Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Takamichi Ogino"'
Autor:
Takamichi Ogino
Publikováno v:
Annals of Japan Prosthodontic Society. 10:353-356
Publikováno v:
Journal of prosthodontic research. 61(1)
Purpose We examined how chewing rate and the extent of reactive hyperemia affect the blood flow in denture-supporting mucosa during chewing. Methods The left palatal mucosa was loaded under conditions of simulated chewing or simulated clenching for 3
Publikováno v:
Journal of Nuclear Science and Technology. 26:52-59
This paper reviews contributions in the application of knowledge information technology to nuclear power plants with emphasis on case descriptions of knowledge-based system development in three major application domains; design and planning, operatio
Autor:
Karen H. Koger, M. Jonathan Haire, Brett L. Humphrys, Jay F. Manneschmidt, Keiichi Setoguchi, Ryodai Nakai, Kazunori Sasaki, Naotaka Terashita, Takamichi Ogino, Makoto Osaki, Akira Kanagawa, Jan-Li Wang, Jay F. Kunze, L. C. Lewis, J. P. Henscheid, Mukesh Tayal, Lorne D. Macdonald, Erl Kohn, Walter P. Dovigo, T. Sampat Sridhar, Michael P. Manahan, Xiangdong Feng, Ian L. Pegg, Aaron Barkatt, Pedro B. Macedo, Samuel J. Cucinell, Shantao Lai, R. K. S. Rathore, P. Munshi, P. Arora, S. D. Malik, A. K. Vaish, K. S. Singh, U. Singh
Publikováno v:
Nuclear Technology. 85:245-249
Publikováno v:
Progress in Nuclear Energy. 9:107-121
Out-of-pile experiments were carried out to study the feasibility of the local sodium boiling detection by use of temperature, flow and acoustic noises. The studies showed that the temperature fluctuation transferred the information of local sodium b
Publikováno v:
Reliability Engineering & System Safety. 22:387-399
This paper describes the MITI (Ministry of International Trade and Industry) projects for decision support systems for NPPs in Japan. Main attention is paid to the new project of an advanced man-machine system for nuclear power plants, of which a con
Publikováno v:
Nuclear Technology. 85:259-273
This article discusses a pressurized water reactor plant analyzer code (NUPAC-1) has been developed to apply to an operator support system or an advanced training simulator. The simulation code must produce reasonably accurate results as well as fun
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