第 1 回 原子力機器健全性国際ワークショップ 関連投稿論文
May 8, 1996, Taejon, Korea


K Kashima, N Miura, S Kanno, K Miyazaki, M Ishiwata, N Gotoh, “A research program fordynamic fracture evaluation of Japanese carbon steel pipes,” Nuclear Engineering and Design,174, pp. 33-39, (1997).

Masanori Kikuchi, “Study on the effect of the crack length on the JIC value,” Nuclear
Engineering and Design, 174, pp. 41-49, (1997).

Katsuyuki Shibata, “Progress of LWR structural safety research at JAERI,” Nuclear
Engineering and Design, 174, pp. 79-90, (1997).

G Yagawa, S Yoshimura, N Soneda, M Hirano, “Probabilistic fracture mechanics analyses ofnuclear pressure vessels under PTS events,” Nuclear Engineering and Design, 174, pp. 91-100,(1997).

第 2 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 20-21, 1998, Tokyo, Japan

Koji Koyama, Itaru Muroya, Toshihiko Tanaka, Takao Nakamura, “Low alloy steel piping testfor fracture criteria of leak before break,” Nuclear Engineering and Design, 191, pp. 147-156,(1999).

Jun Matsumoto, “Core shroud replacement of Fukushima-Daiichi Unit #3,” NuclearEngineering and Design, 191, pp. 167-175, (1999).

N. Miura, “Approximate evaluation method for ductile fracture analysis of a circumferentiallythrough-wall-cracked pipe subjected to combined bending and tension,” Nuclear Engineeringand Design, 191, pp. 177-194, (1999).

Katsumasa Miyazaki, Satoshi Kanno, Masayuki Ishiwata, Kunio Hasegawa, Soek Hwan Ahn,
Kotoji Ando, “Fracture behavior of carbon steel pipe with local wall thinning subjected tobending load,” Nuclear Engineering and Design, 191, pp. 195-204, (1999).

Yonezou Tujikura, Shigeru Urata, “Fracture mechanics evaluation of cast duplex stainless steel
after thermal aging,” Nuclear Engineering and Design, 191, pp. 255-261, (1999).

Genki Yagawa, Yasuhiro Kanto, Shinobu Yoshimura, “Probabilistic fracture mechanics ofnuclear structural components: consideration of transition from embedded crack to surface
crack,” Nuclear Engineering and Design, 191, pp. 263-273, (1999).

第 3 回 原子力機器健全性国際ワークショップ 関連投稿論文
October 11-12, 2000, Taoyuan, Taiwan
Noriyoshi Maeda, Shinichi Nakagawa, Genki Yagawa, Shinobu Yoshimura, “Optimization ofoperation and maintenance of nuclear power plant by probabilistic fracture mechanics,”

Nuclear Engineering and Design, 214, pp. 1-12, (2002).
Kiyoshi Takanabe, Takashi Miyake, Yasumi Nagura, “Development of advanced CRDM
without canopy seal welds,” Nuclear Engineering and Design, 214, pp. 25-34, (2002).

Shigeko Nomoto, Takao Nakamura, “Improvement of the strain concentration factor forsimplified elastic–plastic analysis,” Nuclear Engineering and Design, 214, pp. 41-45, (2002).

Kei Kobayashi, “Aseismic evaluation for aging degradation of nuclear power plantcomponents,” Nuclear Engineering and Design, 214, pp. 57-71, (2002).

Katsuyuki Shibata, Kunio Onizawa, Daisuke Kato, Yinsheng Li, Genki Yagawa, “Research anddevelopment related to PFM for aged nuclear components,” Nuclear Engineering and Design,
214, pp. 113-126, (2002).

Katsumasa Miyazaki, Akira Nebu, Masayuki Ishiwata, Kunio Hasegawa, “Fracture strength andbehavior of carbon steel pipes with local wall thinning subjected to cyclic bending load,”
Nuclear Engineering and Design, 214, pp. 127-136, (2002).

Hideo Kobayashi, Koichi Kashima, “Japanese fitness-for-service code for nuclear power
plants—summary of flaw evaluation procedures,” Nuclear Engineering and Design, 214, pp.
147-149, (2002).

第 4 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 15-16, 2002, Cheju, Korea
第 5 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 21-22, 2004, Kyoto, Japan

Katsuyuki Shibata, Yasuhiro Kanto, Shinobu Yoshimura, Genki Yagawa, “Recent Japanese
Probabilistic Fracture Mechanics Researches Related to Failure Probability of Aged RPV,”
Solid State Phenomena, 120, pp. 49-67, (2007).

Kunio Hasegawa, Hiroaki Tamako, Katsumasa Miyazaki, “Allowable Subsurface Flaws
Located Near Vessel Surface in JSME Code,” Solid State Phenomena, 120, pp. 77-84, (2007).

Naoki Miura, Katsumasa Miyazaki, Masakazu Hisatsune, Kunio Hasegawa, Koichi Kashima,“Ductile Fracture Behaviour of Class 2 and 3 LWR Piping and Its Implications for Flaw
Evaluation Criteria,” Solid State Phenomena, 120, pp. 85-94, (2007).

Yoshihiro Isobe, Mitsuyuki Sagisaka, Shinobu Yoshimura, Genki Yagawa, “EconomicEvaluation of Maintenance Strategies for Steam Generator Tubes Using Probabilistic Fracture
Mechanics and a Financial Method,” Solid State Phenomena, 120, pp. 119-126, (2007).

Masayuki Kamaya, Toshihisa Nishioka, “Finite Element Alternating Method for Interacting
Surface Cracks,” Solid State Phenomena, 120, pp. 147-153, (2007).



Hitohsi Kaguchi, Koji Hamada, Akihisa Sugiyama, Hideyuki Morita, Koji Setta, Hideyasu Ogo,

Eiji Shirai, “Proposal of Rationalized Assessment Procedure for Buckling of Thin-Walled
Cylindrical Tanks,” Solid State Phenomena, 120, pp. 199-206, (2007).
第 6 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 25-26, 2006, Kenting, Taiwan


H. Yamashita, S. Ooki, Y. Tanaka, K. Takamori, K. Asano, S. Suzuki, “SCC growth behavior ofBWR core shroud materials,” International Journal of Pressure Vessels and Piping, 85, pp.
582-592, (2008).

Akira Nebu, Katsumasa Miyazaki, Koichi Saito, “Ductile fracture strength of nickel-based alloy
plates with a surface flaw,” International Journal of Pressure Vessels and Piping, 85, pp.
612-615, (2008).

Masayuki Kamaya, Tomohisa Suzuki, Toshiyuki Meshii, “Failure pressure of straight pipe withwall thinning under internal pressure,” International Journal of Pressure Vessels and Piping, 85,pp. 628-634, (2008).

Akio Tanaka, Kensuke Futahashi, Kiyoshi Takanabe, Chikara Kurimura, Jungo Kato, HidekiyoHara, “Development of a 3-D simulation analysis system for PWR control rod drive
mechanism,” International Journal of Pressure Vessels and Piping, 85, pp. 655-661, (2008).

第 7 回 原子力機器健全性国際ワークショップ 関連投稿論文
July 2-4, 2008, Muju, Korea
Kunio Onizawa, Hiroyuki Nishikawa, Hiroto Itoh, “Development of probabilistic fracture
mechanics analysis codes for reactor pressure vessels and piping considering welding residualstress,” International Journal of Pressure Vessels and Piping, 87, pp. 2-10, (2010).

Y. Kanto, K. Onizawa, H. Machida, Y. Isobe, S. Yoshimura, “Recent Japanese research
activities on probabilistic fracture mechanics for pressure vessel and piping of nuclear power
plant,” International Journal of Pressure Vessels and Piping, 87, pp. 11-16, (2010).



N. Miura, Y. Takahashi, “Evaluation of J-integral for surface cracked plates under biaxial
loading using extended reference stress method,” International Journal of Pressure Vessels andPiping, 87, pp. 58-65, (2010).

Masayuki Kamaya, Hideo Machida, “Reference stress method for evaluation of failure
assessment curve of cracked pipes in nuclear power plants,” International Journal of PressureVessels and Piping, 87, pp. 66-73, (2010).

第 8 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 14-16, 2010, Hyogo, Japan

Masanori Kikuchi, Yoshitaka Wada, Yuto Shimizu, Yulong Li, “Crack growth analysis in a

weld-heat-affected zone using S-version FEM,” International Journal of Pressure Vessels andPiping, 90-91, pp. 2-8, (2012).
Yoshihiko Tanaka, “Study on analogy between dynamic load and displacement-controlled load,”International Journal of Pressure Vessels and Piping, 90-91, pp. 37-45, (2012).

Y. Kanto, M.-J. Jhung, K. Ting, Y.-B. He, K. Onizawa, S. Yoshimura, “Summary ofInternational PFM Round Robin analyses among Asian Countries on reactor pressure vessel
integrity during pressurized thermal shock,” International Journal of Pressure Vessels andPiping, 90-91, pp. 46-55, (2012).

Takuya Ogawa, Masao Itatani, Toshiyuki Saito, Takahiro Hayashi, Chihiro Narazaki, Kentaro
Tsuchihashi, “Fracture assessment for a dissimilar metal weld of low alloy steel and Ni-basealloy,” International Journal of Pressure Vessels and Piping, 90-91, pp. 61-68, (2012).

Naoki Ogawa, Itaru Muroya, Youichi Iwamoto, Takahiro Ohta, Mayumi Ochi, Kiminobu Hojo,
Kazuo Ogawa, “Studies of residual stress measurement and analysis techniques for a PWR
dissimilar weld joint,” International Journal of Pressure Vessels and Piping, 90-91, pp. 84-90,(2012).

第 9 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 18-20, 2012, Kaohsiuing, Taiwan


Masayuki Kamaya, “Estimation of elastic–plastic fracture toughness by numerical simulation
based on a stress-based criterion for ductile crack initiation,” International Journal of PressureVessels and Piping, 117-118, pp. 2-8, (2014).

Yoshiyuki Saito, Junichi Kishimoto, Toshihiro Matsuoka, Hiroki Tamaki, Akio Kitada,“Containment integrity evaluation of MSF-type cask for interim storage and transport of PWR
spent fuel,” International Journal of Pressure Vessels and Piping, 117-118, pp. 33-41, (2014).

H. Takazawa, N. Yanagida, “Effect of creep constitutive equation on simulated stress mitigation
behavior of alloy steel pipe during post-weld heat treatment,” International Journal of Pressure
Vessels and Piping, 117-118, pp. 42-48, (2014).

J. Katsuyama, H. Itoh, Y. Li, K. Osakabe, K. Onizawa, S. Yoshimura, “Benchmark analysis on
probabilistic fracture mechanics analysis codes concerning fatigue crack growth in aged pipingof nuclear power plants,” International Journal of Pressure Vessels and Piping, 117-118, pp.
56-63, (2014).

第 10 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 16-18, 2014, Busan, Korea


M. Nagai, N. Miura, M. Shiratori, “Stress intensity factor solution for a surface crack with highaspect ratio subjected to an arbitrary stress distribution using the influence function method,”International Journal of Pressure Vessels and Piping, 131, pp. 2-9, (2015).

Takuya Ogawa, Masao Itatani, Chihiro Narazaki, Toshiyuki Saito, “Fracture behavior
evaluations for ferritic steel piping with circumferential double flaws on the inner surface,”
International Journal of Pressure Vessels and Piping, 131, pp. 15-21, (2015).

Masayuki Kamaya, “Elastic-plastic failure assessment of cold worked stainless steel pipes,”International Journal of Pressure Vessels and Piping, 131, pp. 45-51, (2015).



Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa, Yinsheng Li, “Failure probabilityanalyses for PWSCC in Ni-based alloy welds,” International Journal of Pressure Vessels andPiping, 131, pp. 85-95, (2015).

第 11 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 11-13, 2016, Nagasaki, Japan

Makoto Udagawa, Yinsheng Li, Akemi Nishida, Izumi Nakamura, “Failure behavior analysesof piping system under dynamic seismic loading,” International Journal of Pressure Vessels
and Piping, 167, pp. 2-10, (2018).

Tomonori Yamada, Shinobu Yoshimura, Yuuichi Koide, Shohei Onitsuka, Tadashi Iijima,“Verification and validation of dynamic response simulation codes for BWR fuel assemblies
under seismic loading,” International Journal of Pressure Vessels and Piping, 167, pp. 25-31,(2018).



Masaki Nagai, Naoki Miura, Masato Yamamoto, “Pedestrian: Probabilistic fracture mechanics
analysis code based on direct sampling with replacement,” International Journal of Pressure
Vessels and Piping, 167, pp. 52-58, (2018).

H. Takazawa, K. Hirosaka, K. Miyazaki, N. Tohyama, S. Saigo, N. Matsumoto, “Failure
probability analyses for PWSCC in Ni-based alloy welds,” International Journal of PressureVessels and Piping, 167, pp. 66-71, (2018).

第 12 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 16-18, 2018, Hualien, Taiwan


Naoto Kasahara, Md Abdullah Al Bari, Ryota Sakemi, “Failure modes of piping under seismic
loads which have both load and displacement controlled characteristics,” International Journalof Pressure Vessels and Piping, 179, (2020), 103938.

Takuya Ogawa, Yohei Ono, Masao Itatani, Takahiro Hayashi, Toshiyuki Saito, “Evaluation ofmechanical properties distribution for irradiated stainless steels simulated by utilizing thegradient of the cold working ratio,” International Journal of Pressure Vessels and Piping, 179,(2020), 103939.
Akihiro Mano, Jinya Katsuyama, Yuhei Miyamoto, Yoshihito Yamaguchi, Yinsheng Li, “A newprobabilistic evaluation model for weld residual stress,” International Journal of PressureVessels and Piping, 179, (2020), 103945.

第 13 回 原子力機器健全性国際ワークショップ 関連投稿論文
April 21-22, 2021, Virtual Meeting
Tomoki Shinko, Masato Yamamoto, “Convertibility of Front Face Displacement to External
Load-Line Displacement for ductile crack growth test on miniature C(T) specimen,”
International Journal of Pressure Vessels and Piping, 197, (2022), 104630.

Akihiro Mano, Ryuta Imai, Yuhei Miyamoto, Kai Lu, Jinya Katsuyama, Yinsheng Li,“Improvement of the return mapping algorithm based on the implicit function theorem withapplication to ductile fracture analysis using the GTN model,” International Journal ofPressure Vessels and Piping, 199, (2022), 104700.

Shunsuke Takagi, S. Yoshida, “Development of estimation method for material property underhigh strain rate condition utilizing experiment and analysis,” International Journal of Pressure
Vessels and Piping, 199, (2022), 104771.