Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Fumiki Takada"'
Autor:
Y. Ito, Fumiki Takada, Joaquin Molla, Katsumasa Nakamura, Eiichi Wakai, Akihiko Kimura, M. Saito, Shuhei Nogami, P. Garin, Hiroaki Kurishita, Ryuta Kasada
Publikováno v:
Journal of Nuclear Materials. 417:1325-1330
About one thousands of small size specimens will be irradiated in the High Flux Test Module (HFTM) with a limited irradiation volume of 0.5 l in the International Fusion Materials Irradiation Facility (IFMIF). It is necessary to verify that the exper
Publikováno v:
Nuclear Engineering and Design. 240:1290-1305
In order to develop a systematic and reasonable concept assuring the structural integrity of components under intense neutron irradiation, two basic tensile properties, true stress–true strain (TS–TS) curves and fracture strain, were investigated
Reduction method of DBTT shift due to irradiation for reduced-activation ferritic/martensitic steels
Publikováno v:
Journal of Nuclear Materials. 398:64-67
The method for reducing irradiation-induced DBTT shift of reduced-activation ferritic/martensitic steels was examined. F82H-LN (low nitrogen, 20 ppm), F82H+60 ppm11B+200 ppmN and F82H+60 ppm10B+200 ppmN steels tempered at 780 °C for 0.5 h were irrad
Autor:
M. Ando, Hiroyasu Tanigawa, Roger E. Stoller, Fumiki Takada, T. Yamamoto, Yoshiaki Kato, Eiichi Wakai, Tomotsugu Sawai, Tomitsugu Taguchi
Publikováno v:
Journal of Nuclear Materials. :74-80
The dependence of irradiation hardening of F82H steel on tempering conditions was examined by JMTR and HFIR irradiation experiments. The JMTR and HFIR irradiations were performed to 2 dpa at 250 °C and 5 dpa at 300 °C, respectively. Irradiation har
Publikováno v:
Journal of Nuclear Materials. 355:119-123
In the case of a blanket module replacement in the ITER, cooling water pipe will be joined to irradiated pipe by the laser welding method. On the cooling water piping of the ITER blanket, various loads (the vibration of coolant flow, plasma disruptio
Autor:
M. Sato, K. Furuya, T. Tomita, Fumiki Takada, M. Ando, K. Oka, Kenji Kikuchi, Eiichi Wakai, Yoshiaki Kato, Soumei Ohnuki, Tomotsugu Sawai, H. Tomita
Publikováno v:
Journal of Nuclear Materials. 356:95-104
Effects of displacement damage and gas atoms on microstructures and mechanical properties of F82H steel were examined by some various different methods. The hardness of F82H was increased by triple beams, dual beams and single beam at 270 °C to 20 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:
Fusion Engineering and Design. 81:631-637
In support of the ITER blanket fabrication, this study clarified the neutron irradiation effect on the tensile properties of HIP joints using stainless steels and the effect of surface roughness (Ry) at the joint boundary on tensile properties of HIP
Autor:
Soumei Ohnuki, H. Tomita, Shiro Jitsukawa, Yoshinobu Tayama, Masayasu Sato, T. Yamamoto, K. Furuya, Eiichi Wakai, T. Tanaka, Koreyuki Shiba, K. Oka, Fumiki Takada, Yoshio Kato
Publikováno v:
Journal of Nuclear Materials. 343:285-296
The dependence of helium production on radiation hardening and -embrittlement has been examined in a reduced-activation martensitic F82H steel (8Cr–2W–0.2V–0.04Ta–0.1C) irradiated at 250 °C to 2.3 dpa. In this study, 10 B and 11 B-doped spec
Autor:
T. Yamamoto, Fumiki Takada, S. Matsukawa, Tomitsugu Taguchi, H. Tomita, Eiichi Wakai, M. Ando
Publikováno v:
Fusion Science and Technology. 47:856-860
The dependence of ductile-brittle transition temperature (DBTT) on tempering time and temperature was examined for a martensitic steel F82H irradiated at 150 and 250°C to a neutron dose of 1.9 dpa ...