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In-core Fuel Management Department, Tepco Systems Corp. | 論文
- Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores
- Nonlinear Behavior under Regional Neutron Flux Oscillations in BWR Cores
- Spatial-harmonic Neutron Spectrum Effect on Frequency-domain Modal Analysis of Regional Stability in BWR
- Development an Verification of and Efficient Spatial Neutron Kinetics Method for Reactivity-Initiated Event Analyses
- Transport Theory Calculation for a Heterogeneous Multi-Assembly Problem by Characteristics Method with Direct Neutron Path Linking Technique