Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Hiroaki Shibazaki"'
Autor:
Akihide Hidaka, Yu Maruyama, Jun Sugimoto, Kazuichiro Hashimoto, Hiroaki Shibazaki, Yuhei Harada, Akio Maeda, Tamotsu Kudo
Publikováno v:
Nuclear Technology. 134:62-70
Aerosol revaporization in piping is being investigated in the WIND project at the Japan Atomic Energy Research Institute. The objectives of this study are to characterize the aerosol revaporization...
Publikováno v:
Journal of Aerosol Science. 31:1045-1059
A relatively small-scale aerosol deposition experiment (called WAVE) in a quartz glass pipe with a 90° bend followed by a short straight section was performed at Japan Atomic Energy Research Institute to investigate the effect of pipe orientation on
Autor:
Kazuichiro Hashimoto, Jun Sugimoto, Eiichi Chino, Hiroaki Shibazaki, Yuhei Harada, Akio Maeda, Yu Maruyama, Tamotsu Kudo, Akihide Hidaka
Publikováno v:
Journal of Nuclear Science and Technology. 37:518-529
It has been pointed out that the reactor coolant system piping could fail prior to the meltthrough of the reactor pressure vessel in a high pressure sequence of pressurized water reactor severe accidents. In order to apply to the evaluation of the pi
Autor:
Kazuichiro Hashimoto, Yuhei Harada, Jun Sugimoto, Akio Maeda, Tamotsu Kudo, Akihide Hidaka, Hiroaki Shibazaki, Yu Maruyama
Publikováno v:
Journal of Nuclear Science and Technology. 36:923-933
In a severe accident of light water reactors, the reactor coolant system (RCS) piping might be subjected to thermal loads caused by the decay heat of the deposited fission products and the heat transfer from the hot gases, with an internal pressure i
Autor:
Yu Maruyama, Hiroaki Shibazaki, Jum Sugimoto, Kazuichiro Hashimoto, Naohiko Nakamura, Akihide Hidaka, Akio Maeda, Yuhei Harada, Minoru Igarashi
Publikováno v:
Journal of Nuclear Science and Technology. 36:433-442
The aerosol deposition test series is being performed to investigate the deposition of FP vapor and aerosol onto the inner surface of reactor coolant piping during a severe accident of a light water reactor. Vapor and aerosol of CsI as an FP simulant
Publikováno v:
Heat Transfer - Japanese Research. 27:284-298
Heat transfer experiments were carried out for natural convection in an enclosure, simulating a dry shielded canister with 24 PWR spent fuel assemblies. The objectives of this study were to investigate the thermal hydraulic characteristics of natural
Publikováno v:
Journal of the Visualization Society of Japan. 17:309-312
Exchange flows through breaches of a vacuum vessel (VV) in a fusion reactor under the Loss-of-Vacuum-Accident (LOVA) conditions were observed to obtain velocity distributions and clarify those flow patterns. The exchange flows were visualized by smok
Publikováno v:
Journal of Nuclear Science and Technology. 33:821-828
A heat transfer and flow visualization experiment was conducted with a one-fifth scale model simulating a dry shielded canister (DSC) with 24 PWR spent fuel assemblies in order to elucidate the heat transfer characteristics and the velocity distribut