Measurement of Flux Tilt and Eigenvalue Separation in axially Decoupled Core

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Reaction rate analysis of nuclear spallation reactions generated by 150, 190, and 235 MeV protons
Reaction Rate Analyses for an Accelerator-Driven System with 14MeV Neutrons in the Kyoto University Critical Assembly
Preliminary Experiments on Accelerator-Driven Subcritical Reactor with Pulsed Neutron Generator in Kyoto University Critical Assembly
A New Experimental Correction Method for the First-Order Perturbation Approximation in the Steady Subcritical Reactor
A Long and Slender Position-Sensitive Helium-3 Proportional Counter with an Anode Wire Supported by a Ladder-Shaped Solid Insulator
Application of Nodal Method to Lambda Mode Higher Harmonics Code
Development of Land Mine Detector System Based on the Measurements of Capture γ-Rays with Anticoincidence and Coincidence Methods
First Injection of Spallation Neutrons Generated by High-Energy Protons into the Kyoto University Critical Assembly
Static and Kinetic Experiments on Accelerator-Driven System with 14MeV Neutrons in Kyoto University Critical Assembly
Experiments and Analyses for Relationship between Flux Tilt in Two-Energy-Group Model and First-Mode Eigenvalue Separation
Determination of Lambda-Mode Eigenvalue Separation of a Thermal Accelerator-Driven System from Pulsed Neutron Experiment
A Proposal of Benchmark Calculation on Reactor Physics for Metallic Fueled and MOX Fueled LMFBR Based upon Mock-up Experiment at FCA
Experiments and Analyses on Sodium Void Reactivity Worth in Uranium-Free Fast Reactor at FCA
Measurement of Uranium-238 Doppler Effect in a Nitride Fueled LMFBR at FCA
High Temperature Doppler Effect Experiment for ^U at FCA, (II) Reaction Rate Measurement up to 2, 000℃ with a Foil Heated by Laser Exposure
High Temperature Doppler Effect Experiment for ^U at FCA, (I) Reactivity Worth Measurement with a Small Heated Sample up to 1, 500℃
Research Project on Accelerator-driven Subcritical System Using FFAG Accelerator and Kyoto University Critical Assembly
Reactor Noise Experiments by Using Acquisition System for Time Series Data of Pulse Train
Measurement of Flux Tilt and Eigenvalue Separation in axially Decoupled Core
Measurement and Analysis of ^Am Fission Rate Ratio Relative to ^U Fission Rate in Thermal Neutron Systems Using Kyoto University Critical Assembly
Measurement of^ Np Fission Rate Ratio Relative to ^U Fission Rate in Cores with Various Thermal Neutron Spectrum at the Kyoto University Critical Assembly
Rapid Estimation of Core-Power Ratio in Coupled-Core System by Rod Drop Method
Analysis of First-Harmonic Eigenvalue Separation Experiments on KUCA Coupled-Core
Reaction Rate Analysis of Nuclear Spallation Reactions Generated by 150, 190, and 235 MeV Protons
Assessment of ^Th Nuclear Data through Analysis of Thorium-loaded Critical Experiments in Thermal-Neutron Systems using the Kyoto University Critical Assembly
Measurement of Fuel Importance Distribution in Non-uniformly Distributed Fuel Systems
Experiments and Analyses on Sodium Void Reactivity Worth in Mock-up Cores of Metallic Fueled and MOX Fueled Fast Reactors at FCA
Nuclear Design Study on a Super High-burnup Fuel Assembly for Pressurized Water Reactors Using Transuranium
Analysis of Experiment on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
Experimental Study on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
Development of Land Mine Detector System Based on the Measurements of Capture γ-Rays with Anticoincidence and Coincidence Methods
Reaction Rate Analysis of Nuclear Spallation Reactions Generated by 150, 190, and 235MeV Protons
Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment
Application of a ^6LiF Small Neutron Detector with an Optical Fiber to Tritium Production Rate Measurement in D-T Neutron Fields
Feynman-α Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14MeV Neutron Source
Feynman-α Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14 MeV Neutron Source
A Novel Concept for Americium-containing Target for Use in Fast Reactors
Interpretation of Spatial Kinetics for Rod Drop Experiment in Loosely Coupled-Core Systems.
Temperature coefficient of reactivity in light-water moderated and reflected cores loaded with highly-enriched-uranium fuel.
Simple and Quick Measurement of Neutron Flux Distribution by Using an Optical Fiber with Scintillator.
Measurement of Reactivity Effect and Thermal Neutron Flux in Non-uniformly Distributed Fuel Assemblies.

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