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Nuclear Fuel Industries, ltd. | 論文
- Lattice Physics Analysis of Measured Rod-by-Rod FP Inventory Distributions of Burnt BWR 9 × 9 UO_2 Assemblies
- Irradiated Behavior at High Burnup for HiFi Alloy
- Out-of-pile Tests of Simulated Rock-like Oxide(ROX)Fuels
- Analysis of Core Stability Measurement Data of Advanced 9×9 Fuel Assembly in a BWR Core
- Improvement of Corrosion Resistance of Vanadium Alloys in High-Temperature Pressurized Water
- Estimation of the Doppler Coefficient from a Lower Power Transient Observed in a Zero-Power Reactor Physics Test of a PWR (I) : Methodology
- Estimating Temperature Reactivity Coefficients by Experimental Procedures Combined with Isothermal Temperature Coefficient Measurements and Dynamic Identification
- Improvement of the SPH Method for Pin-by-Pin Core Calculations
- Fuel and Fission Gas Behavior during Rise-to-Power Test of the High Temperature Engineering Test Reactor(HTTR)
- A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel
- Benchmark Problem Suite for Reactor Physics Study of LWR Next Generation Fuels
- Theoretical Basis for Measuring Small Radon Diffusion Coefficients for a Radium-Bearing Porous Material Generated by Precipitation of Iron (III) Hydroxide
- Transient-Diffusion Measurements of Radon : Fick's Law Confirmation and ^Po/^Po Behavior Determination
- Transient-Diffusion Measurements of Radon : Practical Interpretation of Measured Data
- Sensitivity Analysis for Multiplication Factor Change of LWR Cell Caused by the Differences between JENDL-3.2 and JENDL-3.3
- Post-Dryout Heat Transfer Analysis Model with Droplet Lagrangian Simulation(International Conferences on Power and Energy)
- The Effect of Mixing-vane Arrangements in a Subchannel Turbulent Flow
- Improvement of Spatial Discretization Error on the Semi-analytic Nodal Method Using the Scattered Source Subtraction Method
- Advanced PWR Core Calculation Based on Multi-group Nodal-transport Method in Three-dimensional Pin-by-Pin Geometry
- Effect of Heat Treatment on TEM Microstructures of Zirconium Carbide Coating Layer in Fuel Particle for Advanced High Temperature Gas Cooled Reactor