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J-GLOBAL ID：201301077743111927 Update date: Mar. 24, 2025

CHIBA Go

Affiliation and department：

Research field (1)： Nuclear engineering

Research theme for competitive and other funds (6)：

2024 - 2027 Development of fast and accurate advanced burnup and activation calculation method for nuclear safety
2022 - 2025 原子力発電プラント構造物の放射化計算のための革新的超高速計算フレームワーク
2016 - 2019 TM-EFP: an inovative numerical model for nuclear reactor transient analyses
2016 - 2019 Uncertainty quantification of reactor analysis method at design extension condition: A new estimation method based on covariance between input and prediction error
2012 - 2015 Uncertainty estimation of unmeasurable core safety parameters - a new approach using covariance matrix

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Papers (105)：

Cheol Ho Pyeon, Tomohiro Endo, Go Chiba, Kenichi Watanabe, Genichiro Wakabayashi. Nuclear education programs with reactor laboratory experiments at zero-powered research reactor facilities in Japan. Annals of Nuclear Energy. 2024. 204. 110531-110531
Akio YAMAMOTO, Tomohiro ENDO, Go CHIBA. Limited linear source approximation with Edge Detection for Convergence Stability of Method of Characteristics. Journal of Nuclear Science and Technology. 2024
Fuga Miyazawa, Go Chiba, Kosuke Tsujita, Shuhei Miwa. Computation time reduction of nuclear fuel burnup calculations with the predictor-corrector method using low-order model. Annals of Nuclear Energy. 2024. 195
Jun-Shuang Fan, Go Chiba. Reactor reactivity calculations with simplified-P₃ and perturbation theories. Journal of Nuclear Science and Technology. 2023
Japanese Evaluated Nuclear Data Library version 5: JENDL-5. Journal of Nuclear Science and Technology. 2023

MISC (148)：

Kenichi Tada, Akio Yamamoto, Tomohiro Endo, Go Chiba, Michitaka Ono, Masayuki Tojo. Development of Nuclear Data Processing CodeFRENDY Version 2. Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022). 2022. 107-116
Akio Yamamoto, Tomohiro Endo, Basma Foad, Go Chiba, Kenichi Tada. FRENDY/MG: a multi-group cross section generation module using ace pointwise cross sections. Proc. M&C 2021. 2021. 710-720
Go Chiba, Akio Yamamoto, Kenichi Tada, Tomohiro Endo. Multi-Group Cross Section Library Generation by FRENDY for Fast Reactor Neutronics Calculations. Transactions of the American Nuclear Society. 2021. 124. 556-558
Akio Yamamoto, Kenichi Tada, Go Chiba, Tomohiro Endo. Verification of the Multi-Group Generation Capability of FRENDY Nuclear Data Processing Code for Recent Nuclear Data through Comparison of One-group Reaction Rates. Transactions of the American Nuclear Society. 2021. 124. 544-547
清水亮輔, 千葉豪. Treatment of scattering sources in numerical calculations of the radiative transfer equation with discrete ordinates methods. 日本原子力学会春の年会予稿集(CD-ROM). 2021. 2021

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