Toshikazu Takeda

Q: What Schools Are Affiliated With Toshikazu Takeda

Toshikazu Takeda is affiliated with the following schools: Osaka University, University of Fukui

Toshikazu Takeda's AcademicInfluence.com Rankings

Toshikazu Takeda

Engineering

#6832

World Rank

#8180

Historical Rank

Earthquake Engineering

#11

World Rank

#12

Historical Rank

Civil Engineering

#342

World Rank

#406

Historical Rank

engineering Degrees

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Engineering

Toshikazu Takeda's Degrees

PhD Civil Engineering University of Tokyo
Masters Civil Engineering University of Tokyo
Bachelors Civil Engineering University of Tokyo

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Toshikazu Takeda's Published Works

Number of citations in a given year to any of this author's works

Total number of citations to an author for the works they published in a given year. This highlights publication of the most important work(s) by the author

Published Works

Reinforced Concrete response to simulated earthquakes (1970) (1140)
3-D Neutron Transport Benchmarks (1991) (131)
Effective Convergence of Fission Source Distribution in Monte Carlo Simulation (2001) (38)
Development of Spatially Dependent Resonance Shielding Method (2005) (37)
Ferroelectric Properties of (Ag, Li)(Nb, Ta)O3 Ceramics (2001) (37)
Prediction Uncertainty Evaluation Methods of Core Performance Parameters in Large Liquid-Metal Fast Breeder Reactors (1989) (34)
Estimation of Error Propagation in Monte-Carlo Burnup Calculations (1999) (32)
Burnup sensitivity analysis in a fast breeder reactor-Part I : Sensitivity calculation method with generalized perturbation theory (1985) (31)
Verification of 3D Heterogeneous Core Transport Calculation Utilizing Non-linear Iteration Technique (2004) (30)
A New Nodal SN Transport Method for Three-Dimensional Hexagonal Geometry (1994) (23)
Extension of Askew's Coarse Mesh Method to Few-Group Problems for Calculating Two-Dimensional Power Distribution in Fast Breeder Reactors (1978) (22)
Transport Calculations of MOX and UO2 Pin Cells by the Method of Characteristics (1998) (20)
Minor actinides transmutation performance in a fast reactor (2016) (20)
Three-dimensional transport calculation method for eigenvalue problems using diffusion synthetic acceleration. (1985) (20)
A Coarse-Mesh Correction of the Finite Difference Method for Neutron Diffusion Calculations (1976) (19)
Effects of Substitution of Na and K Ions for Ag Ion in (Ag,Li)NbO3 Ceramics (2003) (19)
Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors (2003) (19)
Effect of Sn2+ Ion Substitution on Dielectric Properties of (Ba,Ca)TiO3 Ferroelectric Ceramics (2010) (19)
The Verification of 3 Dimensional Nodal Kinetics Code ANCK Using Transient Benchmark Problems (2007) (19)
Generalized Bias Factor Method for Accurate Prediction of Neutronics Characteristics (2006) (18)
Theoretical Study on New Bias Factor Methods to Effectively Use Critical Experiments for Improvement of Prediction Accuracy of Neutronic Characteristics (2007) (17)
Core performance tests for the JOYO MK-III upgrade (2007) (16)
Application of Multiband Method to KUCA Tight-Pitch Lattice Analysis (1991) (16)
Spatially Dependent Self-Shielding Method with Temperature Distribution for the Two-Dimensional Transport Code PARAGON (2006) (16)
Application of the response matrix method to BWR lattice analysis (1981) (15)
Effect of Radial Void Distribution within Fuel Assembly on Assembly Neutronic Characteristics (2002) (15)
Interpretation of actinide transmutation in thermal and fast reactors (2002) (14)
Sensitivity and uncertainty analysis for UO2 and MOX fueled PWR cells (2015) (13)
Development and Verification of an Efficient Spatial Neutron Kinetics Method for Reactivity-Initiated Event Analyses (2001) (13)
Neutronic model for modal multichannel analysis of out-of-phase instability in boiling water reactor cores (1997) (13)
Analysis of the SPERT-III E-Core Using ANCK Code with the Chord Weighting Method (2009) (13)
Study on neutron spectrum for effective transmutation of minor actinides in thermal reactors (1997) (13)
Importance of self-shielding for improving sensitivity coefficients in light water nuclear reactors (2014) (12)
Sensitivity Analysis based on Transport Theory (2006) (12)
Space and angle dependent collision probability in cell problems (1973) (11)
Nonlinear Behavior under Regional Neutron Flux Oscillations in BWR Cores (2001) (11)
Three-dimensional transport correction in fast reactor core analysis. (1986) (10)
An effective homogenization method for heterogeneous assemblies (1982) (10)
Analysis of First-Harmonic Eigenvalue Separation Experiments on KUCA Coupled-Core (1998) (10)
Evaluation of Eigenvalue Separation by the Monte Carlo Method (2002) (10)
An Improvement of the Transverse Leakage Treatment for the Nodal SN Transport Calculation Method in Hexagonal-Z Geometry (1996) (10)
New Control Rod Homogenization Method for Fast Reactors (1994) (10)
Anisotropic Collision Probabilities in Cell Problems (1971) (9)
New Calculational Method of Sensitivity Coefficients of Cell Parameters and Its Application (1986) (9)
Extension of Effective Cross Section Calculation Method for Neutron Transport Calculations in Particle-dispersed Media (2006) (9)
A multiband method with resonance interference effect (1999) (9)
Depletion Calculations for PWR Assemblies including Burnable Absorbers with Lattice Code PARAGON (2006) (8)
Reactivity feedback effect on loss of flow accident in PWR (2018) (8)
Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores (2002) (7)
A combined cross-section adjustment and bias factor method for accurate prediction of fast breeder reactor core performance parameters (1993) (7)
Interpretation of transmutation rates of minor actinides in thermal and fast reactors (1998) (7)
Reduction of Systematic Error in Radiopharmaceutical Activity by Entropy Based Mutual Information (2012) (7)
Sensitivity Analysis of Cell Neutronic Parameters in High-Conversion Light-Water Reactors (1987) (7)
Simple and Efficient Parallelization Method for MOC Calculation (2010) (7)
Reaction Rate Calculation in Fast Reactor Blanket Using Multiband Sn Theory (2000) (7)
The Characteristics and Subgroup Methods in Square Light Water Reactor Cell Calculations (2003) (6)
FATIGUE PERFORMANCE OF RC BEAMS STRENGTHENED WITH EXTERNALLY PRESTRESSED PBO FIBER SHEETS (2003) (6)
Doppler reactivity calculation for thermal reactor cells by space-dependent multiband method (1996) (6)
CALCULATION OF THE ANISOTROPIC DIFFUSION COEFFICIENT. (1972) (6)
Development of Erbia-Credit Super High Burnup Fuel: Experiments and Numerical Analyses (2012) (6)
Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide—Fueled Tight-Pitch Light Water Reactor Cells (2000) (6)
Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part II: Prediction Accuracy of Burnup Characteristics (1985) (6)
Parametric Study on Fast Reactors with Low Sodium Void Reactivity by the Use of Zirconium Hydride Layer in Internal Blanket (1997) (6)
Optimization of Internal Blanket Configuration of Large Fast Reactor (1993) (6)
Application of depletion perturbation theory to fuel loading optimization. (1986) (5)
Neutronics Codes Currently Used in Japan for Fast and Thermal Reactor Applications (2004) (5)
Prediction Accuracy Improvement of Neutronic Characteristics of a Breeding Light Water Reactor Core by Extended Bias Factor Methods with Use of FCA-XXII-1 Critical Experiments (2008) (5)
Application of Multiband Method to Pin Cell Calculations. (1993) (5)
Analysis of Large Liquid-Metal Fast Breeder Reactor Critical Experiments by Improved Methods (1988) (5)
Effect of void propagation to sodium void reactivity in transient analyses of fast reactors with sodium-plenum (2018) (5)
Effect of Higher Order Anisotropy on Disadvantage Factor in a Cell (1972) (5)
An estimation of cross-section covariance data suitable for predicting neutronics parameters uncertainty (2020) (5)
Rapid Estimation of Core-Power Ratio in Coupled-Core System by Rod Drop Method (2000) (4)
Resonance calculations using the multiband method and interface currents (1997) (4)
Anisotropic Diffusion Coefficient in a Cylindrical Cell by Integral Transport Theory (1973) (4)
Numerical instability of time-discretized one-point kinetic equations (2000) (4)
An Improved Response Matrix Method for Calculating Neutron Flux Distributions (1977) (4)
Effective one-group coarse-mesh method for calculating three-dimensional power distribution in fast reactors (1979) (3)
Three-dimensional multigroup diffusion code ANDEX based on nodal method for cartesian geometry. (1990) (3)
A new cross section adjustment method of removing systematic errors in fast reactors (2017) (3)
Sensitivity Analysis of Fast Reactor Core Performance Parameters Calculated by JENDL-2 and JENDL-3 (1990) (3)
Development of an advanced controlling system for non-refueling reactors (2005) (3)
Critical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models (2005) (3)
Spatially and Temperature Dependent Dancoff Method for LWR Lattice Physics Code (2004) (3)
Uncertainty analysis of minor actinides transmutation in fast reactor cores (2017) (3)
Effect of Anisotropic Scattering in a Square Cell with Thin Moderator (1972) (3)
Three-Dimensional Transient Analysis of Fast Reactors with Improved Coarse Mesh Method (1994) (3)
Sensitivity and uncertainty analyses of reactivities for PWR cells with UO2 and MOX fuels (2016) (3)
DEVELOPMENT OF CALCULATION METHOD OF SENSITIVITIES FOR LIGHT WATER REACTORS (2013) (3)
Development of neutronics analysis technique for non-refueling core (Part 1:Critical experiment) (2005) (3)
Monte Carlo Based Diffusion Coefficients for LMFBR Analysis (2010) (3)
Disadvantage Factor in a Cell with Thin Moderator (1971) (3)
Effect of anisotropic scattering in neutronics analysis of BWR assembly (2006) (3)
Subgroup Parameters based on Orthogonal Factorization (2007) (3)
Radial diffusion coefficient in a cylindrical cell by P3 method (1973) (3)
A Complement Proposal for Optimization of Subgroup Parameters (2006) (3)
Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis (2002) (3)
Influence of Ca Concentration in (Ba,Ca)TiO3 Based Ceramics on the Reliability of MLCCs with Ni Electrodes (2010) (3)
Comparison of disadvantage factor among square, hexagonal, and cylindrical cells (1974) (2)
Analysis of root-mean-square temperature noise in fast reactor fuel assembly with local blockage (1982) (2)
Intercomparison of NEACRP's three-dimensional neutron transport benchmark problems (1991) (2)
Improvement of Neutronics Calculation Methods for Fast Reactors (Selected Papers of the Joint International Conference of Supercomputing in Nuclear Applications and Monte Carlo : SNA + MC 2010) (2011) (2)
Application of Improved Coarse Mesh Method to BWR Core Calculations (1980) (2)
Method Development for Calculating Minor Actinide Transmutation in a Fast Reactor (2015) (2)
Determination of Effective Diffusion Parameters in Thermal Reactor Assemblies (1980) (2)
Substantial Reduction of High Level Radioactive Waste by Effective Transmutation of Minor Actinides in Fast Reactors Using Innovative Targets (2012) (2)
New Uncertainty Reduction Method of Na Void Worth in Long-Life Small Fast Reactor (2004) (2)
Uncertainty Evaluation of Burnup Properties of Large Fast Reactors Using Data Adjustment Method (1991) (2)
Estimation of anisotropic effect of diffusion coefficient in a fast critical assembly (1974) (2)
Unified Diffusion Coefficient for Analysis of Sodium-Void Worth in Fast Critical Assembly with Control-Rod Channels (1981) (2)
Error Decomposition of Approximations for BWR Core Calculations (2002) (2)
Two-dimensional cell heterogeneity effect in analysis of fast critical assemblies (1988) (2)
Approximate Calculation Method for Second Order Sensitivity Coefficient (1994) (2)
Microscopic Reactor Physics. (1999) (2)
Development of transport code for hexagonal geometry : improved coarse-mesh SN calculation code HEXTR (1992) (2)
Evaluation of neutron streaming in fast breeder reactor fuel subassembly by double heterogeneous modeling (1989) (2)
Comparison of the Flat and Linear Source Variants of the Method of Characteristics (1999) (2)
ANALYSIS OF BOND DETERIORATION PROCESS IN REINFORCED CONCRETE MEMBER : (Part1) Analytical model, method, examples (1985) (2)
Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor (2012) (2)
Development of neutronic analysis technique for non-refueling core part 2: Method (2005) (2)
Development of Erbia-Credit Super-High-Burnup Fuel: Evaluation of Minimum Erbia Content for Criticality Safety Analyses (2012) (2)
Comparison of the Anisotropic Diffusion Coefficients Based on the Benoist and Deniz Formulas (1972) (2)
Some Nuclear Characteristics of Thorium Fueled Light Water Reactors (1988) (2)
Fast Reactor of Negative Na Void Reactivity and Its Transient Behavior (1994) (1)
TECHNICAL REPORT Application of Multiband Method to KUCA Tight-Pitch Lattice Analysis (1991) (1)
Burn up management strategy to design Ultra Long Life fast reactors (2013) (1)
Effective spatial homogenization with neutron leakage effect for FBR control rods. (1985) (1)
Development of Transport Code for Hexagonal Geometry (1992) (1)
Diffusion Calculation Model for Streaming Effects in Low Density Channels in LMFBRs (1989) (1)
Development of nodal Sn transport method in 3D hexagonal geometry (1997) (1)
A simple analytical method for evaluation of limit-cycle oscillation amplitude in boiling water reactors (1998) (1)
Sensitivity Analysis for Multiplication Factor Change of LWR Cell Caused by the Differences between JENDL-3.2 and JENDL-3.3 (2004) (1)
Development of Safety-Enhanced Fast Reactor by Using Minor Actinide Bearing Internal Blanket (2020) (1)
Prediction Uncertainty Analysis of Neutronic Properties of Fast Breeder Reactor by Use of Sensitivity-Based Methodology (1992) (1)
Development of an improved quasi-static transient analysis code based on three-dimensional Sn nodal transport theory for fast reactor (2020) (1)
Revisitation of the studies on covariance data and adjustment analysis: A tribute to M. Salvatores for his great works and remaining future tasks (2021) (1)
Dielectric Properties in the Insoluble Compositions of BaTiO3-CaTiO3 Ceramics (2008) (1)
Sensitivity Coefficients for Fast Reactor Core Analysis (2009) (1)
Spatial-harmonic Neutron Spectrum Effect on Frequency-domain Modal Analysis of Regional Stability in BWR (1999) (1)
Effect of Diffusion Coefficient Collapsing on Neutron Multiplication Factor (1974) (1)
Development of Erbia-Credit Super-High-Burnup Fuel: Assessment of Fuel Cycle Economics (2013) (1)
Analysis of temperature noise propagation in a large fuel subassembly of FBR (1986) (1)
ANALYSIS OF BOND DETERIORATION PROCESS IN REINFORCED CONCRETE MEMBER : (Part 3) Pullout of column reinforcement from joint under seismic loading (1986) (1)
An improved cell calculation method for liquid-metal fast breeder reactor blanket analysis (1988) (1)
A new method for generating group constants for analysis of blanket parameters of HCLWR with Monte Carlo method (1990) (1)
A new method for generating group constants for analysis of blanket parameters of HCLWR with Monte Carlo method (1990) (1)
Drift and Diffusion Coefficients for Asymmetric Cells of Fast Critical Assembly (1984) (1)
Burnup management simulator for small and medium sized reactors (2011) (1)
Effect of Neutron Leakage in Cell Calculations of Fast Critical Assembly (1981) (1)
EXPERIMENTAL AND ANALYTICAL STUDY ON INELASTIC BEHAVIOR OF THE RC COOLING TOWER MODEL SUBJECTED TO HORIZONTAL LOADS (1977) (1)
Effect of Number of Regions in Burnup Calculation for a Fast Reactor (1975) (1)
Intra-pellet neutron flux distribution measurements in LWR critical lattices (2013) (1)
Estimation of reactivity feedback and determination of safety criteria of inherent-safety fast reactors in unprotected transients based on the asymptotic approximation (2021) (1)
DEVELOPMENT OF A THREE-DIMENSIONAL KINETICS CODE FOR COMMERCIAL-SCALE FBR FULL CORE ANALYSIS. (2014) (1)
IMPROVEMENT TO THE CALCULATION OF COLLISION PROBABILITIES IN ANNULAR SYSTEM AND ITS APPLICATION TO CLUSTER GEOMETRY. (1971) (1)
Improvement of fitting method of multiband parameters for cell calculations (1997) (1)
2080) Study on Reinforced Concrete Members Subjected to the Alternate Plastic Deformation : Characteristics of Deflection of Reinforced Concrete Frames(Structure) (1963) (1)
Interference effect of neutron streaming between different fast critical assembly cells (1982) (1)
Analysis of the Main Steam Line Break Benchmark (Phase II) Using ANCK/MIDAC Code (2008) (1)
Present status of research activities on high conversion LWR in Japan. (1987) (1)
First-Flight Collision Probability in Cylindrical Cell System with Finite Height (1974) (1)
Analysis of Bond Deterioration Process in Reinforced Concrete Beam-Column Joints Subjected to Seismic Loading (1991) (1)
Development of new correlated sampling method in Monte Carlo theory (1997) (1)
Simulation of optical model covariance parameters with reduced uncertainty using representativity factor approach (2012) (1)
Evaluation of Prediction Error Reduction for Breeding Ratio by Bias Factor Method with Use of Experimental Result on Basic Reaction Rate Ratio (2008) (0)
Effect of Spatial Variation of Flux on Diffusion Coefficient of a Cylindrical Cell (1974) (0)
Application of the generalized collision probability to anisotropic diffusion coefficient calculation (1974) (0)
Burnup calculation code for cluster-type fuel lattices, BUNDLE (1977) (0)
Study of effective transmutation of minor actinides in heterogeneous light water reactors with various neutron spectra (1999) (0)
Measurement of Eigenvalue Separation in Coupled-Core Systems using Optical Fiber with Scintillator (2001) (0)
Preface of the “Symposium on Advances in Computational Methods of Nuclear Engineering” (2015) (0)
A Fast and Simplified Method to Calculate Exponential of Burnup Matrix (2007) (0)
Nuclear Education, Research and Development in Fukui Prefecture (2011) (0)
Optimization of moderated targets loading in LMFBR for minor actinides incineration (1999) (0)
Contribution of Reactor Physics in Past and Future ; Is Reactor Physics Useful? (2003) (0)
Development of Dielectric Materials Based on Multilayer Ceramic Capacitors for High Temperature Applications (2018) (0)
Inter-Comparison of Doppler Reactivity Coefficients for LWR UO2 and MOX Cells (2002) (0)
Minor Actinides Incineration by Loading Moderated Targets in Fast Reactor (2000) (0)
Optimization of axially heterogeneous fast reactor core with ZrH1.7 layer (1995) (0)
Sensitivity of Sodium Void Worth in Fast Reactors to Cross Sections (1986) (0)
2073) The Shearing Force Distribution Coefficients of Multi-Story Frame Analysis, Including Consideration of Shear Deformation of Beam-Column-Connective Zone (1965) (0)
Calculation of Doppler Reactivity Worth in Transient with Space Dependence of Self-shielding in Fuel Pellet. (1999) (0)
Development of a neutronics calculation method for designing commercial type Japanese sodium-cooled fast reactor (2012) (0)
Passive and Active Vibration Control of Structures Against Earthquake and Microvibration : Approach Towards Vibration Free Structures (1988) (0)
STRUCTURAL USE OF CAST-IN-SITU DIAPHRAM WALLS AT THE BASEMENT (1975) (0)
2) EXPERIMENTAL STUDY OF THE FULL-SIZED REINFORCED CONCRETE BEAMS SUBJECTED TO THE ALTERNATE LOADING (1962) (0)
Radiation Dose in a Reactor Service Area of the AP-1000 Based on the Fukushima Accident (2020) (0)
Design study of spectrum shifter region in research reactor by using the Kyoto University Critical Assembly (KUCA) (1997) (0)
The piezoelectric ceramic composition and piezoelectric ceramic device using the same (2001) (0)
ICONE15-10443 ERBIA-BEARING SUPER HIGH BURNUP FUEL : A PATHWAY FOR BREAKING 5WT% ENRICHMENT BARRIER IN LWR FUEL (2007) (0)
Study on the Minor Actinide Transmutation utilizing Monju Data (2016) (0)
Comparison of Cell Models for Analysis of Heterogeneous Fast Critical Assembly (1985) (0)
Effective Cross Section of 238U Samples for Analyzing Doppler Effect Measurements in Fast Critical Assembly (1997) (0)
Nuclear Reactor Safety and Human Resource Development (2015) (0)
ICONE15-10371 Application of Bias Factor Method with Use of Virtual Experimental Value to Prediction Uncertainty Reduction in Void Reactivity Worth of Breeding Light Water Reactor (2007) (0)
Transient Analysis of UO2 and MOX-Fueled Cores Based on Microscopic Reactor Physics (2008) (0)
APPLICATION OF THE JENDL-4.0 NUCLEAR DATA SET FOR UNCERTAINTY ANALYSIS OF THE PROTOTYPE FBR MONJU (2012) (0)
The piezoelectric ceramic composition (2001) (0)
Development of Inherent Safety Fast Reactor by Using Blanket Bearing Minor Actinides (2018) (0)
Improvement of Design Accuracy for Non-refueling Long-life Fast Reactor (2006) (0)
STUDIES OF DEFLECTION OF REINFORCED CONCRETE SLABS UNDER SUSTAINED LOADS (1986) (0)
Calculation of the Anisotropic Diffusion Coefficient (1972) (0)
ANALYSIS OF BOND DETERIORATION PROCESS IN REINFORCED CONCRETE MEMBERS : Part 2 Analysis of pullouts beam reinforcements in cruciform beam-column joint specimens subjected to seismic loading (1986) (0)
Coarse-Mesh Three-Dimensional Transport Calculation Method (1987) (0)
Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data (2019) (0)
Lnproved Few-group Coarse-mesh Methoa for Calculating Three-dimensional Power Distribution Fn Fast Breeder Reactor (1999) (0)
Sensitivity analysts of jendl library using fast reactor physics parameters (1986) (0)
A Proposal on the Thermal Stress Evaluation for the Reinforced Concrete Structures (1983) (0)
Development of 3-D FBR Heterogeneous Core Calculation Method Based on Characteristics Method (2002) (0)
Neutron Spectrum Calculation Code HARPY for Hexagonal Assembly (1993) (0)
Evaluation of streaming effect in an FBR fuel assembly by double heterogeneous modeling (1987) (0)
Education and Research of Nuclear Engineering in University of Fukui: Regional Collaborative Education and Research (2010) (0)
Optimal neutron spectrum for transmuting minor actinides in thermal reactors (1996) (0)
Advances in Nuclear Analytical System for Fast Reactor Cores. (1994) (0)
Analysis of temperature noise propagation in fast breeder core by the two-equation model (1989) (0)
Sensitivity and uncertainty analysis of reactivities for UO2 and MOX fueled PWR cells (2015) (0)
A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel (2009) (0)
Reactor Physics Producing Good Idea (2003) (0)
Synthesis method of integral type (1973) (0)
Development of power distribution calculation method in FBR assembly (1998) (0)
Analysis of root-mean-square temperature noise in FBR wire-spacered assembly with local blockage (1985) (0)
Development of three-dimensional transport and diffusion codes based on nodal method. (1986) (0)
An Improved Response Matrix Method and Its Verification by One-Dimensional Analysis on Fast Reactors (1976) (0)
Applicability of Constant Flux Approximation in Method of Characteristics with Filtering to Tiny Regions (2009) (0)
Accurate calculational method of multiband parameters for reactor cell calculation (1996) (0)
A safety enhanced sodium-cooled MOX fueled fast reactor core concept (2023) (0)
Calculational method error correlation effect in data adjustment for large LMFBFs (liquid metal fast breeder reactors) (1989) (0)
AN ATTROXIMATION METHOD OF STRESS ANALYSIS OF MULTISTORY FRAME SUBJECTED TO HORIZONTAL FORCE, INCLUDING CONSIDERATION OF SHEAR DEFORMATION OF BEAM-COLUMN-CONNECTIVE ZONE (1965) (0)
STUDY ON IMPROVEMENT OF EARTHQUAKE-RESISTANT BEHAVIORS OF REINFORCED CONCRETE COLUMN : Part 3 Equations for shear strength of columns with large ductility (1983) (0)
Estimation of Anisotropy of Diffusion Coefficient in a Fast Reactor (1976) (0)
Three-Dimensional Nodal Transport Theory Code and its Application (2001) (0)
Minor actinides burning fast reactor flexible to Pu mass balance (1998) (0)
Study on the flux tilt in a large fast reactor (1989) (0)
Effect of Anisotropic Scattering in UO2 and MOX Fueled LWR Cells and Cores (2005) (0)
Fast Reactors and Advanced Light Water Reactors for Sustainable Development (2012) (0)
Core and Fuel Design (From Mechanism to Structure) (2017) (0)
Extension of Fission Product Model for Use in Lattice Calculation of Thorium Fueled BWR (1983) (0)
Education and Research on Nuclear Engineering in Fukui Prefecture: 福井県の原子力はどうなるか (2014) (0)
Moderator Correction for a Wide Resonance by the Greuling-Goertzel Approximation (1971) (0)
Application of multiband S(sub n) method to fast reactor blanket analysis (1997) (0)
Determination of Cell Averaged Diffusion Constants Based on Transport/Diffusion Perturbation Theory (1987) (0)
RESEARCH ON REINFORCEMENT OF BEAM-COLUMN JOINT PANEL FOR SEISMIC RESISTANT REINFORCED CONCRETE FRAME : (Part 2) Bond test of deformed bar and it's analysis (1986) (0)
Application of Bias Factor Method with Use of Exponentiated Experimental Value to Prediction Uncertainty Reduction in Coolant Void Reactivity of Breeding Light Water Reactor (2008) (0)
Meaning and Safety of Pu-thermal Utilization (2002) (0)
Analysis of BWR power instability using spatial higher harmonics mode (1997) (0)
FISSION REACTORS/MATERIALS FOR NUCLEAR SYSTEMS (2013) (0)
Void reactivity evaluation by modified conversion ratio measurements in LWR critical experiments (2015) (0)
Neutronics and Core Design Studies on Fast Breeder Reactor (1989) (0)
Three-dimensional kinetic calculations with improved coarse-mesh method for fast reactors (1990) (0)
Development of Three-Dimensional Transport and Diffusion Codes Based on Nodal Method (1986) (0)
RESEARCH ON REINFORCEMENT OF BEAM-COLUMN JOINT PANEL FOR SEISMIC RESISTANT REINFORCED CONCRETE FRAME : Part1 Pullout of beam reinforcement from joint and deformation characteristics of beam end plastic hinge (1985) (0)
Effect of Nonuniform 3‐D Void Distribution Within BWR Fuel Assemblies on Neutronic Characteristics (2004) (0)
INELASTIC EARTHQUAKE RESPONSE OF MULTISTORY TRUSS STRUCTURE : Comparison between a Truss System and a Replaced Shear Vibration System (1968) (0)
Effect of Na void propagation to void reactivity in Fast Reactors with Sodium Plenum (2017) (0)
Activities on reactor theories and codes in Osaka University (1973) (0)
Development of three-dimensional nodal diffusion code based on group theory (1990) (0)
Minor Actinides Transmutation in Fast Reactors (2016) (0)
Three-dimensional transport effects in analyses of fast critical assemblies (1986) (0)
Development of Nuclear Uncertainty Reduction Methodology for Spent Fuel Pit using Critical Experimental Data (2020) (0)
2052) Indealization of the Plastic Deformation of Reinforced Concrete Beams Subjected to the Alternae Loading(Structure) (1962) (0)
Development of Er-SHB fuel : Critical experiments and analyses of homogeneously erbia-loaded cores in KUCA (2007) (0)
Development of Multilayer Ceramic Capacitors for High Temperature Applications (2010) (0)
Student Training Course Using the Experimental Fast Reactor Joyo and Related Facilities (2009) (0)
Asymptotic Neutron Distribution in a Finite Cylinder (1971) (0)
1 Nuclear data for Non-refueling core design (2006) (0)
Calculations of spatial higher modes without deflation procedure (1995) (0)
Study on higher actinides burning fast reactors (1991) (0)
Monte-Carlo/Collision Probability Hybrid Method for LWR Fuel Assembly Burnup Calculations (1995) (0)
Detailed calculations of minor actinide transmutation in a fast reactor (2015) (0)
Transient analysis of MOX-fueled cores based on microscopic reactor physics (2007) (0)
Supercomputer Applications in the Civil Engineering Field (1991) (0)
Improvement of three-dimensional nodal diffusion method (1999) (0)
Analytical Study of Ultimate Behavior of Underground LNG Storage Tanks Subjected to Both Thermal and Seismic Earth Pressure Load (1986) (0)
Treatment of Axial Buckling in a Fast Reactor (1974) (0)
ANALYTICAL STUDY ON ASEISMIC DESIGN OF BUILDINGS WITH ECCENTRICITY : Part-1 Damage distribution based on inelastic torsional response analyses (1985) (0)
Current Status of the Development Project on Erbia Credit Super High Burnup Fuel (2009) (0)
Trends of Fast Reactor Cycle Technology Development in the World No.1: Accelerating Fast Reactor Development : Start of Operation of Commercial Reactors in 2020 (2010) (0)
SENSITIVITY ANALYSIS OF MONJU USING ERANOS WITH JENDL-4.0 (2012) (0)
2098) On the Research of Preassembled Reinforced Concrete-III. For the Column(Structure) (1964) (0)
Spatially Dependent Self-Shielding Method with Temperature Distribution for LWR Lattice Physics Code PARAGON (2006) (0)

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