Akira Nakamura - My portal - researchmap

Profile Information

Affiliation: Vice Director, Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc.

J-GLOBAL ID: 201701011938553737
researchmap Member ID: B000273739

Research Interests

1

Machine Learning

Research Areas

1

Manufacturing technology (mechanical, electrical/electronic, chemical engineering) / Fluid engineering /

Research History

4

Jul, 2022 - Present

Vice Director, Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc.
Jun, 2017 - Jun, 2022

(Director), Institute of Nuclear Technology, Nuclear Power Plant Aging Research Center, Institute of Nuclear Safety System, Inc.
Aug, 1996 - Jun, 2009

Researcher, Institute of Nuclear Technology, Thermal Hydraulics and Mechanics Group, Institute of Nuclear Safety System, Inc.
Apr, 2004 - Mar, 2007

Associate Professor, Graduate School of Engineering, Fukui University

Committee Memberships

24

Jul, 2022 - Present

Nuclear Research Committee, Japan Welding Engineering Society
Aug, 2016 - Present

Standards Committee, System Safety Technical Committee, Atomic Energy Society Japan
Jul, 2017 - Jan, 2023

Planning Committee of Nuclear Research Committee, Japan Welding Engineering Society
Apr, 2020 - Mar, 2021

北陸信越支部副支部長, 日本機械学会
Apr, 2017 - Mar, 2019

Steering Committee of Power and Energy System Division, Japan Society of Mechanical Engineers
Aug, 2015 - Nov, 2016

第１０回原子炉熱流動と安全に関する日韓シンポジウム現地委員会, 日本原子力学会
Apr, 2014 - Mar, 2016

熱流動部会国際小委員会, 日本原子力学会
Apr, 2014 - Mar, 2015

第92期論文編集委員会, 日本機械学会
Jan, 2014 - Jun, 2014

Organizing Committee of 19th Symposium of Power and Energy Systems, Japan Society of Mechanical Engineers
Apr, 2013 - Mar, 2014

第91期論文編集委員会, 日本機械学会
Apr, 2012 - Mar, 2014

配管減肉管理法の改良・実用化に向けた調査研究分科会, 日本機械学会
Apr, 2012 - Mar, 2013

第90期論文編集委員会, 日本機械学会
Aug, 2012 - Dec, 2012

第９回原子炉熱流動と安全に関する韓日シンポジウム技術委員会, 日本原子力学会
Apr, 2011 - Mar, 2012

第89期論文編集委員会, 日本機械学会
Apr, 2010 - Mar, 2012

配管減肉管理高度化に向けた最新技術知見適用化のための調査研究分科会, 日本機械学会
Apr, 2008 - Mar, 2010

配管減肉管理改善に向けた基盤技術研究分科会, 日本機械学会
Apr, 2007 - Mar, 2010

高速炉熱流動・安全評価特別専門委員会, 日本原子力学会
Apr, 2008 - Mar, 2009

第86期論文編集委員会, 日本機械学会
Apr, 2007 - Mar, 2008

第85期論文編集委員会, 日本機械学会
Apr, 2007 - Mar, 2008

配管減肉特別タスク技術サブタスク代表性検討ワーキング, 日本機械学会

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Awards

4

Jun, 2021

Prize of Excellent Research, Research of accident estimation for nuclear power plant using machine learning, Institute of Nuclear Safety System, Inc.

Akira Nakamura
Apr, 2017

Excellent Paper Award, Measurement of Flow Accelerated Corrosion Rate at an Elbow Pipe and Combination Effect of an Upstream Orifice, Japan Society of Maintenology

Yoichi Utanohara, Koichi Kamahori, Akira Nakamura, Michio Murase
Apr, 2015

JSME Medal for Outstanding Paper, Correlation between Flow Accelerated Corrosion and Wall Shear Stress Downstream from an Orifice, The Japan Society of Mechanical Engineers

Yoichi Utanohara, Yukinori Nagaya, Akira Nakamura, Michio Murase, Kouichi Kamahori
Apr, 2000

Prize of Excellent Research, Flow Simulation of Structure in Piping, Institute of Nuclear Safety System, Inc.

Akira Nakamura

Papers

43

Development of a Machine Learning Method to Predict the Break Diameter during PWR Loss-of-Coolant Accident

Akira NAKAMURA, Takayoshi KUSUNOKI

Transactions of the Atomic Energy Society of Japan, 21(2) 96-105, May, 2022 Peer-reviewedLead author
Heat transfer coefficient suitable for thermal fatigue assessment at a T-junction

Koji Miyoshi, Masayuki Kamaya, Yoichi Utanohara, Akira Nakamura

Nuclear Engineering and Design, 28(370) 1-12, Dec, 2020 Peer-reviewed
Heat transfer coefficient suitable for thermal fatigue assessment at a T-junction

Koji Miyoshi, Masayuki Kamaya, Yoichi Utanohara, Akira Nakamura

Nuclear Engineering and Design, 370 110916-110916, 2020 Peer-reviewed
Study on characteristics of wall temperature fluctuation at a mixing tee with an upstream elbow

Koji Miyoshi, Akira Nakamura

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, 4, 2018
Numerical simulation of thermal stress fluctuation at a mixing tee for thermal fatigue problems

Koji MIYOSHI, Akira NAKAMURA, Yoichi UTANOHARA, Masayuki KAMAYA

Mechanical Engineering Journal, 5(4) 18-00272, 2018 Peer-reviewed
Conjugate numerical simulation of wall temperature fluctuation at a T-junction pipe

Yoichi UTANOHARA, Koji MIYOSHI, Akira NAKAMURA

Mechanical Engineering Journal, 5(3) 18-00044, 2018 Peer-reviewed
Investigation of flow structure to prevent thermal fatigue in a downward branch pipe with a closed end

Koji Miyoshi, Akira Nakamura

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, 4, 2017 Peer-reviewed
Numerical simulation of long-period fluid temperature fluctuation at a mixing tee for the thermal fatigue problem

Yoichi Utanohara, Akira Nakamura, Koji Miyoshi, Naoto Kasahara

Nuclear Engineering and Design, 305 639-652, Aug, 2016 Peer-reviewed
Measurement of Flow Accelerated Corrosion Rate at an Elbow Pipe and Combination Effect of an Upstream Orifice

Yoichi UTANOHARA, Koichi KAMAHORI, Akira NAKAMURA, Michio MURASE

Japan Society of Maintenology, E-Journal of Advanced Maintenance, 8(1) 1-12, May, 2016 Peer-reviewed
An investigation of thermal stress characteristics by wall temperature measurements at a mixing tee

Koji Miyoshi, Masayuki Kamaya, Yoichi Utanohara, Akira Nakamura

Nuclear Engineering and Design, 298 109-120, Mar, 2016 Peer-reviewed
A review of evaluation methods developed for numerical simulation of the temperature fluctuation contributing to thermal fatigue of a T-junction pipe

Akira NAKAMURA, Yoichi UTANOHARA, Koji MIYOSHI, Naoto KASAHARA

Japan Society of Maintenology, E-Journal of Advanced Maintenance, 6(4) 118-130, Feb, 2015 Peer-reviewed
An investigation of wall temperature characteristics to evaluate thermal fatigue at a T-junction pipe

Koji MIYOSHI, Akira NAKAMURA, Yoichi UTANOHARA, Nobuyuki TAKENAKA

JSME, Mechanical Engineering Journal, 1(5) TEP0050-1-TEP0050-12, Oct, 2014 Peer-reviewed
Development of thermal fatigue evaluation methods of piping systems

Naoto KASAHARA, Takamoto ITOH, Masakazu OKAZAKI, Yukihiko OKUDA, Masayuki KAMAYA, Akira NAKAMURA, Hitoshi NAKAMURA, Hideo MACHIDA, Masaaki MATSUMOTO

Japan Society of Maintenology, E-Journal of Advanced Maintenance, 6(1) 14-23, May, 2014 Peer-reviewed
Temperature fluctuation phenomena in a normally stagnant pipe connected downward to a high velocity and high temperature main pipe

Akira Nakamura, Koji Miyoshi, Toru Oumaya, Nobuyuki Takenaka, Shigeo Hosokawa, Daisuke Hamatani, Masatsugu Hase, Daisuke Onojima, Yasuhiro Yamamoto, Atsushi Saito

Nuclear Engineering and Design, 269 360-373, Apr, 2014 Peer-reviewed
Numerical evaluation of wall temperature measurement method developed to estimate thermal stress at T-junction pipe

Koji MIYOSHI, Akira NAKAMURA, Nobuyuki TAKENAKA

JSME, Mechanical Engineering Journal, 1(2) TEP0006-1-TEP0006-14, Apr, 2014 Peer-reviewed
An investigation of wall temperature characteristics to improve the evaluation method for thermal fatigue at a T-junction pipe

Koji Miyoshi, Akira Nakamura, Nobuyuki Takenaka

Proceedings of the 15th International Heat Transfer Conference, IHTC 2014, 2014
Flow and temperature fluctuation mechanism in a downward branch pipe with a closed end (5th. report, Investigation of fluctuation mechanism for penetration depth)

Koji MIYOSHI, Akira NAKAMURA, Takahiro TOKURA, Katsumi SUGIMOTO, Nobuyuki TAKENAKA

Transactions of the JSME (in Japanese), 80(817) FE0255-FE0255, 2014 Peer-reviewed
Flow and temperature fluctuation mechanism in a downward branch pipe with a closed end (4th. report, Influence of inner diameter on penetration depth and fluctuation characteristics)

Koji MIYOSHI, Akira NAKAMURA, Takahiro TOKURA, Katsumi SUGIMOTO, Nobuyuki TAKENAKA

Transactions of the JSME (in Japanese), 80(810) FE0026-FE0026, 2014 Peer-reviewed
Correlation between Flow Accelerated Corrosion and Wall Shear Stress Downstream from an Orifice

Yoichi UTANOHARA, Yukinori NAGAYA, Akira NAKAMURA, Michio MURASE, Koichi KAMAHORI

JSME, Journal of Power and Energy Systems, 7(3) 138-147, Sep, 2013 Peer-reviewed
Verification and Validation of One-Dimensional Flow-Accelerated Corrosion Evaluation Code

Hiroaki Suzuki, Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Souji Koikari, Yukihiko Nagaya, Akira Nakamura, Seiichi Koshizuka, Derek H. Lister

Nuclear Technology, 183(1) 62-74, Jul, 2013 Peer-reviewed

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Misc.

65

Numerical Simulation of Thermal Stress Fluctuation at a Mixing Tee for Thermal Fatigue Problems

INSS journal : Journal of the Institute of Nuclear Safety System, 27 105-116, 2020
Data for Validation to Improve Fluid-structure Thermal Coupled Simulation Methods at a Mixing Tee with Upstream Elbow

INSS journal : Journal of the Institute of Nuclear Safety System, 26 228-250, 2019
Conjugate Numerical Simulation of Wall Temperature Fluctuation at a T-junction Pipe

INSS journal : Journal of the Institute of Nuclear Safety System, 25 63-74, 2018
Data for validation to improve fluid-structure thermal coupled simulation methods at a mixing tee

INSS journal : Journal of the Institute of Nuclear Safety System, 25 156-173, 2018
Study on Characteristics of Wall Temperature Fluctuation at a Mixing Tee (Effect of Upstream Elbow)

INSS journal : Journal of the Institute of Nuclear Safety System, 24 81-89, 2017
Effects of Local Flow Field on Flow Accelerated Corrosion : Wall Thinning Rate at an Elbow Pipe and Combination Effect of an Upstream Orifice

INSS journal : Journal of the Institute of Nuclear Safety System, 23 44-52, 2016
Flow Structure in a Downward Branch Pipe with a Closed End : Characteristics of Flow Velocity in the Branch Pipe

INSS journal : Journal of the Institute of Nuclear Safety System, 23 53-59, 2016
OS0608-126 Study of thermal stress characteristics by wall temperature measuring experiments at a T-junction

MIYOSHI Koji, KAMAYA Masayuki, NAKAMURA Akira

2015 "OS0608-126-1"-"OS0608-126-3", Nov 21, 2015
A122 Large Eddy Simulation of Temperature Fluctuation Downstream from a Mixing Tee : Long-period Fluid Temperature Fluctuation

UTANOHARA Yoichi, NAKAMURA Akira, MIYOSHI Koji, KASAHARA Naoto

National Symposium on Power and Energy Systems, 2015(20) 13-14, Jun 7, 2015
A232 A study of fluid phenomena in a downward branch pipe with a closed end : Fluctuation mechanism for penetration depth

MIYOSHI Koji, TOKURA Takahiro, MAEDA Shogo, SUGIMOTO Katsumi, TAKENAKA Nobuyuki, Nakamura Akira

National Symposium on Power and Energy Systems, 2015(20) 201-204, Jun 7, 2015
A241 Evaluation of wall thinning rate of FAC and mass transfer coefficient in elbow : (5) Measurement of flow accelerated corrosion rate in an elbow pipe and effect of flow velocity on corrosion rate

KAMAHORI Koichi, UTANOHARA Yoichi, NAKAMURA Akira, MURASE Michio

National Symposium on Power and Energy Systems, 2015(20) 213-214, Jun 7, 2015
A242 (6) Evaluation of wall thinning rate of FAC and mass transfer coefficient in elbow : Direct mass transfer measurement in elbow

KAMIYA Kazuaki, TSUNEYOSHI Tatsuya, KATAI Yuki, KAMAHORI Koichi, UTANOHARA Yoichi, NAKAMURA Akira, MURASE Michio, TSUJI Yoshiyuki

National Symposium on Power and Energy Systems, 2015(20) 215-216, Jun 7, 2015
A243 Evaluation of wall thinning rate of FAC and mass transfer coefficient in elbow : (7) Numerical estimation of mass transfer coefficient in high Reynolds number elbow flow

TSUNEYOSHI Tatsuya, KAMIYA Kazuaki, KATAI Yuki, KAMAHORI Koichi, UTANOHARA Yoichi, NAKAMURA Akira, MURASE Michio, TSUJI Yoshiyuki

National Symposium on Power and Energy Systems, 2015(20) 217-218, Jun 7, 2015
(9)Correlation between Flow Accelerated Corrosion and Wall Shear Stress Downstream from an Orifice

Journal of the Japan Society of Mechanical Engineers, 118(1158) 259-259, May 5, 2015
Flow Structure in a Downward Branch Pipe with a Closed End : Effect of Branch Pipe Shapes on Flow Structure

INSS journal : Journal of the Institute of Nuclear Safety System, 22 47-54, 2015
Numerical Simulations of Thermal Striping at T-junction Pipe(3rd Report)The Effects of Inlet Boundary Conditions on Temperature Fluctuation Intensity

INSS journal : Journal of the Institute of Nuclear Safety System, 22 71-83, 2015
A review of evaluation methods developed for numerical simulation of the temperature fluctuation contributing to thermal fatigue of a T-junction pipe

INSS journal : Journal of the Institute of Nuclear Safety System, 22 213-224, 2015
J0560104 Thermal fatigue of pipes induced by fluid temperature change : Temperature fluctuation evaluation at pipe wall using fluid-structure coupled simulation

NAKAMURA Akira, UTANOHARA Yoichi, MIYOSHI Koji, Kasahara Naoto

Mechanical Engineering Congress, Japan, 2014 "J0560104-1"-"J0560104-5", Sep 7, 2014
F082005 Draft Revised Roadmap for Improvement of Pipe-Wall Thinning Management

INADA Fumio, WATANABE Yutaka, NAKAMURA Akira

Mechanical Engineering Congress, Japan, 2014 "F082005-1"-"F082005-2", Sep 7, 2014
A123 Evaluation of wall thinning rate of FAC and mass transfer coefficient in elbow : (3) Numerical estimation of mass transfer coefficient in INSS elbow

TSUNEYOSHI Tatsuya, KATAI Yuki, KAMAHORI Koichi, UTANOHARA Yoichi, NAKAMURA Akira, MURASE Michio, ITO Takahiro, TSUJI Yoshiyuki

National Symposium on Power and Energy Systems, 2014(19) 15-16, Jun 25, 2014

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Presentations

9

DEVELOPMENT OF ESTIMATION METHOD USING MACHINE LEARNING TO EVALUATE BREAK DIAMETER IN PWR LOSS-OF-COOLANT ACCIDENT

Akira NAKAMURA, Takayoshi KUSUNOKI

2023 30th International Conference on Nuclear Engineering (ICONE30), May 24, 2023
Numerical simulations of cesium distribution of Fukushima-Daiichi nuclear power plant accident and its uncertainty caused by computational mesh

Akira NAKAMURA, Takayoshi KUSUNOKI

2017 The International Congress on Advances in Nuclear Power Plants (ICAPP2017), Apr 25, 2017, AESJ
Evaluation of Penetration Length in a Closed Straight Two-inch Branch Pipe Using Numerical Simulations

Akira Nakamura, Koji Miyoshi, Nobuyuki Takenaka

The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Nov 16, 2014, AESJ
SIMULATION OF THERMAL STRIPING AT T-JUNCTION PIPE USING LES WITH SMAGORINSKY CONSTANTS AND TEMPERATURE DIFFUSION SCHEMES

Akira NAKAMURA, Yoichi UTANOHARA, Koji MIYOSHI, Naoto KASAHARA

The Experimental Validation and Application of CFD and CMFD Codes in Nuclear Reactor Technology, CFD4NRS-4, OECD/NEA and IAEA Workshop, Sep 10, 2012, OECD
BENCHMARK SIMULATION OF TEMPERATURE FLUCTUATION USING CFD FOR THE EVALUATION OF THE THERMAL LOAD IN A T-JUNCTION PIPE

Akira NAKAMURA, Hiroshi IKEDA, Shaoxiang QIAN, Masaaki TANAKA, Naoto KASAHARA

The Seventh Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Nov 14, 2010, AESJ
Numerical Investigation of Thermal Striping at a Mixing Tee Using Detached Eddy Simulation

Akira Nakamura, Toru Oumaya, Nobuyuki Takenaka

The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH13), Sep 27, 2009, AESJ
AN APPROACH OF INTEGRATED EVALUATION METHOD FOR THERMAL FATIGUE AND ITS VALIDATION APPLYING SPECTRA TEST

Akira Nakamura, Toru Oumaya

15th International Conference on Nuclear Engineering (ICONE15), Apr 22, 2007, JSME
Experiments on flow-induced in-line oscillation of a cantilevered circular cylinder

Akira NAKAMURA, Atsuhsi OKAJIMA, Takashi KOSUGI, Ryouji TAMAKI

The Fifth JSME-KSME Fluids Engineering Conference, Nov 18, 2002, JSME
A Numerical Simulation and Vortex Structures of In-Line Oscillation of a Elastically Supported Circular Cylinder

Akira NAKAMURA, Atsushi OKAJIMA

ASME-PVP Conference, 2001, "Symposium on Flow-Induced Vibration-2001", Jul 22, 2001, ASME

Professional Memberships

2

Research Projects

1

Research and Development on Shapes of Non-Vibrational Thermocouple in the Pipe System of Industrial Plants

Grants-in-Aid for Scientific Research, Grant-in-Aid for Scientific Research (B), Japan Society for the Promotion of Science, 2002 - 2004

OKAJIMA Atsushi, OKANO Yukimitsu, MIZOTA Takehito, KIMURA Sigeo, NAKAMURA Akira, KIWATA Takahiro