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Nuclear Science and Engineering | 1976

A Coarse-Mesh Correction of the Finite Difference Method for Neutron Diffusion Calculations

Yasuyoshi Kato; Toshikazu Takeda; Seiichi Takeda

This study has been undertaken to evaluate an uncertainty in a finite difference method for two-dimensional neutron diffusion calculations and to provide a simple method to eliminate the uncertainty from k/sub eff/, control rod worth, and peak power density. An effect of a condensation of the energy groups is also studied. It is found that errors in k/sub eff/, control rod worth, and peak power density have linear relationships with the square of mesh spacing, and an extrapolation to zero mesh spacing, by using the linear relationships, is possible, eliminating the uncertainties of 0.7 percent ..delta..k/k in k/sub eff/, approximately 8 percent in control rod worth and approximately 2 percent in peak power density in a case of a mesh calculation as coarse as one mesh point per subassembly. When a basic multigroup cross-section set is condensed into a few-group cross-section set, the errors due to the condensation of the cross sections on k/sub eff/ and on control rod worth are shown to have linear relationships with the inverse square of the number of the condensed energy group. These relationships have been confirmed analytically with the application of perturbation theory.


Journal of Nuclear Science and Technology | 1978

Spatial mesh effect in three-dimensional diffusion calculations for fast reactors.

Masaharu Sakagami; Seiichi Takeda


Archive | 1975

Control rod used for a fast breeder reactor

Seiichi Takeda; Kiyoshi Tsutsumi; Masaaki Yamamoto


Journal of Nuclear Science and Technology | 1978

Application of BWR simulator to neutronics calculation tool in fast reactors.

Seiichi Takeda; Masaharu Sakagami


Journal of Nuclear Science and Technology | 1978

Development of Nuclear Safety Information Retrieval System

Seiichi Takeda; Katsuyuki Kato; Tsutomu Kinbara


Journal of Nuclear Science and Technology | 1978

Numerical Study of Burnup Characteristics of 300 MWe LMFBR Based on Three-Dimensional Calculation

Seiichi Takeda


Journal of Nuclear Science and Technology | 1975

Effect of Number of Regions in Burnup Calculation for a Fast Reactor

Toshikazu Takeda; Seiichi Takeda


Journal of Nuclear Science and Technology | 1974

Effect of diffusion coefficient collapsing on neutron multiplication factor

Toshikazu Takeda; Seiichi Takeda


Journal of Nuclear Science and Technology | 1978

Effect of Np-239 on Fast Reactor Burnup Calculation

Seiichi Takeda; Kazuyoshi Miki


Journal of Nuclear Science and Technology | 1975

Analysis of Control Rod Effect on Neutronics in FBR by Three-Dimensional Calculation

Tomofumi Kobayashi; Seiichi Takeda

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