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Featured researches published by Satoru Katsuragi.


Journal of Nuclear Science and Technology | 1969

Higher Order Perturbation Method in Reactor Calculation

Reiko Saito; Satoru Katsuragi

The higher order perturbation theory is applied to the one-dimensional multi-group diffusion equation. The method of calculating the eigenvalue, eigenfunction and adjoint function of the higher mode is established for a non-Hermetian matrix. The diffusion equation is solved by the higher order perturbation method, through the use of the eigenvalues, eigenfunctions and adjoint functions of the higher modes. The newly developed method is applied to the estimation of reactivity effect in a reactor.


Journal of Nuclear Science and Technology | 1976

A Method of Calculation of Detailed Power Distribution in Fuel Assemblies

T. Suzuki; Satoru Katsuragi

Abstract A method has been developed that effectively estimates the detailed distribution of power generation in the fuel or blanket assemblies in nuclear reactors. A two-dimensional, one-group diffusion model is applied to a region of homogeneous composition enclosed in a contour devoid of concavity viewed from outside. The diffusion equation is reduced to the form of Helmholtz equation, and a non-homogeneous boundary condition of Dirichlet or Neumann type is given on the contour, using neutron fluxes previously obtained in coarse mesh diffusion criticality calculations covering the whole reactor. This boundary value problem in two-dimensional space is made to yield a solution in the form of a potential due to a single or double layer. The method is applied to a hexagonal cell of a fast reactor. The results of calculation are amply accurate in comparison with the corresponding values from the usual fine-mesh diffusion scheme and with much shorter computing time.


Transport Theory and Statistical Physics | 1973

Transport solutions for multilayer slab-cell systems

Tomio Yoshimura Ship; Satoru Katsuragi; T. Suzuki

Abstract Cases method is applied to one-speed neutron-transport problems in multiplayer slab cells. A set of singular integral equations for the eigen-function-expansion coefficients of the angular neutron flux is derived, and two methods of solution suitable for numerical calculation are presented. In the first method the solution of the Hilbert problem is obtained in the form of power series for a coupling parameter. In the second method the singular integral equations are reduced to a set of Fred Holms integral equations. The numerical results are given.


Journal of Nuclear Science and Technology | 1965

EXPERIMENTAL AND THEORETICAL STUDIES OF HEAVY-WATER HOMOGENEOUS TWO-REGION SYSTEM

Jitsuya Hirota; Satoru Katsuragi; Reiko Saito; Takehiko Yasuno

A series of critical experiments and theoretical analyses has been made on two-region systems in which a heavy water solution of uranyl sulfate with 235U enrichment of about 20% is surrounded by heavy water, poisoned with B or mixed with ThO2. D-to-235U atomic ratios in the core solutions ranged 4,500–1,000, depending on the core diameter and the blanket concentration. The theoretical effective multiplication factor is decreased by treating the leakage of fast neutrons from the core rigorously, and is increased by using spatial-dependent effective cross sections. These treatments are justified by the agreement found between the calculated and measured values for the Cd ratio and the thermal flux distribution. The disagreement seen in the effective multiplication factor between the theoretical and experimental values may be attributed to uncertainty in the resonance integral of 235U. The discrepancy in the effective multiplication factors does not exceed 1%, when the accepted value of νI f -I a is reduced ...


Journal of Nuclear Science and Technology | 1978

Benchmark Tests of Radiation Transport Computer Codes for Reactor Core and Shield Calculations

Takumi Asaoka; Norio Asano; Hisashi Nakamura; Hiroshi Mizuta; Hiroshi Chichiwa; Tadahiro Ohnishi; Shun-ichi Miyasaka; Atsushi Zukeran; Tsuneo Tsutsui; Toichiro Fujimura; Satoru Katsuragi


Journal of Nuclear Science and Technology | 1968

A Note on Treatments of Sodium Void Reactivity Effects in a Large Fast Reactor

Tatsuzo Tone; Satoru Katsuragi


Journal of Nuclear Science and Technology | 1973

Analysis of sodium void reactivity measured in FCA V-1 assembly

Masayuki Nakagawa; Hideki Takano; Satoru Katsuragi


Nuclear Science and Engineering | 1970

THE CONSTRUCTION OF NEUTRON CROSS SECTIONS IN THE UNRESOLVED RESONANCE REGION.

Yukio Ishiguro; Satoru Katsuragi; Masayuki Nakagawa; Hideki Takano


Journal of Nuclear Science and Technology | 1969

Some Remarks on the Concept of Group Constants in Resonance Energy Region, (I) Resonance Shielding Factors Including Interference Effects

Masayuki Nakagawa; Hideki Takano; Yukio Ishiguro; Satoru Katsuragi


Journal of Nuclear Science and Technology | 1970

Accuracy of Analytical Treatments for Resonance Absorption in Doppler Resonance Regions

Hideki Takano; Masayuki Nakagawa; Yukio Ishiguro; Satoru Katsuragi

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Hideki Takano

Japan Atomic Energy Research Institute

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Masayuki Nakagawa

Japan Atomic Energy Research Institute

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Yukio Ishiguro

Japan Atomic Energy Research Institute

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Jitsuya Hirota

Japan Atomic Energy Research Institute

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Reiko Saito

Japan Atomic Energy Research Institute

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T. Suzuki

Japan Atomic Energy Research Institute

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Tatsuzo Tone

Japan Atomic Energy Research Institute

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Hideo Kuroi

Japan Atomic Energy Research Institute

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Shun-ichi Miyasaka

Japan Atomic Energy Research Institute

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Takehiko Yasuno

Japan Atomic Energy Research Institute

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