Hiroto Itoh

发表

Benchmark analysis on PFM analysis codes for aged piping of nuclear power plants

Shinobu Yoshimura, Yinsheng Li, Hiroto Itoh, 2012 .

Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress

Hiroto Itoh, Kunio Onizawa, Hiroyuki Nishikawa, 2010 .

Source term uncertainty analysis: probabilistic approaches and applications to a BWR severe accident

Yu Maruyama, Hiroto Itoh, Xiaoyu Zheng, 2015 .

Benchmark analysis and numerical investigation on probabilistic fracture mechanics analysis codes for NPPs piping

Shinobu Yoshimura, Yinsheng Li, Hiroto Itoh, 2012 .

User's Manuals of Probabilistic Fracture Mechanics Codes PASCAL-SC and PASCAL-EQ

Hiroto Itoh, Kunio Onizawa, Katsuyuki Shibata, 2005 .

Benchmark analysis on probabilistic fracture mechanics analysis codes concerning fatigue crack growth in aged piping of nuclear power plants

Shinobu Yoshimura, Yinsheng Li, Jinya Katsuyama, 2014 .

A Probabilistic Evaluation Model for Welding Residual Stress Distribution at Piping Joint in Probabilistic Fracture Mechanics Analysis

Jinya Katsuyama, Hiroto Itoh, Kunio Onizawa, 2008 .

Influence of In-Vessel Melt Progression on Uncertainty of Source Term During a Severe Accident

Yu Maruyama, Hiroto Itoh, Xiaoyu Zheng, 2014 .

Estimation of Source Term Uncertainty in a Severe Accident With Correlated Variables

Yu Maruyama, Hiroto Itoh, Xiaoyu Zheng, 2014 .

Application of Bayesian nonparametric models to the uncertainty and sensitivity analysis of source term in a BWR severe accident

Yu Maruyama, Kenji Kawaguchi, Hiroto Itoh, 2015, Reliab. Eng. Syst. Saf..