Minoru Takahashi - My portal

Profile Information

Affiliation: Professor Emeritus, Tokyo Institute of Technology

Degree: Doctor of Engineering(Tokyo Institute of Technology)
Doctor of Engineering(Tokyo Institute of Technology)

Researcher number: 90171529
J-GLOBAL ID: 200901059056612338
researchmap Member ID: 1000161758

Research Interests

Research Areas

Research History

2016 - 2018

Professor, Institute of Innovative Research, Tokyo Institute of Technology
2013 - 2016

Professor, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
2007 - 2013

Associate Professor, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
1997 - 2007

Associate Professor, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
1984 - 1997

Assistant professor, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
1982 - 1984

Researcher, Fast Reactor Engineering Section, Fast Reactor Safety Division, Power Reactor and Nuclear Fuel Development Corporation
1980 - 1982

Researcher, Sodium Thermal-hydraulics Section, Sodium Technology Division, Power Reactor and Nuclear Fuel Development Corporation

Education

Committee Memberships

2005 - 2005

評議員, 日本伝熱学会

Awards

Oct, 1983

Award of O-arai Engineering Center Chair, Establishment of Cavitation Free Structure of Core Fuel Assemblies in Prototype Fast Reactor "Monju", Power Reactor and Fuel Development Corporation

Papers

Design Study of Small Lead-Cooled Fast Reactor Cores Using SiC Cladding and Structure

Abu Khalid Rivai, Minoru Takahashi

Journal of Power and Energy Systems, 1(2) 134-142, 2007 Peer-reviewed
Experiment and Numerical Simulation of Bubble Behavior in Argon Gas Injection into Lead-Bismuth Pool

Yumi Yamada, Toyou Akashi, Minoru Takahashi

Journal of Power and Energy Systems, 1(1) 87-98, 2007 Peer-reviewed
Experimental and Analytical Study of Lead-Bismuth-Water Direct Contact Boiling Two-Phase Flow

Novitrian, Vaclav Dostal, Minoru Takahashi

Journal of Power and Energy Systems, 1(1) 76-86, 2007 Peer-reviewed
Study on control of oxygen concentration in lead-bismuth flow using lead oxide particles

Masatoshi Kondo, Minoru Takahashi, Kuniaki Miura, Tatsuya Onizawa

JOURNAL OF NUCLEAR MATERIALS, 357(1-3) 97-104, Oct, 2006 Peer-reviewed
Corrosion resistance of Si- and Al-rich steels in flowing lead-bismuth

Masatoshi Kondo, Minoru Takahashi

JOURNAL OF NUCLEAR MATERIALS, 356(1-3) 203-212, Sep, 2006 Peer-reviewed
Corrosion of steels with surface treatment and Al-alloying by GESA exposed in lead-bismuth

A Heinzel, M Kondo, M Takahashi

JOURNAL OF NUCLEAR MATERIALS, 350(3) 264-270, May, 2006 Peer-reviewed
Corrosion of steels in lead-bismuth flow

M Kondo, M Takahashi, N Sawada, K Hata

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 43(2) 107-116, Feb, 2006 Peer-reviewed
Metallurgical Analysis for Ruptured Tube in Lead Bismuth Corrosion Test Facility

Masatoshi KONDO, Minoru TAKAHASHI

Journal of Nuclear Science and Technology, 43(2) 174-178, 2006 Peer-reviewed
Metallurgical study on erosion and corrosion behaviors of steels exposed to liquid lead-bismuth flow

M Kondo, M Takahashi, T Suzuki, K Ishikawa, K Hata, SZ Qiu, H Sekimoto

JOURNAL OF NUCLEAR MATERIALS, 343(1-3) 349-359, Aug, 2005 Peer-reviewed
Study and Pre-experimental Operation of ESP-PDA System for Pb-Bi Droplet Measurement in Steam Flow

E. Yusibani Y, Pramono M.Takahashi

Indonesian Journal of Physics, 16(1) 1-6, 2005 Peer-reviewed
7 MPa Commissioning of Two-phase Flow Loop for Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor

Y. Pramono, M, Takahashi, H. Sofue, M, Matsumoto, F. Huang

Indonesian Journal of Physics, 16(1) 7-12, 2005 Peer-reviewed
Pressure wave propagation in air-water bubbly and slug flow

F Huang, M Takahashi, LJ Gu

PROGRESS IN NUCLEAR ENERGY, 47(1-4) 648-655, 2005 Peer-reviewed
Study on Pb-Bi-water direct contact boiling two-phase flow and heat transfer

M Takahashi, H Sofue, T Iguchi, Y Pramono, F Huang, Novitrian, M Matsumoto, T Matsuzawa, S Uchida

PROGRESS IN NUCLEAR ENERGY, 47(1-4) 569-576, 2005 Peer-reviewed
Study on Pb-Bi natural circulation phenomena

M Takahashi, H Sofue, T Iguchi, M Matsumoto, F Huang, Y Pramono, T Matsuzawa, S Uchida

PROGRESS IN NUCLEAR ENERGY, 47(1-4) 553-560, 2005 Peer-reviewed
Metallurgical study on electro-magnetic flow meter and pump for liquid lead-bismuth flow

M Kondo, M Takahashi

PROGRESS IN NUCLEAR ENERGY, 47(1-4) 639-647, 2005 Peer-reviewed
Experimental studies on steel corrosion in Pb-Bi with steam injection

K Hata, K Hara, M Takahashi

PROGRESS IN NUCLEAR ENERGY, 47(1-4) 596-603, 2005 Peer-reviewed
Pb-Bi-cooled direct contact boiling water small reactor

M Takahashi, S Uchida, K Hata, T Matsuzawa, H Osada, Y Kasahara, N Sawa, Y Okubo, T Obara, E Yusibani

PROGRESS IN NUCLEAR ENERGY, 47(1-4) 190-201, 2005 Peer-reviewed
Design study of Pb-Bi- and NaK-cooled small deep sea fast reactors

A Otsubo, M Takahashi

PROGRESS IN NUCLEAR ENERGY, 47(1-4) 202-211, 2005 Peer-reviewed
First-principles molecular dynamics simulation on interatomic interaction of Fe crystal with Pb and Bi atoms

M Takahashi, YX Qi, H Nitta, N Nishikawa, T Ohno

SCIENCE AND TECHNOLOGY OF ADVANCED MATERIALS, 5(5-6) 673-676, Sep, 2004 Peer-reviewed
短い細管ノズルから流出する高温水の二相流動特性（第2報：蒸発を伴う二相噴流の流動特性）

浜田広次, 高橋実, 井上晃, 有冨正憲

日本機械学会論文集，B編, 70(690) 332-339, 2004 Peer-reviewed

Misc.

Core Characteristics of Small Lead Alloy Cooled Fast Reactor for Various Fuel Types and Cladding-Structure Materials

2007
鉛重金属冷却高速炉の現状と展望

高橋実

2007
Safety Design of Pb-Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR)

2006
First-principles molecular dynamics simulation on interatomic interaction of Fe crystal with Pb and Bi atoms

M Takahashi, YX Qi, H Nitta, N Nishikawa, T Ohno

SCIENCE AND TECHNOLOGY OF ADVANCED MATERIALS, 5(5-6) 673-676, Sep, 2004
Metallurgical Study and Performance of Electro-magnetic Flow Meter for a Liquid Lead-bismuth Flow

2004
Studies on Pb-Bi Flow Technology and Steel Compatibility with Pb-Bi

2004
Study on Pb-Bi-Steam Two-Phase Flow for Evaluation of Lift Pump Performance in PBWFR

2004
Studies for Development of PBWFR

2004
Wall Superheat of Subcooled Sodium Flow Boiling in Vertical Annulus

2 I47, 467, 2002
磁場閉じ込め核融合炉における液体金属二相流却冷システムの電磁流体力学的特性と熱伝達に関する研究

27 663, 1995
平行強磁場下における水銀単相流と空気-水銀二相流の流動・伝熱特性

電磁流体力学, 31(4) 397, 1995
磁場閉じ込め核融合炉における高熱負荷面の2次元衡突噴流冷却

核融合工学と設計, 28 81, 1995
非一様な平行強磁場下における磁性流体の液体単相流と気液二相流

20(6) 1095, 1994
流動系における原子炉級黒鉛の酸化の焼損とCOとCO_2_生成

31(12) 1275, 1994
強磁場下における水銀のプール沸騰熱伝達

実験熱流体科学, 8 67, 1994
鉛直磁場下における空気一水銀層状二相流の流動・伝熱特性

8 46, 1994
水平磁場下における水銀の核沸騰

(148) 626, 1993
磁場閉じ込め核融合炉の液体金属沸騰冷却に関する基礎的研究

高橋実

平成3年度科学研究費補助金（一般研究C）研究成果報告書, 1992
Benchmark Analysis for Multi-dimensional Thermal-Hydraulic Analysis Codes (Phase 1) Upper Plenum Thermal Stratification Analysis with COMMIX-1A, SKORT-II, THAUPR-III and THERVIS-II

Takahashi, M. Tamura, S. Iguchi, T

PNC SN941, (84-91), 1984
Benchmark Analysis for Multi-dimensional Thermal-Hydraulic Analysis Codes (Phase 2) Upper Plenum Thermal Stratification Analysis with VARR-II

Akamatsu, M. Takitani, K. Takahashi, M. Iguchi, T

(84-92), 1984

Books and Other Publications

混相流計測法

森北出版, 2003

Presentations

197

加速器BNCTターゲット兼冷却材用液体リチウムの流動方式

日本混相流学会年会講演会2009, 2009
加速器BNCTターゲット兼冷却材用リチウム液幕噴流の基本的安定性

日本機械学会2009年度年次大会講演会, 2009
加速器中性子捕捉療法用液体リチウム液膜流ターゲットの開発（2）陽子線加速器中性子によるホウ素中性子捕捉療法（BNCT）

日本原子力学会 2009年秋の大会, 2009
加速器BNCTターゲット兼冷却材用リチウムの平板流下液膜内の境界層構造

日本機械学会第87期流体工学部門講演会, 2009
加速器BNCTターゲット兼冷却材用リチウムの凹曲板流下液膜の遠心力不安定

日本機械学会第87期流体工学部門講演会, 2009
Conceptual Study of Lead-Bismuth-Cooled Fast Reactor (PBWFR) and Its Applicability to Chemical Industrial Complex

Tokyo Tech-MIT Symposium, 2008
高速炉のナトリウムキャビテーションに関する研究；（II）キャビテーション初生条件と音響ノイズ特性の試験

日本原子力学会2008年秋の大会（高知）, 2008
高速炉のナトリウムキャビテーションに関する研究；（I）実機設計における課題とキャビテーション試験技術

日本原子力学会2008秋の大会（高知）, 2008
Acoustic Noise and Onset of Sodium Cavitation in Venturi

The 6th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), 2008
Corrosion Behavior of Al-Fe-Sputtering-Coated Steel, High Chromium Steels, Refractory Metals and Ceramics in High Temperature Pb-Bi

2007 International Congress on Advances in Nuclear Power Plants (ICAPP 2007), 2007
Studies for Development of Lead-Alloy-Cooled Fast Reactors

ANINS 2007, 2007
Status and Prospect of Development of Lead-Alloy-Cooled Fast Reactor

International Conference on Advances in Nuclear Science and Engineering (ICANSE 2007), 2007
Corrosion Resistance of Alloy-Sputtering-Coated Steels and High Chromium Steels in Pb-Bi at Transient Temperature Conditions

International Conference on Advances in Nuclear Science and Engineering (ICANSE 2007), 2007
Performance of Oxygen Sensor and Corrosion of Surface-Coated Steels, Ceramics and Refractory Metals in High Temperature LBE

Workshop on Structural Materials for Innovative Nuclear Systems (SMINS) in co-operation with the International Atomic Energy Agency, 2007
Characteristics of Zirconia Solid Electrolyte Sensor in Lead and Lead-bismuth under Control of Oxygen Potential

IV International Workshop on Materials for HLM Cooled Reactors and Related Technologies, 2007
Corrosion Behavior of Al-Fe-Coated Steels and High Chromium Steels in High Temperature Pb-Bi

IV International Workshop on Materials for HLM Cooled Reactors and Related Technologies, 2007
Corrosion Resistance of Refractory Metals and Ceramics in Lead-bismuth at 700oC

5th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, 2007
Experimental Study of Molten Pb-Bi Droplets Impinging on Surface at Various Angles in Gas Flow

Proceedings of 15th International Conference on Nuclear Engineering (ICONE 15), 2007
Visualization of Lead-Bismuth-Water/Steam Direct Contact Boiling Two-Phase Flow Using Gamma-ray Radiography

Proceedings of 15th International Conference on Nuclear Engineering (ICONE 15), 2007
Numerical Analysis of Lead-bismuth-water Direct Contact Boiling Heat Transfer

Proceedings of 15th International Conference on Nuclear Engineering (ICONE 15), 2007

Professional Memberships

Works

原子力安全基盤調査研究（高温・高流速ナトリウムのキャビテーション特性）

2007 - 2009 Artistic work
Pb-Bi冷却直接接触沸騰水型小型高速炉に関する技術開発

2003 - 2004 Artistic work
Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor

2002 - 2004 Artistic work
鉛ビスマス用電磁流量計及びベローズバルブに関する技術開発

2003 - 2003 Artistic work
Study on Corrosion Test Technology in a Flowing Lead-Bismuth Eutectic Alloy

2001 - 2002 Artistic work
Study on Material Corrosion in Pb-Bi

2000 - 2000 Artistic work
Study on Liquid Metal for Coolant of Nuclear Reactors

2000 - 2000 Artistic work
Interfacial Wave and Turbulence in Downward Thick Film Flow

1999
Corrosion of Material in Molten Lead-Bismuth

1999
Two-Dimensional Turbulence in a Mercury Flow in the Presence of a Transverse Magnetic Field

1998
構造体中のLi流動特性に関する研究

1996 - 1997
Turbulence Structure in Liguid Phase of Air-Water Stratified Flow

1996 - 1996
MHD Pressure Drop and Heat Transfer of Lithium Single-Phase Flow in a Rectangular Channel under Transverse Magnetic Field

1996 - 1996
Damping of Turbulence in a Mercury Flow in the Presemce of a Transverse Magnetic Field

1996 - 1996
スチームインジェクタ内部の伝熱流動メカニズムの基礎研究

1994 - 1996
Flow Control Charateristics of Gas-Magnetic Fluid Two-Phase Flow in the Preaence of a Non-Uniforw Magnetic Field

1995 - 1995
Heal Transfer of Plasma Impinging Jet

1994 - 1994
Flow Characteristics and Heat transfer of Liquid Metal Single-Phase and Gas-liquid Two-Phase Flows under a Strong Longitudinal Magnetic Field

1993 - 1994
高温ガス炉の事故時における固有安全性の確保と環境影響の低減化

1993 - 1993
Two-Dimensional Impinging Jet Cooling of High Heat Flux Surface in Magnetic Confinement Fusion Reactor

1992 - 1993

Research Projects

Study on lithium film flow for neutron capture therapy

2008 - 2011
Study on Sodium Cavitation

2007 - 2010
Pb-Bi-Water Direct Contact Boiling Two-Phase Flow

Nuclear and Atomic Science Research, 2002 - 2010
Conceptual Study of Pb-Bi-Cooled Small Fast Reactor

2002 - 2010
Development of Corrosion-resistant Materials for Lead Alloy Coolants

1999 - 2010