スポンサーリンク
Mitsubishi Atomic Power Industries, Inc. | 論文
- Analysis of the Main Steam Line Break Benchmark (Phase II) Using ANCK/MIDAC Code
- Analysis of Core Physics Experiments on Fresh and Irradiated BR3 MOX Fuel in REBUS Program
- The Verification of 3 Dimensional Nodal Kinetics Code ANCK Using Transient Benchmark Problems
- Plasma Shapes for Achieving High Heating Efficiency during Neutral Beam Injection in Doublet III
- Development of Discrete Ordinates Transport Code in Three-Dimensional (R, θ, Z) Geometry for Shielding Design
- Development of Discrete Ordinates SN Code in Three-Dimensional (X, Y, Z) Geometry for Shielding Design
- A Numerical Study on Application of Benoists Anisotropic Diffusion Coefficients
- Development of a Simulation-Based Intelligent Tutoring System for Assisting PID Control Learning (Special Issue on Intelligent CAI and Hypermedia)
- Effect of Higher-Harmonic Flux in Exponential Experiment for Subcriticality Measurement
- Control rod worth in high conversion PWR.
- Nuclear safety analysis of a molten salt breeder reactor.
- Effect of barriers on sodium mist deposition on LMFBR components.
- Behavior of Cladding Tube under Coolant-Loss Accident Conditions