Zobrazeno 1 - 10
of 114
pro vyhledávání: '"Shiro Jitsukawa"'
Publikováno v:
Materials, Vol 15, Iss 6, p 2300 (2022)
1.2C–4Cr–4Mo–10W–3.5V–10Co–Fe high-speed steel (JIS SKH57; ISO HS10-4-3-10) is often manufactured via casting and forging. By applying powder metallurgy, the properties of the abovementioned material can be improved. In this study, the ef
Externí odkaz:
https://doaj.org/article/c94adcca73c948a0bc30ff3d2a622aa9
Autor:
Kiyoyuki Shiba, G.R. Odette, Shiro Jitsukawa, Shigeharu Ukai, Ronald L. Klueh, Satoshi Ohtsuka, Mikhail A. Sokolov, Akihiko Kimura, Ryuta Kasada, Hiroyasu Tanigawa, Takanori Hirose, Takuya Yamamoto, Akira Kohyama
Publikováno v:
Journal of Nuclear Materials. :60-67
The mechanisms of irradiation embrittlement of two Japanese RAFSs were different from each other. The larger DBTT shift observed in F82H is interpreted by means of both hardening effects and a reduction of cleavage fracture stress by M23C6 carbides p
Autor:
Ronald L. Klueh, Naoyuki Hashimoto, Koreyuki Shiba, Shiro Jitsukawa, Mikhail A. Sokolov, Philip J. Maziasz
Publikováno v:
Journal of Nuclear Materials. 357:169-182
In part I of this helium-effects study on ferritic/martensitic steels, results were presented on tensile and Charpy impact properties of 9Cr–1MoVNb (modified 9Cr–1Mo) and 12Cr–1MoVW (Sandvik HT9) steels and these steels containing 2% Ni after i
Publikováno v:
Journal of Nuclear Materials. 357:156-168
Tensile and Charpy specimens of 9Cr–1MoVNb (modified 9Cr–1Mo) and 12Cr–1MoVW (Sandvik HT9) steels and these steels doped with 2% Ni were irradiated at 300 and 400 °C in the High Flux Isotope Reactor (HFIR) up to ≈12 dpa and at 393 °C in the
Autor:
D. Yamaki, Shiro Jitsukawa
Publikováno v:
Fusion Engineering and Design. 81:589-593
Among the various tritium transport processes in lithium ceramics, the importance and the detailed mechanism of surface reactions still remains to be elucidated. The dynamic adsorption and desorption (DAD) model has been developed to calculate the tr
Autor:
Akira Kohyama, Shiro Jitsukawa, Akio Sagara, Mikio Enoeda, Satoshi Konishi, Ryuta Kasada, Takayuki Terai, Shigeharu Ukai, Akihiko Kimura, Masato Akiba
Publikováno v:
Fusion Engineering and Design. 81:909-916
The reduced activation ferritic steel (RAFS) has been selected as structural material for a variety of blanket systems for ITER test blanket modules (TBM). In the evaluation of integrated performance of ferritic steels as structural components of bla
Publikováno v:
Fusion Engineering and Design. 81:595-600
The tritium release behavior from Li2O sintered pellets (81–88% T.D.) is examined by isothermal heating tests. (1) For the 88% T.D. specimens, the fraction of residual tritium is found to follow the square-root law of the annealing time. The rate-d
Autor:
Hiroyasu Tanigawa, Soumei Ohnuki, Shiro Jitsukawa, K. Furuya, Fumiki Takada, Shingo Matsukawa, H. Ohtsuka, T. Yamamoto, K. Oka, Eiichi Wakai
Publikováno v:
Fusion Engineering and Design. 81:1077-1084
Small specimen test technology (SSTT) has been developed to investigate mechanical properties of nuclear materials. SSTT has been driven by limited availability of effective irradiation volumes in test reactors and accelerator-based neutron and charg
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 242:469-472
The effect of implanted helium (He) on the thermal diffusivities of SiC/SiC composites was investigated. In the result, thermal diffusivities of SiC/SiC composites decreased after He implantation. The thermal diffusivities of implanted specimens were