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社団法人 日本原子力学会 | 論文
- An Algorithm for Attenuation of Turbulence in Particulate Flow Linked to the Fluid-dynamic Code COMMIX-M
- Development of Monte Carlo Machine for Particle Transport Problem
- Application of a Refined Emergency Code System SPEEDI to Atmospheric Field Experiments Conducted over a Complex Terrain
- Matrix-Type Multiple Reciprocity Boundary Element Method for Solving Three-Dimensional Two-Group Neutron Diffusion Equations
- Three-Dimensional Isoparametric Boundary Element Method for Solving Neutron Diffusion Equations
- Benchmarking Studies of Probabilistic Fracture Mechanics Analysis Code, PROFMAC-II, for Assessing Pressurized Thermal Shock Events of Reactor Pressure Vessel Integrity Issues
- Use of Sobol's Quasirandom Sequence Generator for Integration of Modified Uncertainty Importance Measure
- Measurement Technique of Boron Isotopic Ratio by Laser-induced Breakdown Spectroscopy
- Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
- Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particles
- Calculational Method of One-Group Nuclear Constants in Nuclear Equilibrium State
- Numerical Solution of Argon 36-38-40 Concentration Profiles within Thermal Diffusion Column
- A Fast Prediction of Plant Behaviour in the Steam Generator Tube Rupture Accident at Mihama Unit 2 Using a Similar Case
- Dissolution of Haematite in Mixtures Containing Different Chelating and Reducing Agents
- Self-Triggering Mechanism of Vapor Explosions for a Molten Tin and Water System
- Self-Triggering Mechanism of Vapor Explosions for the Large-Scale Experiments Involving Fuel Simulant Melt
- The Behavior of Pressurized Gas Injected into Liquid between Horizontal Disks Front Velocity and Bubble Shape
- Effects of Organic Solvent on Infinite Neutron Multiplication Factor of Homogeneous Plutonium Nitrate Solution System
- Transient Behavior of Low Enriched Uranium Silicide Miniplate Fuel under a Triplet Configuration
- Transient Behavior of Low Enriched Uranium Silicide and Aluminide Miniplate Fuel for Research Reactors