Rchr
J-GLOBAL ID：202101020612183567
Update date: Jul. 01, 2024
Katsuyama Jinya
カツヤマ ジンヤ | Katsuyama Jinya
Affiliation and department：
Other affiliations (1)：
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The University of Tokyo
Department of Nuclear Engineering and Management School of Engineering
Project Associate Professor
Research field (2)：
Nuclear engineering
, Metallic materials
Research theme for competitive and other funds (2)：
- 微小欠陥-元素分布トモグラフィー法による原子炉構造材料の照射劣化機構の解明
- 先端ナノ組織分析による事故時加熱環境を考慮した原子炉構造材料の劣化機構解明と予測
Papers (140)：
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Li S., Yamaguchi Yoshihito, Katsuyama Jinya, Li Y., Deng D.*. Modeling of hardness and welding residual stress in Type 316 stainless steel components for the assessment of stress corrosion cracking. Proceedings of ASME 2023 Pressure Vessels and Piping Conference (PVP 2023) (Internet). 2023. 7
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Yamaguchi Yoshihito, Takamizawa Hisashi, Katsuyama Jinya, Li Y. Development of stress intensity factor solution for surface crack at nozzle corner in reactor pressure vessel. Proceedings of ASME 2023 Pressure Vessels and Piping Conference (PVP 2023) (Internet). 2023. 9
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Shimodaira Masaki, Ha Yoosung, Takamizawa Hisashi, Katsuyama Jinya, Onizawa Kunio. Analysis of the effect of pre-crack curvature in Mini-C(T) specimen on fracture toughness evaluation. Proceedings of ASME 2023 Pressure Vessels and Piping Conference (PVP 2023) (Internet). 2023. 11
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Ha Yoosung, Tobita Toru, Takamizawa Hisashi, Katsuyama Jinya. Fracture toughness evaluation of the heat-affected zone under the weld overlay cladding in reactor pressure vessel steel. Journal of Pressure Vessel Technology. 2023. 145. 2. 021501\_1-021501\_9
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Lu K., Takamizawa Hisashi, Katsuyama Jinya, Li Y. Recent improvements of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessels. International Journal of Pressure Vessels and Piping. 2022. 199. 104706\_1-104706\_13
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MISC (21)：
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Ha Yoosung, Shimodaira Masaki, Katsuyama Jinya. Fracture toughness evaluation of weld-HAZ in RPV steel using Mini-C(T) specimens. Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet). 2024. 7
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Takamizawa Hisashi, Lu K., Katsuyama Jinya, Masaki Koichi*, Miyamoto Yuhei*, Li Y. User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL Ver.5 for reactor pressure vessels. JAEA-Data/Code 2022-006. 2023. 221
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Lu K., Katsuyama Jinya, Takamizawa Hisashi, Li Y. Guideline on structural integrity assessment for reactor pressure vessel in domestic light water reactor based on probabilistic fracture mechanics. JAEA-Research 2022-012. 2023. 39
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Yamaguchi Yoshihito, Mano Akihiro, Katsuyama Jinya, Masaki Koichi*, Miyamoto Yuhei*, Li Y. User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL-SP Ver. 2 for piping (Contract research). JAEA-Data/Code 2020-021. 2021. 176
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Yamaguchi Yoshihito, Katsuyama Jinya, Masaki Koichi*, Li Y. Guideline on seismic fragility evaluation for aged piping (Contract research). JAEA-Research 2020-017. 2021. 80
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Lectures and oral presentations (120)：
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Quantitative evaluation of the effect of nondestructive examination based on probabilistic fracture mechanics
(日本機械学会第28回動力・エネルギー技術シンポジウム)
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Uncertainty analyses on fracture toughness of heat affected zone in an RPV steel
(23rd International Group on Radiation Damage Mechanisms (IGRDM-23))
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Evaluation of mechanical properties of weld heat-affected zone in reactor pressure vessel
(日本原子力学会2023年秋の大会)
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Fracture toughness distribution of a thick plate of A533B with welding
(22nd International Group on Radiation Damage Mechanisms (IGRDM-22))
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Effect of annealing models on the welding-induced residual stress and plastic strain in Type 316 stainless steel welded joints
(6th International Symposium on Visualization in Joining \& Welding Science through Advanced Measurements and Simulation (Visual-JW 2022))
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Association Membership(s) (4)：
日本保全学会
, 日本機械学会
, 日本原子力学会
, 日本金属学会
