low
Autor:
Y Miwa, S. Hamada, Shiro Jitsukawa, Takashi Tsukada, Satoshi Kita, Yoshinori Matsui, Masami Shindo
Publikováno v:
Journal of Nuclear Materials. :1393-1396
A low impurity Fe 18Cr 12Ni (HP) and its heats doped with Si and C (HP + Si and HP + C) were irradiated to 6.7 × 10 24 n/m 2 ( E ≫ 1 MeV) at 513 K. The slow strain rate tensile (SSRT) tests were carried out at a constant strain rate of 1.7 × 10
Publikováno v:
Journal of Nuclear Science and Technology. 32:1108-1117
Publikováno v:
Journal of Nuclear Materials. 217:110-117
For the characteristic evaluation of developed compositionally gradient graphite materials, which are composed of a surface SiC coating layer, an intermediate SiC/C layer and a graphite matrix, a thermal cyclic oxidation test in air environment was c
Publikováno v:
Journal of Nuclear Materials. 203:10-16
For the improvement of the oxidation resistance of a graphite material, a preparation study of compositionally gradient SiC/C layer was performed. The compositionally gradient material of SiC/C, which is a graphite material with compositionally gradi
Publikováno v:
Journal of Nuclear Materials. 187:204-208
For advanced graphite materials, functionally gradient material (FGM) of silicon carbide and carbon (SiC/C) has been prepared in order to improve the oxidation resistance. The FGM of SiC/C prepared by the reaction between graphite and gaseous silicon