スポンサーリンク
Department of Nuclear Energy, Graduate School of Engineering, Osaka University | 論文
- Extension of fission product model for use in lattice calculation of thorium fueled BWR.
- Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors
- Unified diffusion coefficient for analysis of sodium-void worth in fast critical assembly with control-rod channels.
- Effect of neutron leakage in cell calculations of fast critical assembly.
- Determination of effective diffusion parameters in thermal reactor assemblies.
- Monte-Carlo/Collision Probability Hybrid Method for LWR Fuel Assembly Burnup Calculations.
- Application of improved coarse mesh method to BWR core calculations.
- Application of depletion perturbation theory to fuel loading optimization.
- Approximate Calculation Method for Second Order Sensitivity Coefficient.
- Three-dimensional transport calculation method for eigenvalue problems using diffusion synthetic acceleration.
- Three-dimensional transport correction in fast reactor core analysis.
- Development of three-dimensional transport and diffusion codes based on nodal method.
- Fast Reactor of Negativ Na Void Reactiv and Its Transient Behavior.
- A New Nodal SN Transport Method for Three-Dimensional Hexagonal Geometry.
- Determination of cell averaged diffusion constants based on transport/diffusion perturbation theory.