Get started
Author

Hitoshi Kaguchi

Observed names: H Kaguchi, H. KAGUCHI, H. Kaguchi, Hitoshi KAGUCHI
OpenAlex ID: A5031968674
Front-end system of the TPE-RX reversed-field pinch machine
1999 · Y. Yagi, S. Sekine, et al. · Fusion Engineering and Design · 35
Advanced type stainless steel 316FR for fast breeder reactor structures
2003 · T. Nakazawa, H. Kimura, et al. · Journal of Materials Processing Technology · 22
Proposal of a new estimation method for the thermal ratchetting of a cylinder subjected to a moving temperature distribution
1993 · Hiroshida Wada, Hitoshi Kaguchi, et al. · Nuclear Engineering and Design · 18
Electromagnetic and structural analysis of thin-double-wall vacuum vessel with D-shape cross section of JT-60U
2003 · H. Kaguchi, K. Shimizu, et al. · IEEE/NPSS Symposium on Fusion Engineering · 7
Evaluation method for structural integrity assessment in core disruptive accident of fast reactor
2003 · Toshio Nakamura, Hitoshi Kaguchi, et al. · Nuclear Engineering and Design · 5
Fatigue crack propagation under cyclic thermal stress
1998 · H. Kaguchi, H. Koto, et al. · Materials at High Temperatures · 5
Applications of probabilistic fracture mechanics to FBR components
1993 · Kiminobu Hojo, Makoto Takenaka, et al. · Nuclear Engineering and Design · 5
Structural design and manufacturing of TPE-RX vacuum vessel
1999 · H Sago, J Orita, et al. · Fusion Engineering and Design · 3
Effect of Microstructure on Creep Fatigue Properties for Type 316 Austenitic Stainless Steels
1996 · Nobuhiro FUJITA, Takanori NAKAZAWA, et al. · 鐵と鋼 : 日本鐡鋼協會々誌 · 3
Evaluation of creep-fatigue design methods by structural failure tests under thermal loads
1995 · Masafumi Yamauchi, Hiroyuki Koto, et al. · Nuclear Engineering and Design · 3
Prediction of transient effects during early stages of creep crack growth
1994 · Grazia DJAVANROODI, H. KAGUCHI, et al. · Gruppo Italiano Frattura Digital Repository (Gruppo Italiano Frattura) · 3
Study on Metallography of Low Cycle Creep Fatigue Fracture of Type 316 Stainless Steels
1992 · Takanori Nakazawa, Nobuhiro Fujita, et al. · Springer eBooks · 3
Study on Fracture Mechanism and a Life Estimation Method for Low Cycle Creep-Fatigue Fracture of Type 316 Stainless Steels
1992 · Hideaki Kaneko, Toshio Sakon, et al. · Springer eBooks · 3
Design and fabrication of divertor base-plate for JT-60U
2002 · K. Ioki, K. Namiki, et al. · IEEE/NPSS Symposium on Fusion Engineering · 2
Benchmark study of creep-fatigue life predicted by elevated temperature design standards of every country
2001 · Takashi Shimakawa, Yoshihiko Tanaka, et al. · 2
Effects of Carbon Content and Chromium Segregation on Creep Rupture Properties of Low Carbon and Medium Nitrogen Type 316 Stainless Steel
1997 · Takanori NAKAZAWA, Nobuhiro FUJITA, et al. · 鐵と鋼 : 日本鐡鋼協會々誌 · 2
PDF
Development of slide support for JT-60U vacuum vessel
2002 · K. Takanabe, H. Kaguchi, et al. · IEEE/NPSS Symposium on Fusion Engineering · 1
Characteristics of a large reversed field pinch machine, TPE-RX
1998 · Yuji Yagi, Takahiro Shimada, et al. · 1
A simplified design method of piping subjected to thermal loads at elevated temperature
1997 · Hitoshi Kaguchi, Hiroshi Wada, et al. · NCSU Libraries Repository (North Carolina State University Libraries) · 1
Evaluation of fatigue properties of 316FR stainless steel welded joints at elevated temperature
1996 · Hitoshi Kaguchi, Hiroyuki Koto, et al. · 1
Fundamental Research on Creep-Fatigue Fracture of Type 316 Stainless Steel for Fast Breeder Reactors
1991 · Hitoshi Kaguchi · 1
Stress Corrosion Cracking Incidents and Repair Technologies on PWR Dissimilar Weld Metal Joints in Japan
2010 · Naoki Chigusa, Shinro Hirano, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
SB-03-2(100) Benchmark Study of Creep-Fatigue life Predicted by Elevated Temperature Design Standards of Every Country(Materials Performance in Nuclear Application 3) :
2001 · Takashi Shimakawa, Yoshihiko Tanaka, et al. · Creep : proceedings of the ... international conference on creep and fatigue at elevated temperatures
K-0802 Development of Structural Integrity Oriented Reliability Assessment System (SORE) For FBR MONJU (2) : Reactor Vessel
2001 · Hiromi SAGO, Hideo MACHIDA, et al. · The proceedings of the JSME annual meeting
PDF
Environmental Effect on Creep Fatigue Life of Type 316FR Stainless Steel in Liquid Sodium at Elevated Temperature
2001 · Hiroshi Ishikawa, Hitoshi Kaguchi, et al. · NCSU Libraries Repository (North Carolina State University Libraries)
PDF
Works count: 30
Citation count: 126
H-index: 5
I10-index: 3
Year
Topic
Type