スポンサーリンク
社団法人 日本原子力学会 | 論文
- A Novel Method for Solving Lithium Carbonate Pellet by Binary-Acid for Tritium Production Rate Measurement by Liquid Scintillation Counting Technique
- The Effect of Annealing Parameter on Corrosion Resistance of Zircaloy-2
- Design Studies of an Epithermal Neutron Beam for Neutron Caputure Therapy at the Musashi Reactor
- Numerical Simulation of Turbulent Shear Flow Using Higher Order Taylor Series Expansion Method
- Radical Formation of Lithium Lactate for ESR Dosimetry
- Identification of Transfer Functions in Feedback System and Inverse Problem
- INSIGHT : An Integrated Scoping Analysis Tool for In-core Fuel Management of PWR
- Numerical Study on Identification of Transfer Functions in a Feedback System and Model Reduction
- Identification of Transfer Functions in Non-square Feedback Systems
- Void Swelling of Proton Irradiated Fe-15Cr-20Ni Ternary Alloy
- Package Flow Model and Its Fuzzy Implementation for Simulating Nuclear Reactor System Dynamics
- High Enrichment of Uranium and Rare Earth Elements in Ionic Salt Bath by Countercurrent Electromigration
- Sensitivities of Some Characteristics of Nuclear Equilibrium State to One-Group Constants
- Preparation of Acid Deficient Solutions of Uranyl Nitrate and Thorium Nitrate by Steam Denitration
- New Sampling Method in Continuous Energy Monte Carlo Calculation for Pebble Bed Reactors
- Radiation Dosimeters for High Dose by Commercial PMOS Transistors Using Normalized Drain Current as Dosimetric Parameter
- Application of Multi-Capillary Fiber to Neutron Microguide Tube
- Evaluation of Covariance Data for Chromium, Iron and Nickel Contained in JENDL-3. 2
- Nonlinear Fracture Mechanics Analysis of Surface Crack Propagation in Fusion Reactor First Wall by Cyclic High Heat Flux Irradiation
- Densification and Swelling in UO_2 Pellets under Hydrostatic Pressure Condition