Kunio Onizawa

发表

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

Shinobu Yoshimura, Yinsheng Li, Hiroto Itoh, 2012 .

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T0 Under Various Selections of Temperature Conditions

Masato Yamamoto, Naoki Miura, Kunio Onizawa, 2014 .

Improvements to a probabilistic fracture mechanics code for evaluating the integrity of a RPV under transient loading

Yinsheng Li, Kunio Onizawa, Katsuyuki Shibata, 2001 .

Finite element analysis of the ductile fracture behavior of nuclear piping with circumferentially through-wall crack.

Takayuki Watanabe, Genki Yagawa, Kunio Onizawa, 1988 .

JAEA Research Program on the Assessment of Structural Integrity of Reactor Pressure Vessels for Safe Long-term Operation

Jinya Katsuyama, Yutaka Nishiyama, Kunio Onizawa, 2012 .

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects

William Server, Naoki Miura, Tapio Planman, 2009 .

Probabilistic Evaluation of Current Structural Integrity Assessment Method for Reactor Pressure Vessel Using PASCAL ver. 2

Kazuya Osakabe, Kunio Onizawa, Katsuyuki Shibata, 2007 .

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

Hiroto Itoh, Kunio Onizawa, Hiroyuki Nishikawa, 2010 .

International Round Robin Test on Master Curve Reference Temperature Evaluation Utilizing Miniature C(T) Specimen

Naoki Miura, M. Valo, Kunio Onizawa, 2014 .

Examination of Flaw Acceptance Standard in JSME Fitness for Service Rule Based on Failure Probability

Shinobu Yoshimura, Kunio Onizawa, Katsuyuki Shibata, 2003 .

Structural Integrity Evaluation of Reactor Pressure Vessels During PTS Events Using Deterministic and Probabilistic Fracture Mechanics Analysis

Jinya Katsuyama, Kazuya Osakabe, Kunio Onizawa, 2013 .

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: First Round Robin Test on Uniform Specimens of Reactor Pressure Vessel Material

Naoki Miura, Kunio Onizawa, Naoki Soneda, 2012 .

Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During PTS Events

Jinya Katsuyama, Kunio Onizawa, Koichi Masaki, 2012 .

Prediction of Collapse Stress for Pipes With Arbitrary Multiple Circumferential Surface Flaws

Kunio Hasegawa, Yinsheng Li, Nathaniel G. Cofie, 2010 .

Benchmark Analysis on Probabilistic Fracture Mechanics Analysis Codes Considering Multiple Cracks and Crack Initiation in Aged Piping of Nuclear Power Plants

Shinobu Yoshimura, Yinsheng Li, Jinya Katsuyama, 2014 .

Development of Seismic Load Evaluation Code for Evaluating Structural Reliability of Nuclear Components

Kunio Onizawa, Masahide Suzuki, Hideharu Sugino, 2006 .

Study on Structural Integrity Assessment of Reactor Pressure Vessel Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses

Jinya Katsuyama, Yutaka Nishiyama, Kunio Onizawa, 2014 .

Final Results of an Analytical Round Robin Exercise to Support Constraint Effects

Naoki Miura, Shengjun Yin, Kunio Onizawa, 2009 .

Alternative Reference Temperature Based on Master Curve Approach in Japanese Reactor Pressure Vessel Steel

Kunio Onizawa, Takashi Hirano, Takatoshi Hirota, 2013 .

Overview of Reliability Test Program on Primary Coolant Piping of Light Water Reactors.

Kunio Onizawa, Katsuyuki Shibata, Ryoichi Kurihara, 1993 .

Estimation of Through-Wall Cracking Frequency of RPV Under PTS Events Using PFM Analysis Method for Identifying Conservatism Included in Current Japanese Code

Jinya Katsuyama, Kazuya Osakabe, Kunio Onizawa, 2014 .

K-0806 Development of PFM Code with a Function of Ductile Crack Extension Analysis : Part2: Sensitivity Analysis using the Ductile Crack Extension Analysis Function of PASCAL

Yinsheng Li, Kunio Onizawa, Katsuyuki Shibata, 2001 .

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 .

Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

Yinsheng Li, Jinya Katsuyama, Yutaka Nishiyama, 2014 .

Improvements to PFM Analysis Code PASCAL and Some Case Studies on RPV Integrity During Pressurized Thermal Shock

Kazuya Osakabe, Kunio Onizawa, Katsuyuki Shibata, 2006 .

Research and development related to PFM for aged nuclear components

Genki Yagawa, Kunio Onizawa, Katsuyuki Shibata, 2002 .

Benchmark Analysis on the Failure Probability Assessment of Piping With Stress Corrosion Cracks

Kunio Onizawa, Hideo Machida, Manabu Arakawa, 2011 .

Study on Flaw Acceptance Standard of ASME Code Sec. XI Based on Failure Probability

Shinobu Yoshimura, Yasuhiro Kanto, Kunio Onizawa, 2004 .

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 .

Technical issues for life evaluation of light water reactor components.

Kunio Onizawa, Nobuya Nakajima, Masahide Suzuki, 1991 .

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

Jinya Katsuyama, Hiroto Itoh, Kunio Onizawa, 2008 .

Summary of International PFM Round Robin analyses among Asian Countries on reactor pressure vessel integrity during pressurized thermal shock

Myung Jo Jhung, Shinobu Yoshimura, Kunio Onizawa, 2012 .

Recent Japanese research activities on probabilistic fracture mechanics for pressure vessel and piping of nuclear power plant

Shinobu Yoshimura, Kunio Onizawa, Hideo Machida, 2010 .

Development of PFM Code with a Function of Ductile Crack Extension Analysis.

Yinsheng Li, Kunio Onizawa, Katsuyuki Shibata, 2003 .

OS0813 Technical Review of Structural Integrity Assessment Procedure on Reactor Pressure Vessel (1) : Comparison of Procedures in Japan and U.S. and Study on the Postulated Flaw

Jinya Katsuyama, Kazuya Osakabe, Kunio Onizawa, 2012 .

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens — 2nd Report: Fracture Toughness Comparison in Specified Loading Rate Condition

Masato Yamamoto, Naoki Miura, Kunio Onizawa, 2013 .

Results of reliability test program on light water reactor piping

Kunio Onizawa, Katsuyuki Shibata, Ryoichi Kurihara, 1994 .

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL2 for Reactor Pressure Vessel Focusing on Weld-Overlay Cladding

Kunio Onizawa, Hiroyuki Nishikawa, 2011 .

Study on Application of PFM Analysis Method to Japanese Code for RPV Integrity Assessment Under PTS Events

Shinobu Yoshimura, Jinya Katsuyama, Kazuya Osakabe, 2015 .

Effects of chemical composition and dose on microstructure evolution and hardening of neutron-irradiated reactor pressure vessel steels

Kunio Onizawa, Yasuyoshi Nagai, Takeshi Toyama, 2010 .

Development of Probabilistic Fracture Mechanics Analysis Code PASCAL ver. 2 for Reactor Pressure Vessel

Kazuya Osakabe, Kunio Onizawa, Katsuyuki Shibata, 2007 .

Effect of Welding Conditions on Residual Stress and SCC Behavior at Butt-Welding Joints of Recirculation Pipes

Jinya Katsuyama, Kunio Onizawa, J. Katsuyama, 2008 .

Study on PWSCC Behaviors at Nickel-Based Alloy Welds Based on Weld Residual Stress Analysis and Probabilistic Fracture Mechanics

Jinya Katsuyama, Kunio Onizawa, Makoto Udagawa, 2010 .

Analytical Study of the Relaxation of Welding Residual Stress by Excessive Loading for Austenitic Stainless Steel Piping Welds

Jinya Katsuyama, Kunio Onizawa, 2009 .

Experimental Study of the Effect of Radiation Exposure to Concrete.

Kunio Onizawa, Masahide Suzuki, Kazushige Fujiwara, 2009 .

Prediction of residual stress distributions due to surface machining and welding and crack growth simulation under residual stress distribution

Jinya Katsuyama, Kunio Onizawa, Masahito Mochizuki, 2011 .

Effect of Welding Conditions on Residual Stress and Stress Corrosion Cracking Behavior at Butt-Welding Joints of Stainless Steel Pipes

Jinya Katsuyama, Kunio Onizawa, Tohru Tobita, 2012 .