Takashi Wakai - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101000323498575
researchmap Member ID: R000017472

Research Areas

Manufacturing technology (mechanical, electrical/electronic, chemical engineering) / Machine materials and mechanics /

Papers

Numerical simulation technologies for safety evaluation in plant lifecycle optimization method, ARKADIA for advanced reactors

Uchibori Akihiro, Doda Norihiro, Aoyagi Mitsuhiro, Sonehara Masateru, Sogabe Joji, Okano Yasushi, Takata Takashi*, Tanaka Masaaki, Enuma Yasuhiro, Wakai Takashi …

Nuclear Engineering and Design, 413 112492\_1-112492\_10, Nov, 2023 Peer-reviewed
Development of element functions and design optimization procedures with knowledge- and AI-aided design integration approach for advanced reactor lifecycle in ARKADIA

Tanaka Masaaki, Enuma Yasuhiro, Okano Yasushi, Uchibori Akihiro, Yokoyama Kenji, Seki Akiyuki, Wakai Takashi, Asayama Tai

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 11, May, 2023 Peer-reviewed
Development of plant lifecycle optimization method, ARKADIA for advanced reactors

Uchibori Akihiro, Sogabe Joji, Okano Yasushi, Takata Takashi*, Doda Norihiro, Tanaka Masaaki, Enuma Yasuhiro, Wakai Takashi, Asayama Tai, Ohshima Hiroyuki

Proceedings of Technical Meeting on State-of-the-art Thermal Hydraulics of Fast Reactors (Internet), 10, Sep, 2022 Peer-reviewed
Sodium-cooled Fast Reactors

Ohshima Hiroyuki, Morishita Masaki*, Aizawa Kosuke, Ando Masanori, Ashida Takashi, Chikazawa Yoshitaka, Doda Norihiro, Enuma Yasuhiro, Ezure Toshiki, Fukano Yoshitaka …

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631, Jul, 2022 Peer-reviewed
The Multiaxial creep-fatigue failure mechanism of Mod. 9Cr-1Mo steel under non-proportional loading; Effect of strain energy on failure lives

Ogawa Fumio*, Nakayama Yuta*, Hiyoshi Noritake*, Hashidate Ryuta, Wakai Takashi, Ito Takamoto*

Transactions of the Indian National Academy of Engineering (Internet), 7(2) 549-564, Jun, 2022 Peer-reviewed
Material data acquisition activities to develop the material strength standard for sodium-cooled fast reactors

Toyota Kodai, Onizawa Takashi, Wakai Takashi, Hashidate Ryuta, Kato Shoichi

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 10, Apr, 2022 Peer-reviewed
Evaluation of multiaxial low cycle creep-fatigue life for Mod.9Cr-1Mo steel under non-proportional loading

Nakayama Yuta*, Ogawa Fumio*, Hiyoshi Noritake*, Hashidate Ryuta, Wakai Takashi, Ito Takamoto*

ISIJ International, 61(8) 2299-2304, Aug, 2021 Peer-reviewed
Development of leak before break assessment guidelines for sodium cooled fast reactors in Japan

Yada Hiroki, Wakai Takashi, Miyagawa Takayuki*, Machida Hideo*

Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet), 10, Jul, 2021 Peer-reviewed
Proposal of simulation material test technique for clarifying the structure failure mechanisms under excessive seismic loads

Hashidate Ryuta, Kato Shoichi, Onizawa Takashi, Wakai Takashi, Kasahara Naoto*

Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet), 9, Jul, 2021 Peer-reviewed
Proposal of simulation materials test technique and their constitutive equations for structural tests and analyses simulating severe accident conditions

Hashidate Ryuta, Kato Shoichi, Onizawa Takashi, Wakai Takashi, Kasahara Naoto*

Proceedings of ASME 2020 Pressure Vessels and Piping Conference (PVP 2020) (Internet), 9, Aug, 2020 Peer-reviewed
A Proposal of inelastic constitutive equations of lead alloys used for structural tests simulating severe accident conditions

Hashidate Ryuta, Onizawa Takashi, Wakai Takashi, Kasahara Naoto*

Proceedings of 2019 ASME Pressure Vessels and Piping Conference (PVP 2019) (Internet), 10, Jul, 2019 Peer-reviewed
Study on creep damage assessment method for Mod.9Cr-1Mo steel by sampling creep testing with thin plate specimen

Kanayama Hideyuki*, Hiyoshi Noritake*, Ogawa Fumio*, Kawabata Mie*, Ito Takamoto*, Wakai Takashi

Zairyo, 68(5) 421-428, May, 2019 Peer-reviewed
Effect of local plastic component on crack opening displacement and on J-integral of a circumferential penetrated crack

Machida Hideo*, Arakawa Manabu*, Wakai Takashi

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8, May, 2019 Peer-reviewed
Development of a crack opening displacement assessment procedure considering change of compliance at a crack part in thin wall pipes made of modified 9Cr-1Mo steel

Wakai Takashi, Machida Hideo*, Arakawa Manabu*, Yanagihara Seiji*, Suzuki Ryosuke*, Matsubara Masaaki*

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 9, Jul, 2018 Peer-reviewed
Proposal of simplified J-integral evaluation method for a through wall crack in SFR pipe made of Mod.9Cr-1Mo steel

Wakai Takashi, Machida Hideo*, Arakawa Manabu*, Kikuchi Koichi*

Proceedings of ASME Symposium on Elevated Temperature Applications of Materials for Fossil, Nuclear, and Petrochemical Industries, 7, Apr, 2018 Peer-reviewed
Proposal on LBB evaluation conditions for sodium cooled fast reactor pipes and effects of pipe parameters

Yada Hiroki, Takaya Shigeru, Wakai Takashi, Nakai Satoru, Machida Hideo*

Nihon Kikai Gakkai Rombunshu (Internet), 84(859) 17-00389\_1-17-00389\_15, Mar, 2018 Peer-reviewed
Study on a unified criterion for preventing plastic strain accumulation due to long distance travel of temperature distribution

Okajima Satoshi, Wakai Takashi, Kawasaki Nobuchika

Mechanical Engineering Journal (Internet), 4(5) 16-00641\_1-16-00641\_11, Oct, 2017 Peer-reviewed
Thermal fatigue test on dissimilar welded joint between Gr.91 and 304SS

Wakai Takashi, Kobayashi Sumio, Kato Shoichi, Ando Masanori, Takasho Hideki*

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 7, Jul, 2017 Peer-reviewed
Influence of cyclic softening on high temperature material properties in Mod.9Cr-1Mo steel

Onizawa Takashi, Nagae Yuji, Kato Shoichi, Wakai Takashi

Zairyo, 66(2) 122-129, Feb, 2017 Peer-reviewed
Effect of specimen size and oxygen partial pressure on creep characteristics for mod. 9Cr-1Mo steel

Kanayama Hideyuki, Hiyoshi Noritake*, Ito Takamoto*, Ogawa Fumio*, Wakai Takashi

Zairyo, 66(2) 86-92, Feb, 2017 Peer-reviewed

Misc.

JSME Series in Thermal and Nuclear Power Generation Vol. 3; Development of codes and standards considering condition in Sodium-cooled Fast Reactor

Okajima Satoshi, Takaya Shigeru, Wakai Takashi, Asayama Tai

Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 3, Sep, 2023
JSME series in thermal and nuclear power generation Vol.3 (Sodium-cooled fast reactor development; R\&Ds on thermal-hydraulics and safety assessment towards social implementation)

Tanaka Masaaki, Uchibori Akihiro, Okano Yasushi, Yokoyama Kenji, Uwaba Tomoyuki, Enuma Yasuhiro, Wakai Takashi, Asayama Tai

Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5, Sep, 2023
Study on fracture behaviour of through-wall cracked elbow under displacement control load

Machida Hideo*, Koizumi Yu*, Wakai Takashi, Takahashi Koji*

Nihon Kikai Gakkai M\&M 2019 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), OS1307\_1-OS1307\_5, Nov, 2019
Improvement of penetrate crack length evaluation method for LBB assessment of sodium-cooled fast reactor components

Wakai Takashi, Machida Hideo*, Arakawa Manabu*

Nihon Kikai Gakkai 2018-Nendo Nenji Taikai Koen Rombunshu (DVD-ROM), 5, Sep, 2018
Study on the seismic buckling evaluation method for Mod. 9Cr-1Mo steel cylindrical vessel

Okafuji Takashi*, Miura Kazuhiro*, Sago Hiromi*, Murakami Hisatomo*, Kubo Koji*, Sato Kenichiro*, Wakai Takashi, Shimomura Kenta

Nihon Kikai Gakkai M\&M 2017 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), 591-595, Oct, 2017
Study of the calculation method for the elastic follow-up coefficient by inelastic analysis

Watanabe Sota*, Kubo Koji*, Okajima Satoshi, Wakai Takashi

Nihon Kikai Gakkai M\&M 2017 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), 581-585, Oct, 2017
Saturation behavior of thermal ratcheting strain due to long range travel of temperature distribution

Okajima Satoshi, Wakai Takashi

Nihon Kikai Gakkai 2017-Nendo Nenji Taikai Koen Rombunshu (DVD-ROM), 5, Sep, 2017
Study on unified criteria for preventing plastic strain accumulation due to thermal stress with long range travel

Okajima Satoshi, Wakai Takashi, Kawasaki Nobuchika

Proceedings of International Conference on Asia-Pacific Conference on Fracture and Strength 2016 (APCFS 2016) (USB Flash Drive), 269-270, Sep, 2016
A Study on evaluation method of penetrate crack length for LBB assessment of fast reactor pipes

Wakai Takashi, Machida Hideo*, Sato Kenichiro*

Nihon Kikai Gakkai M\&M 2015 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), 3, Nov, 2015
Requirements for fracture toughness to satisfy LBB behavior of a pipe made of high chromium steel

Machida Hideo*, Wakai Takashi, Sato Kenichiro*

Nihon Kikai Gakkai 2015-Nendo Nenji Taikai Koen Rombunshu (DVD-ROM), 5, Sep, 2015
J-integral evaluation method for a through wall crack in thin-walled large diameter pipes made of Mod.9Cr-1Mo steel

Wakai Takashi, Machida Hideo*, Arakawa Manabu*, Sato Kenichiro*

Nihon Kikai Gakkai 2015-Nendo Nenji Taikai Koen Rombunshu (DVD-ROM), 5, Sep, 2015
A Report on the Meeting "SMiRT22"

Wakai Takashi

Hozengaku, 12(3) 69-70, Oct, 2013
Collapse strength of multiple notched pipes under combined load

Shiraishi Taisuke*, Matsubara Masaaki*, Suzuki Ryosuke*, Suzuki Masato*, Wakai Takashi, Sakamoto Kenji*

Proceedings of 5th International Workshop New Methods of Damage and Failure Analysis of Structural Parts (CD-ROM), 6, Sep, 2012
Collapse strength of SUS304 steel pipes with circumferential multiple notches subjected to axial tension and bending

Shiraishi Taisuke*, Matsubara Masaaki*, Suzuki Ryosuke*, Suzuki Masato*, Yanagihara Seiji*, Sakamoto Kenji*, Wakai Takashi

Nihon Kikai Gakkai M\&M 2012 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), 3, Sep, 2012
Plastic collapse strength and maximum load evaluation method of flawed stainless piping subjected to axial tension and bending

Yanagihara Seiji*, Matsubara Masaaki*, Suzuki Ryosuke*, Suzuki Masato*, Shiraishi Taisuke*, Sakamoto Kenji*, Wakai Takashi

Nihon Kikai Gakkai M\&M 2012 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), 2, Sep, 2012
A Report on the meeting "SMiRT21"

Wakai Takashi

Hozengaku, 10(4)-96, Jan, 2012
Demonstration of leak-before-break in Japan Sodium cooled Fast Reactor (JSFR) pipes

Wakai Takashi, Machida Hideo*, Yoshida Shinji*, Xu Y.*, Tsukimori Kazuyuki

Transactions of the 21st International Conference on Structural Mechanics in Reactor Technology (SMiRT-21) (CD-ROM), 8, Nov, 2011
The Creep rupture strength evaluation in welded joint of Mod.9Cr-1Mo steel

Wakai Takashi, Nagae Yuji, Takaya Shigeru, Obara Satoshi, Date Shingo*, Yamamoto Kenji*, Kikuchi Koichi*, Sato Kenichiro*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 52(2) 147-159, Jul, 2011
Manufacturability and strength assessment of modified 9Cr-1Mo steel products for Japan sodium cooled fast reactor components, 2; Long thin-walled tubes with small diameter

Wakai Takashi, Onizawa Takashi, Obara Satoshi, Nakashima Takashi*, Yokoyama Tetsuo*, Iseda Atsuro*, Ogumo Shinya*, Futagami Satoshi*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 52(2) 171-181, Jul, 2011
Plasticity collapse strength of stainless piping subjected to combined tension and bending

Matsubara Masaaki*, Hayashi Tatsuya*, Suzuki Masato*, Shiraishi Taisuke*, Sakamoto Kenji*, Wakai Takashi

Nihon Kikai Gakkai M\&M 2011 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), 2, Jul, 2011

Presentations

Multiaxial creep-fatigue life evaluation of Mod.9Cr-1Mo steel at elevated temperature; Study of life arrangement by mathematical formula considering hysteresis energy

Ogawa Fumio*, Imagawa Yuya, Hashidate Ryuta, Wakai Takashi, Hiyoshi Noritake*, Ito Takamoto*

第60回記念高温強度シンポジウム
Development of fitness for service codes and leak-before-break evaluation guidelines for sodium cooled fast reactors

Yada Hiroki, Takaya Shigeru, Nakai Satoru*, Wakai Takashi, Kamishima Yoshio*, Machida Hideo*, Miyagawa Takayuki*

日本保全学会第18回学術講演会
A Proposal of a conversion method between small punch creep properties and uniaxial ones of Mod.9Cr-1Mo steel at the operating temperature of fast reactors

Yamashita Hayato, Onizawa Takashi, Takaya Shigeru, Enuma Yasuhiro, Wakai Takashi, Kato Shoichi, Suzuki Akihiro*

日本機械学会M\&M2021材料力学カンファレンス
Multiaxial creep-fatigue failure mechanism of Mod. 9Cr-1Mo steel under non-proportional loading; Effect of strain energy on failure lives

Ogawa Fumio*, Nakayama Yuta*, Hiyoshi Noritake*, Hashidate Ryuta, Wakai Takashi, Ito Takamoto*

8th International Conference on Creep, Fatigue and Creep-Fatigue Interaction (CF-8)
New approach to beyond design basis events in structural strength field

Kasahara Naoto*, Demachi Kazuyuki*, Sato Takuya*, Ichimiya Masakazu*, Wakai Takashi, Yamano Hidemasa, Nakamura Izumi*

日本保全学会第17回学術講演会
Multiaxial creep-fatigue property of Mod. 9Cr-1Mo steel and life evaluation

Okamoto Masayuki*, Nakayama Yuta*, Ogawa Fumio*, Hashidate Ryuta, Hiyoshi Noritake*, Wakai Takashi, Ito Takamoto*

日本材料学会第70期通常総会・学術講演会
Development of extremely high temperature material property equations and physical property values on austenitic stainless steel

Onizawa Takashi, Wakai Takashi

25th International Conference on Structural Mechanics in Reactor Technology (SMiRT-25)
Development of inelastic constitutive equations of lead alloys used for structural tests simulating severe accident conditions

Hashidate Ryuta, Kato Shoichi, Onizawa Takashi, Wakai Takashi, Kasahara Naoto*

平成31年度日本原子力学会北関東支部若手研究者発表会
Development of extremely high temperature material property equations on austenitic stainless steel

Onizawa Takashi, Shimomura Kenta, Kato Shoichi, Wakai Takashi

JASMiRT第2回国内ワークショップ
Development in remaining of creep life assessment method for Mod. 9Cr-1Mo steel using thin plate specimen

Kanayama Hideyuki, Hiyoshi Noritake*, Ogawa Fumio*, Ito Takamoto*, Wakai Takashi

日本材料学会高温強度・破壊力学合同シンポジウム; 第55回高温強度シンポジウム・第18回破壊力学シンポジウム
Proposal of the creep rupture equation on 316FR steel for Structural material of FR

Onizawa Takashi, Wakai Takashi

日本機械学会M\&M2017材料力学カンファレンス
The Formulation of material characteristics of austenitic stainless steels at extremely high temperature

Shimomura Kenta, Onizawa Takashi, Kato Shoichi, Ando Masanori, Wakai Takashi

2017 ASME Pressure Vessels and Piping Conference (PVP 2017)
Leak before break assessment for class 1 piping in sodium-cooled fast reactors

Yada Hiroki, Takaya Shigeru, Wakai Takashi, Machida Hideo*

日本機械学会第22回動力・エネルギー技術シンポジウム
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 3; Proposal of an assumed leak size in piping under the LORL event

Yada Hiroki, Ando Masanori, Wakai Takashi

日本原子力学会2017年春の年会
Effect of aging and creep damage on mechanical strength of Mod. 9Cr-1Mo steel

Kanayama Hideyuki, Nagae Yuji, Onizawa Takashi, Wakai Takashi, Imo Kazumichi*

日本材料学会第53回高温強度シンポジウム
Applicability evaluation of non-destructive testing using microwaves for a crack on the inner surface of metal pipes

Sasaki Kota*, Yusa Noritaka*, Hashizume Hidetoshi*, Wakai Takashi

17th International Symposium on Applied Electromagnetics and Mechanics (ISEM 2015)
Evaluation of cyclic softening on tensile and creep properties in Mod.9Cr-1Mo steel

Onizawa Takashi, Nagae Yuji, Kato Shoichi, Wakai Takashi

日本材料学会第64期通常総会・学術講演会
Creep and creep-fatigue properties in welded joint of modified 9Cr-1Mo at elevated temperature

Nagae Yuji, Onizawa Takashi, Yamashita Takuya, Wakai Takashi

日本鉄鋼協会第169回春季講演大会
Effect of aging on tensile property in modified 9Cr-1Mo steel for long-term design

Nagae Yuji, Onizawa Takashi, Wakai Takashi

日本鉄鋼協会第168回秋季講演大会
Development of a crack opening displacement assessment procedure considering change of compliance at a crack part in thin wall pipes made of modified 9Cr-1Mo steel

Wakai Takashi, Machida Hideo*, Arakawa Manabu*, Yoshida Shinji*, Yanagihara Seiji*, Suzuki Ryosuke*, Matsubara Masaaki*, Enuma Yasuhiro*

6th International Workshop on New Methods of Damage and Failure Analysis of Structural Parts

Industrial Property Rights

4355787 フェライト鋼の製造方法

若井隆純, 西澤崇徳*, 茂木智*, 木村健一*