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J-GLOBAL ID：201901009219038294   Update date: Sep. 19, 2024

Kasahara Naoto

カサハラ ナオト | Kasahara Naoto
Affiliation and department：
The University of Tokyo Graduate School of Engineering, Department of Nuclear Engineering and Management

About The University of Tokyo Graduate School of Engineering, Department of Nuclear Engineering and Management


Job title： Professor
Homepage URL  (2)： http://park.itc.u-tokyo.ac.jp/nem-kasahara/ ,  http://park.itc.u-tokyo.ac.jp/nem-kasahara/englishnew/index.html
Research field  (1)： Nuclear engineering
Research theme for competitive and other funds  (3)：
  • 2016 - 2020 Study on prevention of catastrophic failure by fracture control technics
  • 2012 - 2016 Study on failure mechanisms and their countermeasures of nuclear structures under extreme loadings
  • 2010 - 2012 Failure Mechanism of Combustion Chamber of Liquid Rocket Engine under Severe Multi-Physics Conditions
Papers (223)：
  • Izumi Nakamura, Naoto Kasahara. Numerical examination on seismic response behavior of a piping system considering the plastic deformation of supports. International Journal of Pressure Vessels and Piping. 2024. 211. 105265-105265
  • Izumi Nakamura, Naoto Kasahara. Discussion On Failure Behavior of Piping Systems Under Extremely Large Seismic Loads in BDBE. Journal of Pressure Vessel Technology. 2021
  • Naoto Kasahara, Takashi Wakai, Izumi Nakamura, Takuya Sato, Masakazu Ichimiya. Example proposals of fracture controlled vessels and piping for failure mitigations. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2021. 2
  • Naoto Kasahara, Takashi Wakai, Izumi Nakamura, Takuya Sato, Masakazu Ichimiya. Application of Fracture Control to Mitigate Failure Consequence Under BDBE. Volume 3: Design and Analysis. 2020
  • Izumi Nakamura, Naoto Kasahara. Investigation on Failure Behavior of Two-Elbow Piping System Models Made of the Simulation Material Under Excessive Seismic Loads. Volume 3: Design and Analysis. 2020
ｍore...
MISC (66)：
  • OGAWA Hiroshi, MACHIDA Hideo, KASAHARA Naoto. OS0603-352 Analytical study on failure mode map for nuclear reactor structures under extreme loadings. 2015. 2015. "OS0603-352-1"-"OS0603-352-3"
  • KATSURA Yamato, KOKUFUDA Toshiaki, ADUULLAH Bari Md, DEMACHI Kazuyuki, SATO Takuya, KASAHARA Naoto. OS0612-266 Progressive Deformation of Structure of Nuclear Power Plant under Seismic Loading. 2015. 2015. "OS0612-266-1"-"OS0612-266-3"
  • IWATA Koji, KARAKIDA Yasuhisa, JIN Chuanrong, KASAHARA Naoto. OS0614-144 Cyclic Plasticity Constitutive Equations for Carbon Steel and Benchmark Analyses of Piping Structures. 2015. 2015. "OS0614-144-1"-"OS0614-144-3"
  • KASAHARA Naoto, SUZUKI Masaaki. OS0601-300 Total evaluation of loadings and strength by multi-physics simulation. 2015. 2015. "OS0601-300-1"-"OS0601-300-3"
  • KURIBAYASHI Hiroshi, SUZUKI Masaaki, KASAHARA Naoto. J0310401 Development of Thermal Fatigue Damage Evaluation Method for Thermal Stratification Oscillation by using Frequency Response Function. Mechanical Engineering Congress, Japan. 2015. 2015. "J0310401-1"-"J0310401-5"
ｍore...
Patents (3)：
  • 空気浮揚式の浮体免震構造
  • Thermal Load Reduction System for Nuclear Reactor Vessel、U.S. Patent Application Serial No.10/682,859,
  • 原子炉容器の熱荷重緩和装置
Books (15)：
  • 原子力年鑑2019
    日刊工業新聞社 「原子力年鑑」編集委員会-編 2018
  • 続・実際の設計 (改訂新版) 機械設計に必要な知識とモデル
    日刊工業 2017 ISBN:9784526076794
  • Fast Reactor System Design
    SpringerLink 2017
  • 東日本大震に関する研究
    東京大学新聞社 2017
  • Thermal Plastic Ratcheting,. In Hetnarski RB (Ed.) Encyclopedia of Thermal Stresses, Vol 1, pp 1 - 8. Springer Dordrecht, Heidelberg, New York, London
    Springer 2015 ISBN:9789400763555
ｍore...
Lectures and oral presentations  (470)：
  • 原子炉容器を模擬したノズル付き円板試験体の局部破損に関する研究,
    (原子力学会 2019)
  • Experimental and Analytical Study on Local Failure of Structure Subjected to High Temperature and Pressure
    (The American Society of Mechanical Engineers Pressure Vessels & Piping Conference 2019)
  • A Proposal of Inelastic Constitutive Equations of Lead Alloys Used for Structural Tests Simulating Severe Accident Conditions
    (The American Society of Mechanical Engineers Pressure Vessels & Piping Conference 2019)
  • APPLICATION OF FRACTURE CONTROL TO NUCLEAR COMPONENTS FOR MITIGATION OF ACCIDENT CONSEQUENCE
    (SMiRT 25 04 Aug 2019 - 09 Aug 2019, Charlotte, North Carolina, USA 2019)
  • DISCUSSION ON FAILURE BEHAVIOUR OF PIPING SYSTEMS SUBJECTED TO EXCESSIVE SEISMIC LOADS
    (SMiRT 25 04 Aug 2019 - 09 Aug 2019, Charlotte, North Carolina, USA 2019)
ｍore...
Education (1)：
  • 1982 - 1984 The University of Tokyo 工学系研究科 産業機械工学専攻
Professional career (1)：
  • 博士(工学) (東京大学)
Work history (3)：
  • 2005/10/01 - 日本原子力研究開発機構
  • 1998/10/01 - 核燃料サイクル開発機構
  • 1984/04/01 - 動力炉・核燃料開発事業団
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