Details of the Researcher

PHOTO

Shinji Ebara
Section
Graduate School of Engineering
Job title
Associate Professor
Degree
  • 博士(工学)(東北大学)

  • 修士(工学)(東北大学)

Research History 2

  • 2009/04 - Present
    Tohoku University Graduate School of Engineering, Department of Quantum Science and Energy Engineering

  • 2000/04 - 2009/03
    九州大学 大学院総合理工学研究院

Education 4

  • Tohoku University

    - 2000

  • Tohoku University Graduate School, Division of Engineering

    - 2000

  • Tohoku University Faculty of Engineering

    - 1995

  • Tohoku University Faculty of Engineering

    - 1995

Committee Memberships 20

  • 核融合科学研究所 核融合科学研究所運営会議共同研究委員会委員

    2021/04 - Present

  • 日本学術振興会 科学研究費委員会専門委員 2段階書面審査委員

    2020/12 - 2021/11

  • 日本原子力学会 核融合工学部会 庶務幹事

    2017/04 - 2018/03

  • 日本原子力学会 核融合工学部会 庶務幹事

    2017/04 - 2018/03

  • 日本原子力学会・編集委員会 編集委員

    2014/07 - 2017/06

  • 日本原子力学会・編集委員会 編集委員

    2014/07 - 2017/06

  • 動力エネルギーシステム部門 第19回動力・エネルギー技術シンポジウム 実行委員会 委員

    2014/02 - 2014/06

  • 動力エネルギーシステム部門 第19回動力・エネルギー技術シンポジウム 実行委員会 委員

    2014/02 - 2014/06

  • 日本原子力学会・企画小委員会 委員長

    2012/04 - 2014/03

  • 日本原子力学会・企画小委員会 委員長

    2012/04 - 2014/03

  • 第16回動力・エネルギー技術シンポジウム 実行委員会 委員

    2010/10 - 2011/06

  • 第16回動力・エネルギー技術シンポジウム 実行委員会 委員

    2010/10 - 2011/06

  • 第8回核融合エネルギー連合講演会 組織委員会 委員

    2009/06 - 2010/12

  • 第8回核融合エネルギー連合講演会 組織委員会 委員

    2009/06 - 2010/12

  • プラズマ・核融合学会 編集委員会 企画委員

    2008/07 - 2010/06

  • プラズマ・核融合学会 編集委員会 企画委員

    2008/07 - 2010/06

  • 日本原子力学会・核融合工学部会 運営委員 庶務担当

    2009/04 - 2010/03

  • 日本原子力学会・核融合工学部会 運営委員 庶務担当

    2009/04 - 2010/03

  • 日本機械学会「配管減肉管理改善に向けた基盤技術研究分科会」 委員

    2009/06 -

  • 日本機械学会「配管減肉管理改善に向けた基盤技術研究分科会」 委員

    2009/06 -

Show all ︎Show first 5

Professional Memberships 5

  • Japan Society of Maintenology

  • The Japan Society of Plasma Science and Nuclear Fusion Research

  • Japan Society of Mechanical Engineers

  • Heat Transfer Society of Japan

  • Atomic Energy Society of Japan

Research Interests 8

  • flow simulation

  • PIV

  • visualization experiment

  • porous media

  • heat-transfer engineering

  • fluid engineering

  • nuclear engineering

  • fusion engineering

Research Areas 4

  • Manufacturing technology (mechanical, electrical/electronic, chemical engineering) / Thermal engineering /

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

  • Energy / Nuclear engineering /

  • Energy / Nuclear fusion /

Papers 82

  1. Experimental study of boiling heat transfer characteristics of multi-elbow cooling system under one-sided heating with long section for fusion divertor cooling Peer-reviewed

    Shuta Nakano, Yukinori Hamaji, Shinji Ebara, Hidetoshi Hashizume

    Fusion Engineering and Design 204 114408-114408 2024/07

    Publisher: Elsevier BV

    DOI: 10.1016/j.fusengdes.2024.114408  

    ISSN: 0920-3796

  2. Feasibility Study on Liquid Divertor Using Molten Salt Free Surface Flow with Turbulent Promoters Peer-reviewed

    Takahiro IJIMA, Shota SAKURAI, Fumiya TAKAHASHI, Shinji EBARA, Hidetoshi HASHIZUME

    Plasma and Fusion Research 18 2405075-2405075 2023/08/28

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.18.2405075  

    eISSN: 1880-6821

  3. Heat Transfer Characteristics Evaluation of Multi-Elbow Cooling System for Fusion Divertor under One-Sided Heating Peer-reviewed

    Shinji EBARA, Kenya MITOBE, Yukinori HAMAJI, Hidetoshi HASHIZUME

    Plasma and Fusion Research 18 2405034-2405034 2023/06/05

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.18.2405034  

    eISSN: 1880-6821

  4. Relationship between frequency characteristic of turbulent velocity fluctuation and wall thinning rate by flow-accelerated corrosion Peer-reviewed

    Tatsuru KANEKO, Shinji EBARA, Hidetoshi HASHIZUME

    E-Journal of Advanced Maintenance 11 (2) 92-98 2019

  5. EXPERIMENTAL INVESTIGATION OF INFLUENCE OF TURBULENT NEAR-WALL FLOW ON FLOW ACCELERATED CORROSION BEHIND AN ORIFICE Peer-reviewed

    T. Kaneko, S. Ebara, H. Hashizume

    Proceedings of The 29th International Symposium on Transport Phenomena ISTP29-153 2018/11

  6. Flow Field Investigation in a Cooling Channel with Finger-Stacked Structure Using PIV Measurement Peer-reviewed

    Shohei YASUNAGA, Shinji EBARA, Hidetoshi HASHIZUME

    Proceedings of the 11th International Symposium on Advanced Science and Technology in Experimental Mechanics 57-Shohei YASUNAGA-770.pdf 2016/11

  7. HEAT TRANSFER CHARACTREISTIC OF SPHERE-PACKED RECTANGULAR CHANNEL FOR HIGH PRANDTL NUMBER FLUID UNDER ONE-SIDED HEATING CONDITION Peer-reviewed

    Dorota Smakulska, Shohei Yasunaga, Shinji Ebara, Hidetoshi Hashizume

    Proceedings of the 4th International Forum on Heat Transfer Paper ID IFHT2016-2041 2016/11

  8. Characteristics of Flow Field and Pressure Fluctuation in Complex Turbulent Flow in the Third Elbow of a Triple Elbow Piping with Small Curvature Radius in Three-dimensional Layout Peer-reviewed

    Shinji Ebara, Hiroyuki Takamura, Hidetoshi Hashizume, Hidemasa Yamano

    Proceedings of the 17th International Conference on Emerging Nuclear Energy Sciences (ICENES 2015) Paper 1117.pdf 2015/10

  9. Evaluation of influence of the inlet swirling flow on the flow field in a triple elbow system Peer-reviewed

    Jun Mizutani, Shinji Ebara, Hidetoshi Hashizume

    Proceedings of the 17th International Conference on Emerging Nuclear Energy Sciences (ICENES 2015) Paper 1110.pdf 2015/10

  10. Influence of Piping Layout upon the Characteristics of Flow Separation and Pressure Fluctuation in the Primary Cold-leg of Sodium Cooled Fast Reactor Peer-reviewed

    Jun Mizutani, Shinji Ebara, Hidetoshi Hashizume, Hidemasa Yamano

    Proceedings of the 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10) NUTHOS10-1085 2014/12

  11. Visualization experiment of complex flow field in a sphere-packed pipe by detailed PIV measurement Peer-reviewed

    Shinji Ebara, Mohammad Reza Nematollahi, Hidetoshi Hashizume

    FUSION ENGINEERING AND DESIGN 89 (7-8) 1251-1256 2014/10

    DOI: 10.1016/j.fusengdes.2014.03.079  

    ISSN: 0920-3796

    eISSN: 1873-7196

  12. FEASIBILITY STUDY OF APPLICATION OF A SELF-FORMED FLOW FIELD DOWNSTREAM OF ELBOWS TO DIVERTOR COOLING Peer-reviewed

    Shoichi Kodate, Tatsuya Kubo, Shinji Ebara, Hidetoshi Hashizume

    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 5 ICONE21-16105 2014

    DOI: 10.1115/ICONE21-16105  

  13. FLOW VISUALIZATION EXPERIMENT OF A SWIRLING FLOW FORMED DOWNSTREAM OF A PIPING WITH SUCCESSIVE THREE ELBOW TO BE APPLIED TO DIVERTOR COOLING Peer-reviewed

    Shoichi Kodate, Shinji Ebara, Hidetoshi Hashizume

    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 6 ICONE22-30577 2014

    DOI: 10.1115/ICONE22-30577  

  14. Evaluation of heat transfer characteristics of a sphere-packed pipe for Flibe blanket Peer-reviewed

    Atsushi Watanabe, Shinji Ebara, Akio Sagara, Hidetoshi Hashizume

    FUSION ENGINEERING AND DESIGN 88 (9-10) 2357-2360 2013/10

    DOI: 10.1016/j.fusengdes.2013.01.051  

    ISSN: 0920-3796

    eISSN: 1873-7196

  15. INFLUENCE OF FREQUENCY CHARACTERISTICS OF VELOCITY FLUCTUATIONS IN COMPLEX TURBULENT FLOW DOWNSTREAM OF AN ORIFECE UPON PIPE WALL THINNING Peer-reviewed

    S. Ebara, H. Yanai, H. Hashizume

    Proceedings of The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics NURETH15-321 2013/05

  16. EXPERIMENTAL STUDY ABOUT THE INFLUENCE OF LIQUID FILM FORMED JUST DOWNSTREAM OF AN ORIFICE UPON PIPE WALL THINNING Peer-reviewed

    M. Umehara, S. Ebara, H. Hashizume

    Proceedings of The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics NURETH15-337 2013/05

  17. DEVELOPMENT OF PROPOSED GUIDELINE OF FLOW-INDUCED VIBRATION EVALUATION FOR HOT-LEG PIPING IN A SODIUM-COOLED FAST REACTOR Peer-reviewed

    Takaaki Sakai, Hidemasa Yamano, Masaaki Tanaka, Ayako Ono, Hiroyuki Ohshima, Tetsuya Kaneko, Kazuo Hirota, Hiromi Sago, Yang Xu, Yukiharu Iwamoto, Shinji Ebara, Takahiro Murakami, Takashi Nishihara, Akira Yamaguchi, Tomomichi Nakamura

    Proceedings of The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics NURETH15-042 2013/05

  18. 3.3 熱流動制御とモデリング(3.第一壁・ブランケットの物質熱輸送に関する研究,日米科学技術協力事業TITANプロジェクト) Peer-reviewed

    功刀 資彰, 横峯 健彦, 植木 祥高, 結城 和久, 佐竹 信一, 江原 真司, 橋爪 秀利

    プラズマ・核融合学会誌 89 (11) 2013/01

    Publisher: 社団法人プラズマ・核融合学会

    ISSN: 0918-7928

  19. Experimental Study of Influence of Elbow Curvature on a Swirling Flow Generated in a Three-Dimensionally Connected Dual Elbow Peer-reviewed

    Tatsuya KUBO, Shinji EBARA, Hidetoshi HASHIZUME

    E-Journal of Advanced Maintenance 5 (1) 34-41 2013

  20. Experimental evaluation of pipe wall thinning characteristics downstream of an orifice for an asymmetric swirling flow generated in a three-dimensionally- connected elbow piping as the inflow condition Peer-reviewed

    Shinji Ebara, Tatsuya Kubo, Hidetoshi Hashizume

    Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B 79 (808) 2616-2620 2013

    Publisher: Japan Society of Mechanical Engineers

    DOI: 10.1299/kikaib.79.2616  

    ISSN: 0387-5016

  21. EFFECTS OF SEPARATION VORTICES ON PRESSURE FLUCTUATION OF COMPLEX TURBULENT FLOW IN A DUAL ELBOW WITH SMALL CURVATURE RADIUS IN A THREE-DIMENSIONAL LAYOUT Peer-reviewed

    Shinji Ebara, Hiroaki Konno, Hidetoshi Hashizume, Tetsuya Kaneko, Hidemasa Yamano

    Proceedings of the Eighth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety N8P1048 2012/12

  22. VERIFICATION TEST OF A THREE-SURFACE-MULTI-LAYERED CHANNEL TO REDUCE MHD PRESSURE DROP Peer-reviewed

    Mitsuhiro Aoyagi, Yoshiki Inage, Satoshi Ito, Shinji Ebara, Yoshitaka Ueki, Kazuhisa Yuki, Feng-Chen Li, Sergey Smolentsev, Takehiko Yokomine, Tomoaki Kunugi, Tom Sketchley, Mohamed Abdou

    Proceedings of the Eighth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety N8P1089 2012/12

  23. Flow Visualization Experiment for Downstream of Orifices with Different Aperture Shapes

    Masako KATO, Shinji EBARA, Hidetoshi HASHIZUME

    Proceedings of 1st International Conference on Maintenance Science and Technology for nuclear Power Plants 165-166 2012/11

  24. Experimental Study of Influence of Elbow Curvature on a Swirling Flow Generated in a Three-Dimensionally Connected Dual Elbow

    Tatsuya KUBO, Shinji EBARA, Hidetoshi HASHIZUME

    Proceedings of 1st International Conference on Maintenance Science and Technology for nuclear Power Plants 115-116 2012/11

  25. Flow Visualization and Frequency Characteristics of Velocity Fluctuations of Complex Turbulent Flow in a Short Elbow Piping Under High Reynolds Number Condition Peer-reviewed

    Hiroyuki Takamura, Shinji Ebara, Hidetoshi Hashizume, Kosuke Aizawa, Hidemasa Yamano

    JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME 134 (10) 101201 2012/10

    DOI: 10.1115/1.4007436  

    ISSN: 0098-2202

  26. Prediction of unsteady flow field in a primary circuit hot-leg piping of a sodium-cooled fast reactor Peer-reviewed

    田中 正暁, 佐郷 ひろみ, 岩本 幸治, 江原 真司, 小野 綾子, 村上 貴裕, 早川 教

    日本機械学会論文集B編 78 (792) 1392-1396 2012/08

    Publisher: The Japan Society of Mechanical Engineers

    DOI: 10.1299/kikaib.78.1392  

    ISSN: 0387-5016

    More details Close

    A study on flow induced vibration in the primary cooling system of Japan Sodium cooled Fast Reactor (JSFR) consisting of large diameter pipe and pipe elbow with short curvature radius ("short-elbow") has been conducted. Flow-induced vibration in the short-elbow is an important issue in design study of JSFR, because it may affect to structural integrity of the pipe. In this paper, unsteady flow characteristics in the JSFR short-elbow pipe related to the large-scale eddy motion were estimated based on knowledge from existing studies for curved pipes and scaled water experiments and numerical simulations for the JSFR hot-leg piping.

  27. EXPERIMENTAL INVESTIGATION OF INFLUENCE OF INLET FLOW CONDITIONS ON SWIRLING FLOW GENERATED IN A THREE-DIMENSIONALLY CONNECTED DUAL ELBOW

    Tatsuya Kubo, Shinji Ebara, Hidetoshi Hashizume

    Proceedings of the 15th International Symposium on Flow Visualization ISFV15-105 2012/06

  28. FLOW STRUCTURE OF HIGH REYNOLDS NUMBER FLOW IN A DUAL-ELBOW PIPING SIMULATING COLD-LEGS OF JSFR

    H. Takamura, S. Ebara, H. Yamano, H. Hashizume

    Proceedings of the 15th International Symposium on Flow Visualization ISFV15-058 2012/06

  29. Study on Flow-Induced-Vibration Evaluation of Large-Diameter Pipings in a Sodium-Cooled Fast Reactor:(39)Estimation of multiple-elbow effect by means of PIV measurement afpplied to single and dual elbow flows by using a 1/7-scale model of the cold-leg piping

    Takamura Hiroyuki, Ebara Shinji, Hashizume Hidetoshi, Yamano Hidemasa

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012 265-265 2012

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2012f.0.265.0  

  30. Evaluation of heat transfer performance for a sphere-packed pipe by using molten salt under high heat flux condition

    A. Watanabe, S. Ebara, H. Hashizume

    21st International Toki Conference (ITC-21) 2011/11/28

  31. Pressure Fluctuation Characteristics of Complex Turbulent Flow in a Dual Elbow with Small Curvature Radius in a Three-dimensional Layout

    H. Konno, S. Ebara, H. Hashizume, H. Yamano, K. Aizawa

    Proceedings of the 8th International Conference on Flow Dynamics 94-95 2011/11/09

  32. Thermo-Fluid Simulation in a Liquid Metal Blanket with Three-Surface- Multi-Layered Channel Peer-reviewed

    M. Aoyagi, S. Ito, S. Ebara, T. Muroga, H. Hashizume

    Fusion Science and Technology 60 (2) 523-527 2011/08

  33. HEAT TRASFER EXPERIMENTS USING A HIGH PRANDTL NUMBER FLUID FLOWING IN SPHERE-PACKED CHANNELS FOR FLIBE BLANKET DESIGN Peer-reviewed

    Katsuya Shimizu, Shinji Ebara, Hidetoshi Hashizume

    FUSION SCIENCE AND TECHNOLOGY 60 (2) 528-532 2011/08

    ISSN: 1536-1055

  34. THERMO-FLUID SIMULATION IN A LIQUID METAL BLANKET WITH THREE-SURFACE-MULTI-LAYERED CHANNEL Peer-reviewed

    Mitsuhiro Aoyagi, Satoshi Ito, Shinji Ebara, Takeo Muroga, Hidetoshi Hashizume

    FUSION SCIENCE AND TECHNOLOGY 60 (1) 283-287 2011/07

    ISSN: 1536-1055

  35. PIV Measurements of a Complex Turbulent Flow in a Short Elbow Piping under a High Reynolds Number Condition

    H. Takamura, H. Konno, S. Ebara, H. Hashizume, K. Aizawa, H. Yamano

    Proceedings of The 9th International Symposium on Particle Image Velocimetry 2011/07

  36. Experimental Estimation in Characteristics of Swirling Flow Appearing in a Three-Dimensionally Connected Dual Elbow Layout by Means of Matched Refractive-index PIV Measurement

    T. Kubo, H. Yanai, S. Ebara, H. Hashizume

    Proceedings of The 11th Asian Symposium on Visualization ASV11-po-30 2011/05

  37. w PRESSURE MEASUREMENT TEST OF SINGLE ELBOW SIMULATING Na COOLED FAST REACTOR COLD-LEG PIPING Peer-reviewed

    Shinji Ebara, Yuta Aoya, Tsukasa Sato, Hidetoshi Hashizume, Kazuhisa Yuki, Kosuke Aizawa, Hidemasa Yamano

    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 4 PTS A AND B 705-+ 2011

    DOI: 10.1115/ICONE18-29719  

  38. Numerical simulation of turbulent flow in microscopic pore scale of pebble bed by large-eddy simulation Peer-reviewed

    S. Ebara, T. Yokomine, A. Shimizu, H. Hashizume

    FUSION ENGINEERING AND DESIGN 85 (7-9) 1638-1641 2010/12

    DOI: 10.1016/j.fusengdes.2010.04.065  

    ISSN: 0920-3796

  39. Pressure Fluctuation Characteristics of Complex Turbulent Flow in a Single Elbow With Small Curvature Radius for a Sodium-Cooled Fast Reactor Peer-reviewed

    Shinji Ebara, Yuta Aoya, Tsukasa Sato, Hidetoshi Hashizume, Yuki Kazuhisa, Kosuke Aizawa, Hidemasa Yamano

    JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME 132 (11) 111102 2010/11

    DOI: 10.1115/1.4002813  

    ISSN: 0098-2202

  40. PIV measurement for dual elbow flow using 1/7-scale model of cold-leg piping in a sodium-cooled fast reactor

    S. Ebara, T. Sato, H. Hashizume, K. Aizawa, H. Yamano

    Proceedings of the 7th International Conference on Flow Dynamics 108-109 2010/11

  41. Analysis of generating mechanism of liquid droplet jet stream at the orifice downstream area Peer-reviewed

    M. Umehara, S. Ebara, H. Hashizume

    Proceedings of The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety N8P0305 2010/10

  42. Investigation of influence of inlet flow conditions on flow structure in a dual elbow Peer-reviewed

    H. Yanai, S. Ebara, H. Hashizume

    Proceedings of The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety N8P0303 2010/10

  43. Understanding Key Parameters in Flow Accelerated Corrosion for Advanced Wall Thinning Prediction Peer-reviewed

    Hiroshi Abe, Shinji Ebara, Nobuyuki Fujisawa, Hidetoshi Hashizume, Kiwamu Sue, Yutaka Watanabe, Takayuki Yamagata

    Proceedings of International Symposium on the Ageing Management and Maintenance of Nuclear Power Plants (ISaG2010) 38-46 2010/05

  44. TURBULENT HEAT TRANSFER IN A TUBE WITH TWISTED TAPE UNDER A MAGNETIC FIELD Peer-reviewed

    T. Yokomine, S. Ebara, S. Satake, T. Kunugi

    FUSION SCIENCE AND TECHNOLOGY 56 (2) 1033-1037 2009/08

    ISSN: 1536-1055

  45. NUMERICAL ANALYSIS FOR THERMAL AND MECHANICAL PROPERTIES OF PEBBLE BED Peer-reviewed

    Shinji Ebara, Yasutaka Harai, Takehiko Yokomine, Akihiko Shimizu

    FUSION SCIENCE AND TECHNOLOGY 56 (1) 148-152 2009/07

    DOI: 10.13182/FST09-A8892  

    ISSN: 1536-1055

  46. THERMO-HYDRAULIC DESIGN OF HIGH FLUX TEST MODULE FOR IFMIF-EVEDA IN JAPAN Peer-reviewed

    T. Yokomine, S. Ebara, A. Shimizu

    FUSION SCIENCE AND TECHNOLOGY 56 (1) 267-272 2009/07

    ISSN: 1536-1055

  47. Numerical Simulation of Turbulent Flow in Porous Media by Large-eddy Simulation

    Ebara Shinji, Yokomine Takehiko, Shimizu Akihiko

    Proceedings of National Heat Transfer Symposium 2009 265-265 2009

    Publisher: The Heat Transfer Society of Japan

    DOI: 10.11368/nhts.2009.0.265.0  

  48. Turbulent heat transfer in a tube with twisted tape under a magnetic field

    T. Yokomine, S. Ebara, S. Satake, T. Kunugi

    Fusion Science and Technology 56 (2) 1033-1037 2009

    Publisher: American Nuclear Society

    DOI: 10.13182/FST09-A9047  

    ISSN: 1536-1055

  49. Ultra Fast Heat Transport Analysis by Modified Molecular Dynamics Applying Non-Fourier Law to Electron Heat Conduction Peer-reviewed

    YUICHIRO YAMASHITA, TAKEHIKO YOKOMINE, SHINJI EBARA, AKIHIKO SHIMIZU

    International Journal of Transport Phenomena 10 83-91 2008/08

  50. Large-eddy simulation of MHD turbulent heat transfer over a three-dimensional backward-facing step

    Takami Satoshi, Ebara Shinji, Yokomine Takehiko, Shimizu Akihiko

    Proceedings of National Heat Transfer Symposium 2008 298-298 2008

    Publisher: The Heat Transfer Society of Japan

    DOI: 10.11368/nhts.2008.0.298.0  

  51. Numerical study of heat transfer characteristics in a tube with regularly spaced twisted tape Peer-reviewed

    Hiroyuki Nakaharai, Satoshi Takami, Takehiko Yokomine, Shinji Ebara, Akihiko Shimizu

    FUSION SCIENCE AND TECHNOLOGY 52 (4) 855-859 2007/11

    DOI: 10.13182/FST07-A1599  

    ISSN: 1536-1055

  52. Numerical simulation of turbulent flow and heat transfer in a cooling channel of ifmif high flux test module Peer-reviewed

    Shinji Ebara, Hiroyuki Nakaharai, Takehiko Yokomine, Akihiko Shimizu

    FUSION SCIENCE AND TECHNOLOGY 52 (4) 786-790 2007/11

    DOI: 10.13182/FST07-A1586  

    ISSN: 1536-1055

    eISSN: 1943-7641

  53. Large-eddy simulation of turbulent flow and heat transfer in a mildly expanded channel of IFMIF high flux test module Peer-reviewed

    Shinji Ebara, Takehiko Yokomine, Akihiko Shimizu

    FUSION ENGINEERING AND DESIGN 82 (15-24) 2504-2509 2007/10

    DOI: 10.1016/j.fusengdes.2007.05.032  

    ISSN: 0920-3796

  54. TEMPERATURE NOISE OF ALUMINUM THIN FILM IRRADIATED WITH ULTRA SHORT PULSE LASER

    Yuichiro YAMASHITA, Takehiko YOKOMINE, Shinji EBARA, Akihiko SHIMIZU

    Proceedings of the Asian Thermophysical Properties Conference Paper No.-17 2007/08

  55. Numerical examination of temperature control in helium-cooled high flux test module of IFMIF Peer-reviewed

    Shinji Ebara, Takehiko Yokomine, Akihiko Shimizu

    FUSION ENGINEERING AND DESIGN 82 (1) 61-72 2007/01

    DOI: 10.1016/j.fusengdes.2006.07.092  

    ISSN: 0920-3796

  56. Development of a porous-type manifold for IFMIF high flux test module Peer-reviewed

    Yasutaka Harai, Takayuki Shimizu, Hiroshi Irisa, Shinji Ebara, Takehiko Yokomine, Akihiko Shimizu

    Fusion Science and Technology 52 (3) 549-553 2007

    Publisher: American Nuclear Society

    DOI: 10.13182/FST07-A1546  

    ISSN: 1536-1055

  57. Laser parameter dependence properties of heat transport mechanism in thin metal film Peer-reviewed

    Yuichiro YAMASHITA, Takehiko YOKOMINE, Shinji EBARA, Akihiko SHIMIZU

    Engineering Sciences Reports, Kyushu University 28 (3) 343-348 2006/12

    Publisher:

    DOI: 10.15017/14565  

    ISSN: 1346-7883

  58. Structural analysis with thermal effects for vessels of the gas-cooled high-flux test module of IFMIF Peer-reviewed

    Shinji Ebara, Takehiko Yokomine, Akihiko Shimizu

    FUSION SCIENCE AND TECHNOLOGY 50 (4) 538-545 2006/11

    DOI: 10.13182/FST06-A1277  

    ISSN: 1536-1055

    eISSN: 1943-7641

  59. Measurement of Acoustic Radiation Force Acting on a Small Particle in Progressive Waves in Water

    Shinji EBARA, Takashi ASANO, Takehiko YOKOMINE, Akihiko SHIMIZU

    IEICE Technical Report US2006 (67) 19-22 2006/10

    Publisher: The Institute of Electronics, Information and Communication Engineers

    ISSN: 0913-5685

    More details Close

    Measurements are made for acoustic radiation force acting on small particles in a progressive wave with a frequency of 1.95 MHz which is not plane. The radiation forces measured are quite larger than those estimated by theories assuming plane progressive waves. The magnitude of the radiation force obtained in the experiment is not proportional to the acoustic intensity. This result is also different from the theories. Since an acoustic streaming is not observed, it is considered that the difference in sound beam pattern of the progressive waves causes the difference of the acoustic radiation force between experiment and theories.

  60. DEVELOPMENT OF AN ADVANCED COOLING DEVICE USING POROUS MEDIA WITH ACTIVE BOILING FLOW COUNTER TO HIGH HEAT FLUX Peer-reviewed

    S Toda, K Yuki, S Ebara, Y Kunikata, J Abei, H Hashizume

    International Heat Transfer Conferences IHTC13 boi-58 2006/08

  61. Model for Heat Transfer in Packed Bed under Local Thermal Non-equilibrium Conditions Peer-reviewed

    Yuichiro TANAKA, Takehiko YOKOMINE, Shinji EBARA, Akihiko SHIMIZU

    Engineering Sciences Reports, Kyushu University 28 (1) 17-22 2006/06

    Publisher:

    DOI: 10.15017/14556  

    ISSN: 1346-7883

  62. Large Eddy Simulation of heat transfer characteristics in a tube with regularly spaced twisted tape Peer-reviewed

    Hiroyuki NAKAHARAI, Takehiko YOKOMINE, Shinji EBARA, Akihiko SHIMIZU

    Engineering Sciences Reports, Kyushu University 28 (1) 23-29 2006/06

    Publisher:

    DOI: 10.15017/14557  

    ISSN: 1346-7883

  63. Heat transport analysis of femtosecond laser ablation with full Lagrangian modified molecular dynamics Peer-reviewed

    Y. Yamashita, T. Yokomine, S. Ebara, A. Shimizu

    INTERNATIONAL JOURNAL OF THERMOPHYSICS 27 (2) 627-646 2006/03

    DOI: 10.1007/s10765-006-0050-5  

    ISSN: 0195-928X

  64. Heat transport analysis for femtosecond laser ablation with molecular dynamics-two temperature model method Peer-reviewed

    Y Yamashita, T Yokomine, S Ebara, A Shimizu

    FUSION ENGINEERING AND DESIGN 81 (8-14) 1695-1700 2006/02

    DOI: 10.1016/j.fusengdes.2005.09.011  

    ISSN: 0920-3796

  65. Dust mobilization by high-speed vapor flow under LOVA Peer-reviewed

    K Matsuki, S Suzuki, S Ebara, T Yokomine, A Shimizu

    FUSION ENGINEERING AND DESIGN 81 (8-14) 1347-1351 2006/02

    DOI: 10.1016/j.fusengdes.2005.09.058  

    ISSN: 0920-3796

  66. Feasibly study on cast-like IFMIF high flux test module Peer-reviewed

    S Ebara, S Nagata, H Irisa, T Yokomine, A Shimizu

    FUSION ENGINEERING AND DESIGN 81 (8-14) 887-891 2006/02

    DOI: 10.1016/j.fusengdes.2005.08.039  

    ISSN: 0920-3796

  67. Structural analysis for the gas-cooled high flux test module of IFMIF Peer-reviewed

    S Ebara, T Yokomine, A Shimizu

    FUSION ENGINEERING AND DESIGN 75-79 853-857 2005/11

    DOI: 10.1016/j.fusengdes.2005.06.133  

    ISSN: 0920-3796

    eISSN: 1873-7196

  68. Numerical study on behavior of hydrogen ice pellet in drift tube Peer-reviewed

    T Yokomine, Y Yonemoto, S Ebara, A Shimizu

    FUSION SCIENCE AND TECHNOLOGY 47 (3) 779-783 2005/04

    ISSN: 1536-1055

  69. Ice formation and pressurization under low pressure in cryostat Peer-reviewed

    Y Yamashita, T Yokomine, S Ebara, A Shimizu

    FUSION SCIENCE AND TECHNOLOGY 46 (4) 541-547 2004/12

    ISSN: 1536-1055

  70. Obserbation of Ash Deposition on Heat Transfer Surface under Large Temperature Gradient Peer-reviewed

    Imansyah Ibnu Hakim, Naoto WATANABE, Takehiko YOKOMINE, Shinji EBARA, Akihiko SHIMIZU

    Engineering Sciences Reports, Kyushu University 25 (4) 395-399 2004/03

    Publisher: Kyushu University

    DOI: 10.15017/16712  

    ISSN: 1346-7883

  71. Unsteady three-dimensional simulation of interactions between flow and two particles Peer-reviewed

    T Tsuji, R Narutomi, T Yokomine, S Ebara, A Shimizu

    INTERNATIONAL JOURNAL OF MULTIPHASE FLOW 29 (9) 1431-1450 2003/09

    DOI: 10.1016/S0301-9322(03)00137-X  

    ISSN: 0301-9322

  72. Experimental investigation on dust behavior in fusion reactor at LOVA Peer-reviewed

    H Nakaharai, T Chuman, T Yokomine, S Ebara, A Shimizu

    FUSION SCIENCE AND TECHNOLOGY 44 (2) 364-368 2003/09

    ISSN: 1536-1055

  73. 10.NUMERICAL INVETIGATION OF MULTIPLE GAS-PARTICLE IMPINGING JETS HEAT TRANSFER USING FRACTAL MODEL Peer-reviewed

    Takehiko YOKOMINE, Kazuto HIGA, Shinji EBARA, Akihiko SHIMIZU

    The 6th ASME-JSME Thermal Engineering Joint Conference TED-AJ03-259 2003/05

  74. Entrainment behavior of activated dusts in the fusion reactor under LOVA Peer-reviewed

    H Nakaharai, T Chuman, S Ebara, T Yokomine, A Shimizu, T Korenaga

    FUSION ENGINEERING AND DESIGN 63-64 313-318 2002/12

    DOI: 10.1016/S0920-3796(02)00260-0  

    ISSN: 0920-3796

  75. Feasibly study of gas-cooled test cell for material testing in IFMIF Peer-reviewed

    Y Yonemoto, E Maki, S Ebara, Y Yokomine, A Shimizu, T Korenaga

    FUSION ENGINEERING AND DESIGN 63-64 443-447 2002/12

    DOI: 10.1016/S0920-3796(02)00197-7  

    ISSN: 0920-3796

  76. Heat transfer with phase change in porous media exposed to high heat load Peer-reviewed

    S Ebara, S Toda, H Hashizume, A Shimizu, T Yokomine

    CHT'01: ADVANCES IN COMPUTATIONAL HEAT TRANSFER II, VOLS 1 AND 2, PROCEEDINGS 2 985-992 2001

  77. APPLICATION OF POROUS MEDIA TO HIGH HEAT FLUX REMOVAL OF PLASMA FACING COMPONETNS OF FUSION REACTOR Peer-reviewed

    S. Ebara, S. Toda, H. Hashizume

    Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety 151-157 2000/10

  78. Application of porous matrix to high heat load removal system Peer-reviewed

    S Ebara, S Toda, H Hashizume

    HEAT AND MASS TRANSFER 36 (4) 273-276 2000/07

    DOI: 10.1007/s002310000088  

    ISSN: 0947-7411

  79. Application of porous matrix to high heat load removal system Peer-reviewed

    S. Ebara, S. Toda, H. Hashizume

    Heat and Mass Transfer/Waerme- und Stoffuebertragung 36 (4) 273-276 2000

    Publisher: Springer-Verlag GmbH & Company KG

    DOI: 10.1007/s002310000088  

    ISSN: 0947-7411

  80. Fundamental study on high heat flux removal system using evaporated fluid in metal porous media Peer-reviewed

    S Toda, S Ebara, H Hashizume

    HEAT TRANSFER 1998, VOL 4 4 503-508 1998

  81. ONCEPT OF HIGH HEAT REMOVAL DEVICE USING EVAPORATION IN POROUS MEDIA Peer-reviewed

    S. Toda, S. Ebara, H. Hashizume

    Proceedings of 2nd Japanese-German Symposium on Multi-Phase Flow 133-144 1997/09

  82. Gas Entrainment Induced by Vortex behind an Obstacle Peer-reviewed

    T. KUMAZAWA, S. EBARA, H. HASHIZUME, S. TODA

    Proceedings of 8th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 3 1742-1746 1997/09

Show all ︎Show first 5

Misc. 27

  1. B125 A Detailed PIV Measurement of Flow Field in Flow Channel with Finger Stacked Structure

    YASUNAGA Shohei, EBARA Shinji, HASHIZUME Hidetoshi

    National Symposium on Power and Energy Systems 2015 (20) 47-48 2015/06/07

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    This study investigates the flow field in a flow channel with finger-stacked structure (FSS), which was proposed as a heat transfer promoter for Flibe blanket, by means of PIV measurement matching refractive indices of the channel material and working fluid. The experimental results revealed that turbulence energy was generated in the large velocity shear regions formed behind the fingers, and transported downstream. Then, when the gap between the fingers and channel wall was adjusted to 1 mm, the stagnant region behind the fingers that appeared in the case of 0 mm gap disappeared. In addition, turbulence energy was newly generated from the tips of the fingers. From these results, high heat transfer promotion is expected in the whole heating surface area of the flow channel with FSS setting small gap.

  2. F134 Fundamental Study for Application of Swirling Flow generated downstream of a Multi-elbow Layout to Divertor Cooling

    KODATE Shouichi, HATTORI Munehito, EBARA Shinji, HASHIZUME Hidetoshi

    National Symposium on Power and Energy Systems 2015 (20) 171-172 2015/06/07

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    In this study, heat transfer performance downstream of three-dimensionally-connected multi elbows, where a strong swirling flow appear due to the elbow layout, was experimentally studied and compared to that of a swirl tube supposed to be used in the ITER divertor. Dual and triple elbow layouts were tested, and local and averaged Nusselt numbers in the circumferential direction were evaluated from the experiment. The averaged Nusselt numbers of the triple elbow layout were slightly larger than those of the dual one. Although a comparably weak swirling flow was generated in the experiment, the heat transfer rate becomes 0.8 times as large as that of the swirl tube under the condition of single phase flow.

  3. 大型高温超伝導マグネットの開発の現状と展望‐高温超伝導導体の分割製作と接合技術による大型マグネットの開発

    橋爪秀利, 伊藤悟, 江原真司, 遊佐訓孝, 柳長門, 寺崎義朗, 田村仁, 相良明男

    プラズマ・核融合学会誌 91 (2) 87-96 2015/04

  4. B123 Study on the influence of piping layout upon flow separation characteristic in the downstream of a elbow in the primary cold-leg of sodium cooled fast reactor

    MIZUTANI Jun, EBARA Shinji, HASHIZUME Hidetoshi, YAMANO Hidemasa

    National Symposium on Power and Energy Systems 2014 (19) 51-54 2014/06/25

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    It is quite likely that a complex turbulent flow field and large pressure fluctuation induced by separation vortex shed from the intrados of the elbows are seemed to appear in the cold leg piping of the primary cooling system of Japan Sodium-cooled Fast Reactor. This study researched the influence of the inflow condition upon the flow separation especially in the 3rd elbow. In this study, the inflow condition to the 3rd elbow was imposed by changing the distance between the 2nd and 3rd elbows from 6.4D (original design) to 9.4D. The visualization experiment showed that the flow separation appeared in the intrados of the 3rd elbow as was the case with the original design and the separated regions became larger than that in the original one. This is because a swirling flow observed at the inlet of the 3rd elbow became weaker than that in the original case.

  5. A214 Study on Reduction of Pipe Wall Thinning in the Downstream of an Orifice

    KATO Masako, EBARA Shinji, HASHIZUME Hidetoshi

    National Symposium on Power and Energy Systems 2014 (19) 195-196 2014/06/25

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    In this study, two issues related to liquid droplet impingement (LDI) erosion were tackled. As for the LDI erosion just behind an orifice, numerical simulation of single-phase gas flow was conducted and then traces of liquid droplets were simulated on the assumption of point mass approximation with drag force from the flow field for the liquid droplets. The numerical parameters were the size of the liquid droplets and their initial conditions such as position and velocity. As a result, it was found that liquid droplets appearing in the vicinity of the aperture of the orifice did not impinge on the pipe wall just behind the orifice. As for the suppression of the formation of liquid film just behind an orifice, a few orifice with multi-apertures were fabricated and tested experimentally, and the flow fields and behavior of liquid film formed downstream of the orifices were observed. The experiment showed that the apertures in the circumferential direction near the pipe wall were effective to suppress the formation of liquid film.

  6. Basic Study on Flow Separation Phenomenon in Cooling System Piping in Fast Reactors : Clarification of Complex Flow Structure in a Multi-Elbow in a High Reynolds Number Regime : Joint Research Report in JFY2008 and JFY2009

    JAEA-research 2013 (11) 巻頭1-2,1-72 2013/10

    Publisher: 日本原子力研究開発機構

  7. D112 Influence of an Asymmetry Swirling Flow Generated downstream of a Three-dimensionally Connected Dual Elbow upon Pipe Wall Thinning Caused downstream of an Orifice

    KUBO Tatsuya, EBARA Shinji, HASHIZUME Hidetoshi

    National Symposium on Power and Energy Systems 2013 (18) 105-108 2013/06/19

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    Flow visualization experiment and accelerated pipe wall thinning experiment were conducted by applying a swirling flow generated by a piping configuration, three-dimensionally connected dual elbow, to the inlet flow condition of a pipe orifice to investigate pipe wall thinning downstream of an orifice appearing due to the combination of swirling flow and orifice The flow downstream of the orifice was curved by the action of the swirling flow, and the channel wall where the flow turned off toward underwent a large amount of wall thinning Profiles of turbulent quantities, such as turbulent kinetic energy and Reynolds shear stress, were compared to those of amount of pipe wall thinning It was found that the profiles of Reynolds shear stress showed good agreement with those of pipe wall thinning in the case for a large amount of that However, relatively small amount of pipe wall thinning, any profile related to fluid motion could not explain the profiles of pipe wall thinning

  8. 日米科学技術協力事業TITANプロジェクト 3.第一壁・ブランケットの物質熱輸送に関する研究 3.3 熱流動制御とモデリング

    功刀資彰, 横峯健彦, 植木祥高, 結城和久, 佐竹信一, 江原真司, 橋爪秀利

    プラズマ・核融合学会誌 89 (11) 2013

    ISSN: 0918-7928

  9. I142 A Detailed PIV Measurement of Complex Flow Field in Sphere-packed Pipe

    Ebara Shinji, Nematollahi Mohammad Reza, Hashizume Hidetoshi

    Procee[d]ings of Thermal Engineering Conference 2012 287-288 2012/11/16

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    A sphere-packed pipe (SPP) was scrutinized to clarify the complicated turbulent flow field by means of PIV measurement. The geometrically complicated system was visualized by matching refractive index of acrylic resin as the channel material and Sodium Iodide solution as the working fluid. The visualization experiment was conducted with Reynolds number based on the sphere diameter and Darcy velocity of 5,000. As a result, it was found that high velocity regions appeared in the vicinity of packed sphere near penetrating paths formed in the SPP. In addition, it was clarified that turbulence energy was mainly generated in the large velocity shear regions formed near the pipe wall behind the packed spheres.

  10. S083021 U-RANS Simulation of Elbow Flow with a 1/7 Scale Experimental Loop Simulating JSFR Cold-Leg Piping

    KANEKO Tetsuya, YAMANO Hidemasa, TANAKA Masaaki, EBARA Shinji, HASHIZUME Hidetoshi

    Mechanical Engineering Congress, Japan 2012 "S083021-1"-"S083021-5" 2012/09/09

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    A study on flow-induced vibration in the primary cooling system of Japan Sodium cooled Fast Reactor (JSFR) has been conducted 111 Japan Atomic Energy Agency (JAEA). The flow-induced vibration in the elbow is an important issue in design study of JSFR consisting of large diameter pipe and elbow with short curvature radius, because it may affect to structural integrity of the pipe. In this study, Unsteady Reynolds Averaged Navier-Stokes equations (U-RANS) approach with the Reynolds Stress Model (RSM) using a commercial CFD code has been applied to the flow through single and double short-elbows under a high Reynolds number condition. This numerical simulation has utilized a 1/7 scaled water experiment of the JSFR cold-leg piping in order to investigate the flow structure in a three-dimensionally connected double elbow. As a result, applicability of the numerical simulation method was confirmed by comparison between the numerical and experimental results. The simulation has also shown that flow fields m the 1st elbow was different from that in the 2nd elbow and pressure fluctuation in the 2nd elbow was larger than that in the 1st elbow because their larger vortex flow structure.

  11. D222 Influence of Frequency Characteristics of Turbulence Velocity Fluctuations upon Pipe Wall Thinning downstream of an Orifice

    EBARA Shinji, YANAI Hiroki, HASHIZUME Hidetoshi

    National Symposium on Power and Energy Systems 2012 (17) 371-374 2012/06/20

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    It is very important to clarify the mechanism of Flow-accelerated Corrosion (FAC) from the viewpoint of plant maintenance because of the large potential influence of FAC. From the evidence that the scale of scalloped pattern appearing in the region where FAC occurs is different according to the extent of pipe wall thinning, it can be considered that a scale in the flow, e.g., frequency in the turbulent motion, affetcs the FAC. Experimental data is analyzed in terms of frequency characteristics by using a circular pipe with an orifice. It is shown that Reynolds stress has a lot to do with pipe wall thinning by FAC.

  12. D212 Experimental Flow Visualization of a Gas-liquid Two-phase Flow immediately downstream of an Orifice

    KATO Masako, EBARA Shinji, HASHIZUME Hidetoshi

    National Symposium on Power and Energy Systems 2012 (17) 355-356 2012/06/20

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    Pipe wall thinning caused by erosion and corrosion is one of important problems in thermal and nuclear power plants. In this study, LDI erosion, which is one of the causes of pipe wall thinning especially in steam piping, is focused on. Since LDI erosion which appears downstream of an orifice is considered to depend on the shape of the orifice's aperture, two types of orifice with and without taper are scrutinized by visualization experiments of air-water two-phase flow and only air flow. Some differences are observed in the reattachment point downstream of the orifice, entrainment behavior of liquid phase behind the orifice and shocks formed immediately behind the orifice aperture.

  13. S054096 Evaluation for Flow-Induced Vibration of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor (6) : Prediction of Unsteady Flow Field in JSFR Hot-Leg Piping

    TANAKA Masaaki, SAGO Hiromi, IWAMOTO Yukiharu, EHARA Shinji, ONO Ayako, MURAKAMI Takahiro, HAYAKAWA Satoshi

    Mechanical Engineering Congress, Japan 2011 "S054096-1"-"S054096-5" 2011/09/11

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    In Japan Atomic Energy Agency (JAEA), a study on flow induced vibration in the primary cooling system of Japan Sodium cooled Fast Reactor (JSFR) consisting of large diameter pipe and pipe elbow with short curvature radius ("short-elbow") has been conducted. Flow-induced vibration in the short-elbow is an important issue in design study of JSFR, because it may affect to structural integrity of the pipe. In this paper, unsteady flow characteristics in the JSFR short-elbow pipe related to the large-scale eddy motion were estimated based on knowledge from existing studies for curved pipes and scaled water experiments and numerical simulations for the JSFR hot-leg piping.

  14. A213 Experimental study for heat transfer enhancement of high Pr number fluids in sphere-packed annular channel

    Shimizu Katsuya, Ebara Shinji, Hashizume Hidetoshi

    Procee[d]ings of Thermal Engineering Conference 2010 237-238 2010/10/29

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    High Prandtl number (Pr) fluid Flibe, whose Pr varies from 25 to 150 depending on its composition, has been proposed to be used as the cooling and breeding liquid in blanket of fusion reactor. In this study, heat transfer experiments with sphere-packed circular pipes (SPP) and annular channels, which are heat transfer promoter for Flibe, are conducted using silicone oils as working fluids whose Pr are almost 25, 100 and 150. The results show that SPP has a little fin effect and sphere packed annular channels can obtain slightly higher heat transfer performance than circular pipe when comparing in the same pumping power.

  15. Temperature Control of IFMIF High Flux Test Module

    EBARA Shinji

    Journal of plasma and fusion research 85 (8) 564-566 2009/08/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  16. Heat Removal Technologies in Fusion Reactor -from Actual Uses to Advanced Technologies-

    戸田三朗, 江原真司, 江里幸一郎, 関洋治, 榎枝幹夫, SMOLENTSEV Srgey, 結城和久, 相良明男, 橋爪秀利

    Journal of Plasma and Fusion Research 85 (8) 539-569 2009/08

    Publisher: The Japan Society of Plasma Science and Nuclear Fusion Research

  17. Entrainment behavior of activated dusts in vapor air

    Suzuki Shinya, Matsuki Kazuhiro, Takehiko Yokomine, Ebara Shinji, Shimizu Akihiko

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2005s 663-663 2005

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2005s.0.663.0  

  18. Temperature control for high flux test module of IFMIF with non-uniform nuclear heating

    Irisa Hiroshi, Nagata Satoshi, Ebara Shinji, Yokomine Takehiko, Shimizu Akihiko

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2005s 649-649 2005

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2005s.0.649.0  

  19. Prospect towards inevitably closed gas turbine : Thermal efficiency of multistage compression/expansion Erichson-cycle

    SHIMIZU Akihiko, EBARA Shinji

    Procee[d]ings of Thermal Engineering Conference 2004 77-78 2004/11/10

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    Every existing gas turbine is of open-cycle in which exhaust gas is discharged into atmosphere. Several exceptions, namely those of open-cycle, all disappeared so far, because there has been no demand for that. Therefore, the effort of gas-turbine development has been directed towards simple enhancement of the inlet gas temperature through material development and/or some exquisite blade cooling technique. In the field of nuclear energy, on the other hand, there exists a demand of closed-cycle for the next generation reactors such as high temperature gas-cooled power reactor or gas-cooled fusion reactor for which the perfect confinement of radioactivity is the crucial requisite. Moreover, in the nuclear applications, the highest temperature of the gas turbine cycle is restricted from above by other factors such as integrity of irradiated materials or possible mobility of the radioactivity. If so, the problem inevitably reduces to that of how to realize the excellent cycle performance through other thermo-mechanical considerations

  20. Thermal elastoplastic analysis for high flux gas-cooled test module of IFMIF

    Nagata Satoshi, Ebara Shinji, Yokomine Takehiko, Shimizu Akihiko

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2004f 624-624 2004

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2004f.0.624.0  

  21. TED-AJ03-259 NUMERICAL INVESTIGATION OF MULTIPLE GAS-PARTICLE IMPINGING JETS HEAT TRANSFER USING FRACTAL MODEL :

    YOKOMINE Takehiko, HIGA Kazuto, EBARA Shinji, SHIMIZU Akihiko

    Proceedings of the ... ASME/JSME Thermal Engineering Joint Conference 2003 (6) 272-272 2003

    Publisher: 日本機械学会

    More details Close

    The calculation is performed by using κ-ε turbulence model in which the particle source terms described turbulence modulation due to particles and Lagrange model for discrete particle motion with Direct Simulation Monte Carlo method and fractal model to express the particle coagulations, collisions and breakups. As the adhesion forces between the particles, viscous force and capillary force are considered. The critical Stokes numbers for coagulation and breakup and Capillary number are used as switches of working the adhesion forces. When the initial particle size distribution is uniform, flow and heat transfer characteristics of both phases are independent of coalescence. If the initial size distribution has many small particles (Dist-S), the enhancement of turbulent energy due to particles becomes dominant as the heat transfer enhancement mechanism. On the contrary, the increase of heat capacity by added particles mainly promotes the heat transfer if many large particles initially involved (Dist-L). The size distribution makes large difference of heat transfer between both nozzles. If many small particles involved, the heat transfer is promoted while enhancement of heat transfer is promoted while enhancement of heat transfer and turbulent energy is prevented by the highly concentrated belt-like region of particles of many large particles involved.[figure]

  22. 2 Structural analysis of gas-cooled test module of the IFMIF

    SHIMIZU Akihiko, YOKOMINE Takehiko

    (20) 25-25 2003

    Publisher: プラズマ・核融合学会

  23. Study of gas-cooled test cell of the IFMIF

    SHIMIZU Akihiko, YONEMOTO Yukihiro, NAGATA Satoshi

    (19) 24-24 2002

    Publisher: プラズマ・核融合学会

  24. 高熱負荷を受ける多孔質内での相変化を伴う伝熱

    第2回先進数値伝熱国際シンポジウム講演論文集 2 985-992 2001

  25. 高熱負荷除去システムへの多孔質体の応用

    第9回原子力熱・流体部門国際会議議演論文集 (CD-ROM(log24.pdf)) 1999

  26. 金属多孔質内での蒸発を利用した高熱流束除去システムに関する基礎研究

    第11回国際伝熱会議講演論文集 4 503-508 1998

  27. 障害物後流の旋回渦による気体巻き込みに関する研究

    第8回原子力熱・流体部門国際会議講演論文集 3 1742-1746 1997

Show all ︎Show first 5

Presentations 34

  1. EXPERIMENTAL INVESTIGATION OF INFLUENCE OF TURBULENT NEAR-WALL FLOW ON FLOW ACCELERATED CORROSION BEHIND AN ORIFICE International-presentation

    T. Kaneko, S. Ebara, H. Hashizume

    29th International Symposium on Transport Phenomena 2018/10/31

  2. Study for influence of frequency characteristic of turbulent velocity fluctuation upon flow-accelerated corrosion International-presentation

    Tatsuru KANEKO, Shinji EBARA, Hidetoshi HASHIZUME

    4th International Conference on Maintenance Science and Tcchnology 2018/09/23

  3. 溶融塩ブランケット第一壁冷却 Finger-stacked Structure 流路での片面加熱・乱流促進体発熱条件における伝熱性能評価

    大石真希, 江原真司, 橋爪秀利, 相良明男

    第12回核融合エネルギー連合講演会 2018/06/28

  4. 熔融塩液体ダイバータの実現可能性の検討 -乱流促進による高熱負荷除去に関する評価-

    櫻井翔太, 江原真司, 橋爪秀利

    第12回核融合エネルギー連合講演会 2018/06/28

  5. 溶融塩ブランケットにおける第一壁冷却流路 Finger-stacked Structure 流路における核発熱評価

    大澤一人, 江原真司, 橋爪秀利

    第12回核融合エネルギー連合講演会 2018/06/28

  6. 多段エルボ配管下流自己形成旋回流の強制対流沸騰伝熱特性

    川上紘史, 江原真司, 橋爪秀利, 浜地志憲

    第23回 動力・エネルギー技術シンポジウム 2018/06/14

  7. 流れ加速型腐食への乱流場速度変動周波数特性の依存性調査

    金子立, 江原真司, 橋爪秀利

    第23回 動力・エネルギー技術シンポジウム 2018/06/14

  8. Evaluation of Boiling Heat Transfer Characteristic of a Self-Formed Swirling Flow downstream of Multi-Elbow Piping under One-Sided Heating Condition International-presentation

    Hiroshi Kawakami, Munehito Hattori, Shinji Ebara, Hidetoshi Hashizume

    13th International Symposium of Fusion Nuclear Technology 2017/09/25

  9. Thermofluid Characteristics of a Flow Channel with Finger-stacked Structure for the first wall Cooling of Flibe Blanket(2) Evaluation of Pressure Drop and Heat transfer Characteristics International-presentation

    Masaki Oishi, Shohei Yasunaga, Shinji Ebara, Hidetoshi Hashizume, Akio Sagara

    13th International Symposium of Fusion Nuclear Technology 2017/09/25

  10. Thermofluid Characteristics of a Flow Channel with Finger-stacked Structure for the first wall Cooling of Flibe Blanket (1) Optimization of Channel Structure by Flow Visualization Experiment International-presentation

    Shouhei Yasunaga, Shinji Ebara, Hidetoshi Hashizume, Akio Sagara

    13th International Symposium of Fusion Nuclear Technology 2017/09/25

  11. Evaluation of influence of the inlet swirling flow on the flow field in a triple elbow system International-presentation

    Jun Mizutani, Shinji Ebara, Hidetoshi Hashizume

    17th International Conference on Emerging Nuclear Energy Sciences (ICENES 2015) 2015/10/04

  12. Characteristics of Flow Field and Pressure Fluctuation in Complex Turbulent Flow in the Third Elbow of a Triple Elbow Piping with Small Curvature Radius in Three-dimensional Layout International-presentation

    Shinji Ebara, Hiroyuki Takamura, Hidetoshi Hashizume, Hidemasa Yamano

    17th International Conference on Emerging Nuclear Energy Sciences (ICENES 2015) 2015/10/04

  13. Finger-Stacked Structure流路における内部流動のPIV詳細計測

    安永昌平, 江原真司, 橋爪秀利

    第20回動力・エネルギー技術シンポジウム 2015/06/18

  14. 三段エルボ配管における入口旋回流の流れ場への影響評価

    水谷淳, 江原真司, 橋爪秀利

    第20回動力・エネルギー技術シンポジウム 2015/06/18

  15. エルボ下流自己形成流動場のダイバータ冷却への応用に関する基礎研究

    古舘翔一, 服部宗仁, 江原真司, 橋爪秀利

    第20回動力・エネルギー技術シンポジウム 2015/06/18

  16. FLOW VISUALIZATION EXPERIMENT OF A SWIRLING FLOW FORMED DOWNSTREAM OF A PIPING WITH SUCCESSIVE THREE ELBOW TO BE APPLIEDTO DIVERTOR COOLING International-presentation

    Shoichi Kodate, Shinji Ebara, Hidetoshi Hashizume

    2014 22nd International Conference on Nuclear Engineering (ICONE22) 2014/07/07

  17. オリフィス下流部に生じる配管減肉の低減に関する研究

    加藤雅子, 江原真司, 橋爪秀利

    第19回動力・エネルギー技術シンポジウム 2014/06/26

  18. Na冷却高速炉1次系コールドレグにおける配管レイアウトのエルボ下流への影響評価

    水谷淳, 江原真司, 橋爪秀利, 山野秀将

    第19回動力・エネルギー技術シンポジウム 2014/06/26

  19. 連続立体エルボ配管下流で生じる旋回流の可視化計測とダイバータ冷却への適用可能性の検討

    古舘翔一, 江原真司, 橋爪秀利

    第10回核融合エネルギー講演会 2014/06/19

  20. Na冷却高速炉における大口径配管の流力振動評価に関する研究;(40)コールドレグ1/7 縮尺流動試験装置を用いた3段エルボ管内複雑乱流流れのPIV計測

    高村宏行, 江原真司, 橋爪秀利, 山野秀将

    日本原子力学会2013年秋の大会 2013/09/03

  21. 3次元接続二段エルボ下流に生成する非対称旋回流のオリフィス下流配管減肉への影響

    久保達也, 江原真司, 橋爪秀利

    第18回動力・エネルギー技術シンポジウム 2013/06/20

  22. ぺブル充填矩形流路を用いた高プラントル数流体の伝熱流動実験

    渡邉篤史, 江原真司, 橋爪秀利, 相良明男

    第50回 日本伝熱シンポジウム 2013/05/29

  23. INFLUENCE OF FREQUENCY CHARACTERISTICS OF VELOCITY FLUCTUATIONS IN COMPLEX TURBULENT FLOW DOWNSTREAM OF AN ORIFECE UPON PIPE WALL THINNING International-presentation

    S. Ebara, H. Yanai, H. Hashizume

    The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulicsics and Safety 2013/05/12

  24. EXPERIMENTAL STUDY ABOUT THE INFLUENCE OF LIQUID FILM FORMED JUST DOWNSTREAM OF AN ORIFICE UPON PIPE WALL THINNING International-presentation

    M. Umehara, S. Ebara, H. Hashizume

    The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulicsics and Safety 2013/05/12

  25. EFFECTS OF SEPARATION VORTICES ON PRESSURE FLUCTUATION OF COMPLEX TURBULENT FLOW IN A DUAL ELBOW WITH SMALL CURVATURE RADIUS IN A THREE-DIMENSIONAL LAYOUT International-presentation

    Shinji Ebara, Hiroaki Konno, Hidetoshi Hashizume, Tetsuya Kaneko, Hidemasa Yamano

    The Eighth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety 2012/12/02

  26. ペブル充填管内複雑流動場のPIV詳細計測

    江原真司, Mohammad Reza Nematollahi, 橋爪秀利

    日本機械学会熱工学コンファレンス2012 2012/11/17

  27. Experimental Study for Heat Transfer Enhancement of High Prandtl Number Fluids in Sphere-packed Annular Channel for Flibe Blanket International-presentation

    Shinji Ebara, Katsuya Shimizu, Akio Sagara, Hidetoshi Hashizume

    27th Symposium on Fusion Technology 2012/09/24

  28. Numerical Evaluation of Thermo-fluid and Structural Characteristics of IFMIF High Flux Test Module International-presentation

    Shinji Ebara, Takahide Yoshida, Takehiko Yokomine, Eiichi Wakai

    27th Symposium on Fusion Technology 2012/09/24

  29. 蒸気系配管のオリフィス下流再循環領域での減肉に関する実験的研究

    江原 真司, 梅原 真弘, 橋爪 秀利

    日本保全学会 第9回学術講演会 2012/07/25

  30. オリフィス下流高速気液二相流および液膜からの液滴発生の可視化計測

    江原 真司, 梅原 真弘, 橋爪 秀利

    日本保全学会 第9回学術講演会 2012/07/25

  31. オリフィス下流における配管減肉への乱流速度変動周波数の影響

    江原真司, 矢内宏樹, 橋爪秀利

    第17回動力・エネルギー技術シンポジウム 2012/06/21

  32. PIV measurement for dual elbow flow using 1/7-scale model of cold-leg piping in a sodium-cooled fast reactor International-presentation

    7th International Conference on Flow Dynamics (ICFD2010) 2010/11/01

  33. Pressure measurement test of single elbow simulating Na-cooled fast reactor cold-leg piping International-presentation

    18th International Conference on Nuclear Engineering (ICONE-18) 2010/05/17

  34. Evaluation of Heat Transfer Characteristics of Multi-Elbow Cooling System under One-sided Heating for Fusion Divertor

    Shinji Ebara, Kenya Mitobe, Yukinori Hamaji, Hidetoshi Hashizume

    The 31st International Toki Conference on Plasma and Fusion Research (ITC31) 2022/11/08

Show all Show first 5

Research Projects 26

  1. Application of swirling flow generated downstream of multi-elbow piping to fusion divertor cooling Competitive

    System: Nuclear and Atomic Science Research

    2012/04 - Present

  2. Study for pipe wall thinning in nuclear power plants by flow accelerated corrosion (FAC) -Effect of local flow field on FAC Competitive

    System: Nuclear and Atomic Science Research

    2009/04 - Present

  3. Study for pipe wall thinning in nuclear power plants by liquid droplet impingement erosion (LDI) -Entrainment of liquid droplet from liquid film on pipe wall near an oriffice Competitive

    System: Nuclear and Atomic Science Research

    2009/04 - Present

  4. Experimental study for flow induced vibration in a pipe with multi-elbow in fast reactor Competitive

    System: Nuclear and Atomic Science Research

    2009/04 - Present

  5. Thermofluid experiment for design of Flibe blanket in a fusion reactor Competitive

    System: Cooperative Research

    2009/04 - Present

  6. ダイバータ冷却に向けたACT2による複数エルボ下流自己形成旋回流の沸騰伝熱特性評価実験

    Offer Organization: 核融合科学研究所

    System: 一般共同研究

    2022/04 - 2024/03

  7. Development of a novel fusion liquid divertor with very long lifetime using molten salt Flibe

    Ebara Shinji

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Tohoku University

    2019/04 - 2022/03

    More details Close

    From a flow visualization experiment utilizing PIV, turbulence promotion effect due to pebbles installed on the channel bottom was clarified. It was found from heat transport experiment in which free surface of the flow was heated by Halogen heaters that fluid mixing was enhanced by the pebbles arranged on the channel bottom and surface temperature decreased compared to that without pebble case. These results can enable us to hope slower flow velocity of Flibe and smaller amount of evaporation in the vacuum vessel in a fusion reactor, and to envisage that the feasibility of liquid divertor using Flibe is greatly improved.

  8. 液体溶融塩ブランケット第一壁開発のための高磁場下伝熱促進流路の特性評価

    Offer Organization: 核融合科学研究所

    System: LHD計画共同研究

    2018/04 - 2021/03

  9. Clarification of flow scale dependency of mass transfer in high Schmidt nunmber turbulent flow and challenge for pipe wall thinning control technique

    Shinji Ebara

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (C)

    Institution: Tohoku University

    2016/04/01 - 2019/03/31

    More details Close

    In this study, an accelerated wall thinning experiment using benzoic acid as thinning wall, flow visualization experiment by means of PIV and visualization experiment of concentration field using LIF were conducted in order to analyze mass transfer from a channel wall in a complex high Schmidt number turbulent flow downstream of an orifice. From the observation of the concentration field, it was found that frequent and intermittent ejections of high concentration fluid from a channel wall appeared in large wall thinning rate area. The ejections instantaneously reached up to several mm in height whereas the viscous sublayer thickness was assumed to be of the order of 0.1 mm and the concentration boundary layer thickness was assumed to be thinner than it in the area. This phenomena observed is considered to indicate that larger vortex structures than the viscous sublayer and concentration layer have a lot to do with the mass transport from the channel wall.

  10. Remote-filed based tomographic evaluation of two-phase flows aiming at a countermeasure against a loss of coolant accidents

    Yusa Noritaka

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Tohoku University

    2015/04/01 - 2019/03/31

    More details Close

    This study attempted the application of remote field eddy current technique to the evaluation of two-phase flows from outside the pipe, especially for the purpose of confirming presence of coolants in the case of a loss of coolant accident. Detailed three-dimensional finite element simulations and experiments revealed, however, high frequency excitation necessary to distinguish water and air makes it difficult to realize remote field phenomena in case of pipes carrying the fluids are made from metals. Furthermore, even the pipes are made from composite materials whose electrical conductivity is much smaller than that of the metals, it was difficult to obtain tomographic images of the two-phase flows with a high spatial and time resolutions as originally expected.

  11. Demonstration of a remountable high-temperature superconducting magnet and construction of universal joints toward the realization of an innovative fusion reactor

    Hashizume Hidetoshi

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (S)

    Institution: Tohoku University

    2014/05/30 - 2019/03/31

    More details Close

    We established a method to predict the jointing resistance of the REBCO tapes under cryogenic temperature, strong magnetic field environment and improved heat transfer correlation for pool boiling in the metal porous media indispensable for the cooling performance prediction. In addition, we introduced joint piece and low temperature heat-treatment into the bridge-type mechanical lap joint of the 10kA conductor to succeed realizing 1/3 jointing resistance with 1/6 fabrication time. Furthermore, we performed a pinning center introduction based on a critical state model and a self-magnetic field evaluation by using proton beam irradiation to show controllability of a critical current density, which indicates the possibility of the function-divided conductor based on the superconductivity physics. According to the above results, the demountable high Tc superconducting magnet for an innovative nuclear fusion reactor is demonstrated together with the general jointing method for the magnets.

  12. A Challenge to Development of Functionally-graded Long-life Divertor based on Degradation Behavior Caused by Thermal Fatigue of Tungsten

    Nogami Shuhei

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Tohoku University

    2014/04/01 - 2018/03/31

    More details Close

    The objective of this research is development of functionally-graded tungsten (W) for divertor using a void dispersion strengthened W (VDSW) and a nano structure controlled W (NSCW). Based on the fundamental mechanical properties, recrystallization behavior, fatigue properties, and resistance to the beam bombardment, development of the VDSW and NSCW was carried out and the excellent performance was shown by these materials. Development of a new testing machine for evaluating the fatigue properties was also carried out and the available data of these materials were obtained. In contrast, the evaluation of resistance to helium implantation was carried out under the only limited evaluation conditions. This is one of the issues to be improved by future works. However, the development of fabrication technology of reasonable joints using VDSW and NSCW was all but almost over. Therefore, the objective of this research is considered to be basically achieved.

  13. Study on mechanism and prediction of non-axisymmetric wall thinning in pipeline

    Fujisawa Nobuyuki, EBARA Shinji, YAMAGATA Takayuki

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Niigata University

    2012/04/01 - 2016/03/31

    More details Close

    In order to understand the mechanism of non-axisymmetric wall-thinning in a pipeline of nuclear power plant, the velocity field and mass transfer characterisatics of the pipe due to the flow accelerated corrosion and liquid droplet impingement erosion are studied experimentally and numerically. The results are summarized as follows: 1. The flow downstream of elbow-orifice pipeline shows non-axisymmetric flow behavior, which is due to the combined effect of swirl upstream and the secondary flow in the elbow and orifice. 2. Mass transfer characteristics downstream of the elbow and orifice behaves similar to the flow field. 3. Non-axisysymmetric behavior downstream of orifice can be predicted by numerical method based on the mass and momentum equations combined with the k-εmodel of turbulence. 4. The wall-thinning due to liquid droplet impingement erosion is studied experimentally and the numerical prediction method is proposed.

  14. Construction and demonstration of universal joint techniques for realization of a remountable high-temperature superconducting magnet

    HASHIZUME Hidetoshi, EBARA Shinji, YUSA Noritaka, ITO Satoshi

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (A)

    Institution: Tohoku University

    2011/04/01 - 2014/03/31

    More details Close

    We conducted this research aiming for realization of universal joint techniques to be applied to a remountable high-temperature superconducting magnet. We set three objectives in this research: 1) Establishment of universal joint techniques, 2) Optimization of cooling system using porous media and 3) Design and fabrication of a large-scale conductor and its joint. In the research of the cooling system, we confirmed that metal porous media can suppress film boiling and the fact implies that the system is suitable for the remountable magnet. In addition, we fabricated a large-scale conductor having mechanical joint section and achieved a current of 100 kA. Based on the above results, we demonstrated the concept of joint techniques and a remountable high-temperature superconducting magnet.

  15. Engineering Design of High Flux Test Module of IFMIF Competitive

    System: The Other Research Programs

    2000/04 - 2013/03

  16. Elucidation of Multiple-scale Mass Transfer Mechanism from Wall toComplex Turbulent Flow and Challenge to FAC Control Technique

    EBARA Shinji

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Young Scientists (B)

    Institution: Tohoku University

    2011 - 2012

    More details Close

    In order to clarify the relationship between flow-accelerated corrosion and scales of fluid motion, i.e., frequencies in the turbulent motion, visualization experiments for fluid flow by using PIV method were conducted and the flow fields were analyzed in detail. When the levels of power spectrum densities of fluctuating velocities obtained from the experiments were compared to the profile of pipe wall thinning obtained from an actual plant, their trend showed a fair agreement with each other. Furthremore, they showed a better agreement when a low-pass filtering operation was done for the fluctuating velocities. However, Reynolds stress profile showed a much more better agreement with the actual profile of pipe wall thinning.

  17. Measurement of Internal Configuration of Pebble Bed by UsingNonlinear Ultrasound CT and Large-Scale Numerical Simulations for its ThermofluidDynamics

    EBARA Shiji

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Young Scientists (B)

    Institution: Kyushu University

    2008 - 2009

    More details Close

    In this study, for the purpose of elucidating detailed thermofluid phenomena in pebble bed, a nonlinear ultrasound CT system, which could obtain the internal configuration of pebble bed in detail, was tried to construct and numerical simulation which would excluded possible numerical models was performed. From evaluation experiment of the nonlinear ultrasound CT, it was found that CT images were deteriorated by a difference of acoustic refraction between solid and fluid phases. In addition, several problems to resolve for the realization of the CT system were extracted. On the other hand, in the numerical simulation, large-eddy simulation was adopted as a turbulent model, a parallel numerical code was created and detailed simulation for fluid flow in the pebble bed was done.

  18. 高経年化原子炉プラントにおける流れ加速型腐食(FAC)への流動場の影響解明 Competitive

    2009 -

  19. 複雑流路における流れのPIV可視化実験 Competitive

    2009 -

  20. Internal structural diagnostics of pebble bed using nonlinear ultasonic CT Competitive

    System: Grant-in-Aid for Scientific Research

    2008/04 -

  21. Numerical simulation for thermal-hydraulic and thermo-mechanic characteristic of pebble bed Competitive

    System: Grant-in-Aid for Scientific Research

    2007/04 -

  22. 超音波を用いたマイクロ・マニピュレーションの開発 Competitive

  23. 音響場と粒子の相互作用 Competitive

  24. ガス冷却温度制御に関する研究 Competitive

  25. Heat Transfer and Fluid Flow in Porous Media with Phase Change Competitive

  26. Study on Gas Cooling Temperature Control Competitive

Show all Show first 5

Other 7

  1. Flibeブランケットにおける第一壁冷却およびトリチウム回収促進を両立する冷却流路構造の基礎研究

    More details Close

    Flibeブランケットにおける第一壁冷却流路に用いる乱流伝熱促進のための棒状構造物を、トリチウム回収にも用いることを提案し、その流路構造の最適化を流れの可視化実験および伝熱実験により行う。

  2. 高中性子束領域試験モジュールの工学設計

    More details Close

    IFMIF(国際核融合材料照射施設)における高中性子束試験モジュールの工学設計を行う。

  3. 配管群における水蒸発特性に関する研究助成

    More details Close

    原子炉タービン建屋の再水器における配管群での水蒸発特性に関する数値解析

  4. 超音波マイクロマニピュレーションのドラッグデリバリーシステムへの応用

    More details Close

    超音波によるマイクロマニピュレーションの素過程である微少物体に働く音響放射力の研究において、周囲流体の粘性が多大な影響を及ぼすと考えられるμmオーダーの微少物体に対しては未だ十分な研究はなされているとは言えず、流体の持つ粘性や物体の弾性、音場の特性が放射力にどう影響を及ぼすかはまだ不明な点が多い。ドラッグデリバリシステム(DDS)ではμmオーダーのキャリアーを用いるため、音響放射力のメカニズムを把握することが超音波DDSの実現には欠かせない。本研究では、理論では扱われていない流体の粘性や物体の弾性、音波ビームの特性が及ぼす音響放射力への影響を実験的に明らかにすることを目的とする。

  5. 粒子充填層における熱流動及び熱機械特性の大規模in-silico実験

    More details Close

    プラントの性能は、粒子充填層では充填密度などの平均量により決まるが、粒子層内の応力集中、粒子の熱クリープによる流路閉塞やヒートスポットの発生など安全性に決定的な要因となる現象は局所的な物理量に影響を受ける。従来の充填層の研究は、粒子群を粗視化、平均操作する観点から行われており、上記局所的な現象を捉えることは決してできない。本研究では粒子充填層を粗視化することなく、小スケールは小スケールのまま扱い、数値解析を行う。充填層全体に影響を及ぼすであろう、熱クリープなどの粒子の配置に依存する局所的現象を解明することを目的とし、数値モデルを極力排した大規模な直接計算を行う。

  6. 進行波中の微小物体に作用する音響放射力の測定

    More details Close

    近年のマイクロマシンやバイオテクノロジー、微細加工技術の発展に伴って、微少物体の操作はますます重要な技術として認識されてきている。μmオーダーの微少領域では微細な埃が大きな障害物として作用するため、また細胞などの壊れ易い生体物質を扱うためにはクリーンな非接触によるマニピュレーションが必要になる。超音波による音響放射力を用いたマニピュレーションは、操作範囲が広いなどの利点があり、多くの研究が行われている。しかし、周囲流体の粘性が多大な影響を及ぼすと考えられる、近年のマイクロ・マニピュレーションで対象とするようなμmオーダーの微少物体に対しては未だ十分な研究はなされているとは言えない。また、素過程である微少物体に働く音響放射力の研究も十分とはいえず、流体の持つ粘性や物体の弾性、音場の特性が放射力にどう影響を及ぼすかは、まだ不明な点が多い。本研究では、これらの影響を実験的に明らかにし、音波によるマイクロ・マニピュレーション技術の発展に寄与することを目的とする。

  7. 放射化ダストの事故時における飛散挙動解析

    More details Close

    核融合装置内では炭化水素や金属などの微粒子が存在し、これらは放射性同位体であるトリチウムの吸収や、構成金属原子の放射化などを引き起こす。核融合装置の放射能バリアである真空容器が何らかの事故により破断した場合、これらの放射化ダストが炉外に放出する可能性がある。この放射化ダストの挙動をあらかじめ解析することは安全性の観点から重要であり、これまで種々の研究が行われてきた。ITERで想定されている事故事象、ICE/LOVAでは湿潤環境下でのダストの挙動が問題となるが、従来の研究はいずれも乾燥環境下でのものであり、濡れ壁面が存在する場合などの湿潤状態を想定した研究はない。そこで本研究では湿潤環境下での粒子付着現象、その中でも濡れ壁面への粒子付着に着目し、実験を行い定量的な評価を行った。

Show all Show first 5