Go Chiba 研究室

AI 要約（直近 5 年の研究成果）

※ AI（Claude）が、公開されている論文要旨から研究の問い・手法・主要な発見を事実情報として抽出・再構成して自動生成しています。誤りを含む可能性があるため、正確性は研究室公式情報でご確認ください。

研究成果（41 件）

• [2026] Comparison of cost-reduced computational methods for nuclide transmutation problems
  DOI: https://doi.org/10.1080/00223131.2025.2611407
• [2026] Uncertainty propagation calculation from model parameters in thermal scattering of H-1 bound in H ₂ O to neutronics parameters with deterministic sampling method and sandwich formula
  DOI: https://doi.org/10.1080/00223131.2026.2693273
• [2025] Correction Method of Few-Group Cross Sections for Core Analysis of High-Temperature Gas-Cooled Reactors
  DOI: https://doi.org/10.13182/mc25-47343
• [2025] Revisiting mini-max polynomial approximation method for nuclear fuel depletion calculation
  DOI: https://doi.org/10.1016/j.anucene.2025.111948
• [2025] Burnup calculation using POD-based neutron spectrum reconstruction
  DOI: https://doi.org/10.1080/00223131.2025.2560559
• [2025] Fast Burnup Calculation Method Based on Neutron Spectrum Reconstruction with Proper Orthogonal Decomposition and Regression Model
  DOI: https://doi.org/10.13182/mc25-46817
• [2025] Nuclear data sensitivity analysis on LWR nuclear fuel depletion with the modern evaluated nuclear data libraries
  DOI: https://doi.org/10.1080/00223131.2025.2486807
• [2025] Preliminary Investigation of Dancoff Factor Treatment in Application of Direct Coupling Code System Using FRENDY Version 2 and GENESIS on Three-Dimensional LWR Fuel Assembly Problem
  DOI: https://doi.org/10.13182/mc25-47476
• [2024] Verification of Neutronics Analysis Method Using CBZ and GENESIS for a Prismatic High-Temperature Gas-Cooled Reactor
  DOI: https://doi.org/10.13182/physor24-43456
• [2024] Neutron Shielding Calculation with the ACE-FRENDY-CBZ Sequence
  DOI: https://doi.org/10.13182/physor24-43507

科研費（0 件）

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所属学会・役職（0 件）

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