Takaya Shigeru

タカヤシゲル | Takaya Shigeru

Affiliation and department：

Research field (1)： Nuclear engineering

Research theme for competitive and other funds (1)：

Papers (67)：

Seki Akiyuki, Yoshikawa Masanori, Nishinomiya Ryota*, Okita Shoichiro, Takaya Shigeru, Yan X. Development of a surrogate system of a plant dynamics simulation model and an abnormal situation identification system for nuclear power plants using deep neural networks. Nuclear Technology. 2024. 210. 6. 1003-1014
Takaya Shigeru, Seki Akiyuki, Yoshikawa Masanori, Sasaki Naoto*, Yan X. Proposal of a novel AI-based plant operator support system for the safety of nuclear power plants. Mechanical Engineering Journal (Internet). 2024. 11. 2. 23-00408\_1-23-00408\_11
Hashidate Ryuta, Yada Hiroki, Takaya Shigeru, Enuma Yasuhiro. Proposal of a method of extracting design issues on maintenance for the rational design of next-generation reactors. Hozengaku. 2024. 23. 1. 103-111
Yada Hiroki, Takaya Shigeru, Machida Hideo*. Comparison between fracture mechanics evaluation methods in ASME Boiler \& Pressure Vessel Code, section XI and those in JSME leak-before-break evaluation guidelines for sodium-cooled fast reactors. Proceedings of ASME 2023 Pressure Vessels and Piping Conference (PVP 2023) (Internet). 2023. 8
Yada Hiroki, Takaya Shigeru, Morohoshi Kyoichi*, Yokoi Shinobu*, Miyagawa Takayuki*. Proposal for maintenance optimization scheme based on system based code concept. Mechanical Engineering Journal (Internet). 2023. 10. 4. 23-00044\_1-23-00044\_13

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MISC (18)：

Okajima Satoshi, Takaya Shigeru, Wakai Takashi, Asayama Tai. JSME Series in Thermal and Nuclear Power Generation Vol. 3; Development of codes and standards considering condition in Sodium-cooled Fast Reactor. Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet). 2023. 3
Tanaka Masaaki, Doda Norihiro, Yokoyama Kenji, Mori Takero, Okajima Satoshi, Hashidate Ryuta, Yada Hiroki, Oki Shigeo, Miyazaki Masashi, Takaya Shigeru. Development of ARKADIA for the innovation of advanced nuclear reactor design process (Overview of optimization process development in design optimization support tool, ARKADIA-Design). Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet). 2022. 5
Yokoi Shinobu*, Kamishima Yoshio*, Sadahiro Daisuke*, Takaya Shigeru. Determination methodologies for input data including loads considered for reliability evaluation of fast reactor components. JAEA-Data/Code 2016-002. 2016. 38
Takaya Shigeru, Chikazawa Yoshitaka, Hayashida Kiichi, Tagawa Akihiro, Kubo Shigenobu, Yamashita Atsushi. Maintenance management of nuclear power reactors at the stage of research and development. JAEA-Research 2016-006. 2016. 2016. 6. 66-2,1-66
Takaya Shigeru, Sasaki Naoto*, Tomobe Masato*. Statistical properties of material strength for reliability evaluation of components of fast reactors; Austenitic stainless steels. JAEA-Data/Code 2015-002. 2015. 54

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Patents (6)：

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Lectures and oral presentations (119)：

Development of advanced reactor knowledge- and AI-aided design integration approach through the whole plant lifecycle, ARKADIA, 13; Achievements and future challenges for design optimization support in knowledge management systems
(日本原子力学会2024年春の年会)
Development of advanced reactor knowledge- and AI-aided design integration approach through the whole plant lifecycle, ARKADIA, 11; Achievements of design optimization processes and future challenges in ARKADIA-Design
(日本原子力学会2024年春の年会)
Development of fitness-for-service code for sodium-cooled fast reactors
(Virtual Workshop on Condition Monitoring and Structural Health Management for Nuclear Power Plants)
Analysis of inspection process schedules for sodium cooled fast reactors using swarm intelligence
(日本保全学会第19回学術講演会)
Development of a method for extracting maintenance preconditions by using the graph structure and application to maintenance scheduling
(日本保全学会第19回学術講演会)

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Awards (7)：

2019/11 - 日本機械学会一般社団法人日本機械学会動力エネルギーシステム部門貢献表彰液体金属炉の供用期間中検査に関わる基本論理の確立を規格化
2019/05 - 米国機械学会(ASME) BPV Committee on Nuclear Inservice Inspection (XI) Awards Significant role in the development of BPV XI Division 2, Requirements for Reliability and Integrity Management Programs for Nuclear Power Plants
2019/03 - 日本機械学会標準事業国際功績賞 JSME/ASMEの連携による信頼性評価を活用した高速炉用維持規格の開発
2017/05 - 日本保全学会論文賞「高温磁気センサの開発」
2011/05 - 日本保全学会論文賞オーステナイト系ステンレス鋼溶接継手の金属組織と残留応力に及ぼす実機での高温長時間使用及び補修溶接の

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