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Hydrodynamic Instability of Downward Two-Phase Flow

Research Project

Project/Area Number 60460235
Research Category

Grant-in-Aid for General Scientific Research (B)

Allocation TypeSingle-year Grants
Research Field Nuclear engineering
Research InstitutionKyushu University

Principal Investigator

FUKUDA Kenji  Kyushu University, Associate Professor, 工学部, 助教授 (90117234)

Co-Investigator(Kenkyū-buntansha) KONDOH Tetsuya  Kyushu University, Research Assistant, 工学部, 助手 (00162107)
Project Period (FY) 1985 – 1986
Project Status Completed (Fiscal Year 1986)
Budget Amount *help
¥3,200,000 (Direct Cost: ¥3,200,000)
Fiscal Year 1986: ¥900,000 (Direct Cost: ¥900,000)
Fiscal Year 1985: ¥2,300,000 (Direct Cost: ¥2,300,000)
KeywordsTow-phase flow instability / CCFL / Flooding / Dryout / 逸走型不安定 / フラッディング,CCFL / ドライアウト
Research Abstract

In postulated breaks in cold legs for LWR's or the advanced thermal reactor (ATR), downward two-phase flow may arise in the reactor core. In this case, ECC water is designed to be injected from its top, to flow downward in the core; its flow rate is limited by the CCFL - counter current flow limit. Thus, this project aims to investigate into the characteristics of downward flow especially focusing on its flow instabilities; some might be caused by the CCFL, resulting in the dryout of heating rods.
In this study, the follwing two types of experiments are carried out. Firstly, the experimental apparatus is made of the two heater channels, each consists of a 1-st riser, a downcomer and a 2-nd riser. From this experiment, three types of instabilities are observed: a 2-nd-riser-governed dynamic instability, an excursion type instability which leads to a blockage in one channel, and another one type. The second experiments are carried out with four heated downcomers, and two instability types are observed. For low flow rates, steam void goes upward against falling liquid flow, being accumulated at the top where the dryout is initiated. For high flow rates, the flooding causes the dryout at the bottom. Analyses are performed for these phenomena, which results show good agreement with the experimental data.

Report

(1 results)
  • 1986 Final Research Report Summary
  • Research Products

    (10 results)

All Other

All Publications (10 results)

  • [Publications] Kenji FUKUDA: Journal of Nuclear Science and Technology. (1987)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] 堺公明: 日本原子力学会誌 投稿予定.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] 福田研二: 第22回日本伝熱シンポジウム講演論文集C217. 398-400 (1985)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] 堺公明: 日本機械学会関西支部第7回シンポジウム=二相流講演論文集. 864-2. 25-28 (1986)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] 成合英樹: 日本原子力学会熱流動数値解析特別専門委員会 二相流ワーキンググループ報告書4章.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] Kenji FUKUDA: "Experimental Study on Two-Phase Flw Instability in a System Including Downcomers" Journal of Nuclear Science and Technology. (1987)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] Takaaki SAKAI: "On the Heat Transfer Limits of Boiling, Downward Two-Phase Flow in Parallel Channels (in Japanese)" Journal of the Atomic Energy Sciety of Japan.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] Kenji FUKUDA: "Instability of Two-Phase Flow in a System Including Downcomers (in Japanese)" Proc. Jap. Heat Transfer Conf., C217. 22. 398-400 (1985)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] Takaaki SAKAI: "On the Heat Transfer Limits of Boiling, Downward Two-Phase Flow. (in Japanese)" Proc. JSME &-th Symp. on Two-Phase Flow, Kansai Branch. 864-2. 25-28 (1986)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] Hideki NARIAI: "Linear Analysis" Rept. of Working Group in the Atomic Energy Society of Japan for "Numerical Analysis in Nuclear Reactors - Two-Phase Flow WG".

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary

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Published: 1987-03-31   Modified: 2016-04-21  

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