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Investigation of the countermeasure improvement of nuclear reactor safety components

Research Project

Project/Area Number 26870005
Research Category

Grant-in-Aid for Young Scientists (B)

Allocation TypeMulti-year Fund
Research Field Nuclear engineering
Thermal engineering
Research InstitutionHokkaido University

Principal Investigator

MIWA Shuichiro  北海道大学, 工学(系)研究科(研究院), 助教 (00705288)

Project Period (FY) 2014-04-01 – 2016-03-31
Project Status Completed (Fiscal Year 2015)
Budget Amount *help
¥3,770,000 (Direct Cost: ¥2,900,000、Indirect Cost: ¥870,000)
Fiscal Year 2015: ¥1,820,000 (Direct Cost: ¥1,400,000、Indirect Cost: ¥420,000)
Fiscal Year 2014: ¥1,950,000 (Direct Cost: ¥1,500,000、Indirect Cost: ¥450,000)
Keywords気液二相流 / 流体振動 / スラグ流 / 熱流動 / 凝縮 / 混相流 / 安全工学 / 流体力学 / 熱工学
Outline of Final Research Achievements

In this research project, experimental study was carried out to investigate the integrity of the passive safety piping components under gas-liquid two-phase flow condition. In order to simulate the internal two-phase flow phenomena observed in U-tube bend, 1 inch two-phase flow loop with elbow section was newly constructed. The loop consists of two elbow sections so that all of flow regimes can be obtained, from bubbly to annular flow. For the instrumentation, tri-axial force transducers, impedance void meter, and pressure transducers were installed to measure the dynamic force signal, void fraction fluctuation, and pressure fluctuation, respectively. Based on the newly developed database, force spectrum predictive model, applicable to 1" pipe diameter, was developed from local two fluid model, which can be applied to various engineering systems that involve gas-liquid two-phase flow.

Report

(3 results)
  • 2015 Annual Research Report   Final Research Report ( PDF )
  • 2014 Research-status Report
  • Research Products

    (9 results)

All 2016 2015 Other

All Int'l Joint Research (1 results) Journal Article (5 results) (of which Peer Reviewed: 3 results,  Acknowledgement Compliant: 1 results) Presentation (2 results) (of which Int'l Joint Research: 2 results) Remarks (1 results)

  • [Int'l Joint Research] Purdue University(米国)

    • Related Report
      2015 Annual Research Report
  • [Journal Article] Analysis of Flow Induced Vibration due to Stratified Wavy Two-phase Flow2016

    • Author(s)
      S. MIWA, T. Hibiki, M. Mori
    • Journal Title

      Journal of Fluids Engineering

      Volume: 1 Pages: 1-1

    • Related Report
      2015 Annual Research Report
    • Peer Reviewed / Acknowledgement Compliant
  • [Journal Article] 気液二相流による配管振動2015

    • Author(s)
      三輪修一郎,日引俊詞,森治嗣
    • Journal Title

      配管技術

      Volume: 1 Pages: 1-1

    • NAID

      40020300254

    • Related Report
      2015 Annual Research Report
  • [Journal Article] Two-phase flow induced vibration in piping systems2015

    • Author(s)
      11.S. Miwa, T. Hibiki, and M. Mori
    • Journal Title

      Progress in Nuclear Energy

      Volume: 78 Pages: 270-284

    • Related Report
      2015 Annual Research Report
    • Peer Reviewed
  • [Journal Article] Two-phase flow induced vibration in piping systems2015

    • Author(s)
      Shuichiro Miwa, Michitsugu Mori, Takashi Hibiki
    • Journal Title

      Progress in Nuclear energy

      Volume: 78 Pages: 270-284

    • DOI

      10.1016/j.pnucene.2014.10.003

    • Related Report
      2014 Research-status Report
    • Peer Reviewed
  • [Journal Article] 気液二相流における配管振動2015

    • Author(s)
      三輪修一郎,日引俊詞,森治嗣
    • Journal Title

      配管技術,日本工業出版

      Volume: 57 Pages: 32-37

    • Related Report
      2014 Research-status Report
  • [Presentation] Prediction of Two-phase Flow Induced Vibration using Artificial Void Signal2015

    • Author(s)
      S. Miwa, T. Hibiki, and M. Mori
    • Organizer
      International Conference on Nuclear Engineering
    • Place of Presentation
      Makuhari, Chiba, JAPAN
    • Year and Date
      2015-05-17
    • Related Report
      2015 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Development of Internal Two-phase Flow Induced Force Fluctuations Model2015

    • Author(s)
      S. Miwa, T. Hibiki, and M. Mori
    • Organizer
      Japan-US Seminar on Two-phase Flow Dynamics
    • Place of Presentation
      Purdue University, West Lafayette, IN, USA
    • Year and Date
      2015-05-10
    • Related Report
      2015 Annual Research Report
    • Int'l Joint Research
  • [Remarks] 北海道大学 原子力システム安全工学研究室HP

    • URL

      http://nuclearsafety.eng.hokudai.ac.jp/

    • Related Report
      2015 Annual Research Report

URL: 

Published: 2014-04-04   Modified: 2022-01-27  

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