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Chihiro Kondo,Tadashi Kondo 제어로봇시스템학회 2009 제어로봇시스템학회 국제학술대회 논문집 Vol.2009 No.8
A revised Group Method of Data Handling (GMDH)-type neural network algorithm for medical image recognition is proposed and is applied to 3-dimensional medical image analysis of the heart. The revised GMDH-type neural network algorithm has a feedback loop and can identify the characteristics of the medical images accurately using feedback loop calculations. In this algorithm, the polynomial type and the radial basis function (RBF) type neurons are used for organizing the neural network architecture. The optimum neural network architecture fitting the complexity of the medical images is automatically organized so as to minimize the prediction error criterion defined as Prediction Sumof Squares (PSS).
Revised RBF network algorithm and its application to the interactive art system
Chihiro Kondo,Tadashi Kondo 제어로봇시스템학회 2009 제어로봇시스템학회 국제학술대회 논문집 Vol.2009 No.8
In this study, a revised radial basis function (RBF) network is proposed and applied to the identification problems of the nonlinear system and the interactive art system. In the revised RBF network, the structural parameters such as means and variances of the radial basis functions in the neurons are determined automatically and so revised RBF network can be easily applied to the practical complex problems such as the interactive art system. The interactiveart system outputs the art expressions such as the sound and graphics using the artificial sensibility curves that are identified using the revised RBF network.
DT Neutronics Benchmark Experiment on Lead at JAEA-FNS
Kentaro Ochiai,Keitaro Kondo,Seiki Ohnishi,Kosuke Takakura,Satoshi Sato,Yuichi Abe,Chikara Konno,Chihiro Suzuki,Takahiro Yagi 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Lead is one of the most important candidate materials for nuclear fusion reactor blankets. We have carried out an integral benchmark experiment on lead at the DT neutron source facility of JAEA, FNS. A cubic lead assembly on a side of 45.3 cm was set up and was irradiated with the DT neutron source. Reaction rates of the ^(27)Al(n,α)^(24)Na, ^(93)Nb(n,2n)^(92m)Nb, ^(90)Zr(n,2n)^(89)Zr, and ^(115)In(n,n')^(115m)In reactions and neutron spectra above 2 MeV were measured inside the assembly with activation foil and a small NE213 spectrometer, respectively. A Monte Carlo code, MCNP5, was adopted to calculate the reaction rates and neutron spectra. The latest nuclear data libraries, JENDL-3.3 ENDF/B-VII.0, JEFF-3.1 and FENDL-2.1, were used in the calculation. The calculation results with the three libraries except for JENDL-3.3 agreed with the measured reaction rates and neutron spectra. On the other hand, that with JENDL-3.3 underestimated the measured ones with the depth. We found out that the inappropriate evaluation of the (n,2n), elastic scattering and inelastic scattering reactions in the lead isotopes of JENDL-3.3 caused the disagreements.