Nuclear Design Study on a Super High-burnup Fuel Assembly for Pressurized Water Reactors Using Transuranium

スポンサーリンク

概要

• 論文の詳細を見る
• Atomic Energy Society of Japanの論文
• 1997-07-25

著者

• SHIROYA Seiji

  Research Reactor Institute, Kyoto University

• Shiroya S

  Nuclear Engineering Science Division Research Reactor Institute Kyoto University

• Shiroya S

  Nuclear Energy Science Division Reserch Ractor Institute Kyoto University

• Shiroya S

  Research Reactor Institute Kyoto University

• Shiroya S

  Kyoto Univ.

• Shiroya S

  Kyoto Univ. Osaka

• Shiroya Seiji

  Nuclear Engineering Science Division Research Reactor Institute Kyoto University

• Shiroya Seiji

  Research Reactor Institute Kyoto University

• Kanda K

  Kyoto Univ.

• Kanda Keiji

  Research Reactor Institute Kyoto University

• MORI Masaaki

  Nuclear Engineering, Ltd.

• Shiroya Seiji

  Nuclear Energy Science Division Reserch Ractor Institute Kyoto University

• KOBAYASHI Katsutoshi

  Japan Atomic Energy Research Institute

• Katsuhei Kobayashi

  Research Reactor Institute Kyoto University

• Kobayashi Katsuhei

  Research Reactor Institute Kyoto University

• HIJIYA Masayuki

  Nuclear Engineering, Ltd.

• Mori M

  Tokyo Electric Power Co.

• Hijiya Masayuki

  Nuclear Engineering Limited

• Hijiya Masayuki

  Nuclear Engineering Ltd.

• Mori Masaaki

  Nuclear Engineering Limited (nel)

• KANDA Keiji

  Research Laboratory of Nuclear Reactor, Tokyo Institute of Technology

関連論文

• 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
• Development of Land Mine Detector System Based on the Measurements of Capture γ-Rays with Anticoincidence and Coincidence Methods
• Derivation of Optimum Polar Angle Quadrature Set for the Method of Characteristics Based on Approximation Error for the Bickley Function
• 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
• 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 the Effective Neutron Capture Cross Section of Cesium-134 by Triple Neutron Capture Reaction Method
• Measurement of Thermal Neutron Cross Section and Resonance Integral of the Reaction ^Cs (n, γ) ^Cs
• Measurement of Neutron Capture Cross Section of ^Np from 0.02 to 100eV
• 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
• Nuclear Design Study on a Super High-burnup Fuel Assembly for Pressurized Water Reactors Using Transuranium
• 冷中性子ラジオグラフィ-を用いたLi1.33Ti1.67O4中のリチウムイオンの動きの解析
• 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
• 中性子ラジオグラフィによるリチウム電池内におけるリチウム元素分布の可視化〔英文〕
• Involvement of Cytocalbin (Cytoskeleton-Related Calmodulin-Binding Protein) on the Cytoskeletal Regulation
• Measurements of Neutron-induced Fission Cross Section of Protactinium-231 from 0. 1eV to 10keV with Lead Slowing-down Spectrometer and at 0. 0253eV with Thermal Neutron Facility
• Measurements of Neutron-induced Fission Cross Section of Americium-243 from Thermal Neutron Energy to 15keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility
• Development of Hybrid Core Calculation System using Two-dimensional Full-Core Heterogeneous Transport Calculation and Three-dimensional Advanced Nodal Calculation
• Neutron Capture Cross Section Measurement of Praseodymium in the Energy Region from 0.003eV to 140keV
• Measurement of Neutron Capture Cross Section of ^Np by Linac Time-of-Flight Method and with Linac-driven Lead Slowing-down Spectrometer
• Application of BGO Scintillators to Absolute Measurement of Neutron Capture Cross Sections between 0. 01 eV and 10 eV
• 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
• Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors
• Production of Pure ^Pu Tracer for the Assessment of Plutonium in the Environment
• Cross Sections of Charge Transfer between Uranium Atoms and Ions Produced by Autoionization
• Reduction of Charge Transfer Loss in Atomic Laser Isotope Separation by Production of Excited Ions through Autoionization Levels
• Measurement of Neutron Flux Spectrum by Multi-Foil Activation Method at the Central Graphite Cavity of UTR-KINKI
• Comparison between Equilibrium Cycle and Successive Multicycle Optimization Methods for In-Core Fuel Management of Pressurized Water Reactors
• Huma Melanoma Treated by Boron Neutron Capture Therapy: Comparison of the Clinical Response with the Predicted Response
• Effects of Neutron Resonance Interference between Ta and Au
• Application of a ^6LiF Small Neutron Detector with an Optical Fiber to Tritium Production Rate Measurement in D-T Neutron Fields
• Flux Distribution in Phantom for Biomedical Use of Beam-Type Thermal Neutrons
• Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors
• Neutron Capture Cross Section Measurement of Praseodymium in the Energy Region from 0.003eV to 140keV
• A Remark on the Integral Measurement of Thermal Neutron Spectra
• Effect of (.GAMMA.,n) reactions of heavy water moderator on beam quality in biomedical irradiation facility.
• Application of Neutron Radiography to Visualization and Void Fraction Measurement of Air-Water Two-Phase Flow in a Small Diameter Tube.
• 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.
• Phantom experiment and analysis for in vivo measurement of boron-10 concentrations in melanoma for boron neutron capture therapy.
• Measurement of Reactivity Effect and Thermal Neutron Flux in Non-uniformly Distributed Fuel Assemblies.

もっと見る 閉じる

スポンサーリンク