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Study on Accident Mitigation and Cooling of Damaged Core during Severe Accidents of Right water Reactor (Possibility of Cooling by Penetrated Water into a Narrow Gap between a Reactor Pressure Vessel and Piled-up Debris of Damaged Core)

Research Project

Project/Area Number 08650272
Research Category

Grant-in-Aid for Scientific Research (C)

Allocation TypeSingle-year Grants
Section一般
Research Field Thermal engineering
Research InstitutionKogakuin University

Principal Investigator

KOIZUMI Yasuo  Kogakuin University・Faculty of Engineering, Professor, 工学部, 教授 (20215156)

Co-Investigator(Kenkyū-buntansha) OHTAKE Hiroyasu  Kogakuin University・Faculty of Engineering, Lecturer, 工学部, 講師 (40255609)
MIYASHITA Tohru  Kogakuin University・Faculty of Engineering, Lecturer, 工学部, 講師 (00100371)
Project Period (FY) 1996 – 1997
Project Status Completed (Fiscal Year 1997)
Budget Amount *help
¥1,900,000 (Direct Cost: ¥1,900,000)
Fiscal Year 1997: ¥500,000 (Direct Cost: ¥500,000)
Fiscal Year 1996: ¥1,400,000 (Direct Cost: ¥1,400,000)
KeywordsSevere Accidents in Light Water Reactor / Reactor Safety / Narrow Flow Passage / Flow Characteristics / Two-Phase Flow / Critical Heat Flux / Flooding / Counter-Current Flow Limiting (CCFL) / 狭間隘流路 / 限界熱流束
Research Abstract

The facility used was a R-113 closed-loop. The test section was a thick wall copper pipe of 240mm in length. 100mm in OD and 34 or 36mm in ID.A glass pipe was inserted into the test pipe to from a vertical-narrow-annular flow passage of 0.5,1,2 or 5mm gap. Following the Bond number scaling, the gap size was determined from the gap width between the reactor pressure vessel and the piled-up debris of the damaged core estimated in the TMI-2 accident. Experiments performed were the critical heat flux experiments of (1) bottom-closed counter-current flow and (2) bottom drainage counter-current flow. The flow state was recorded on a VTR with a CCD camera and a fiber scope.
The mode of heat transfer was nucleate boiling. As the heat flux was increased, the critical heat flux (CHF) condition was eventually reached. However, no abrupt wall temperature increase was observed then. After the heat flux was increased more, the sharp increase in the wall temperature was perceived. In both (1) and (2) experiments, after the counter-current flow limiting (CCFL) was initiated to restrict the liquid penetration into the flow passage, unstable-intermittent dray patches were formed partially on the heated surface and the CHF point was reached. At this stage, there is no sharp wall temperature increase. After the heat flux (i.e.the upward vapor flow) was elevated more, that liquid penetration was testricted more and the liquid penetrating rate becomes less than the evaporation rate, large-stable dry-patches were created and the wall temperature excursion started. No.difference was observed between the (1) and (2) experiments in the CHF heat flux q_<CHF> and the temperature excursion initiation heat flux q_<EXC>. The values of q_<CHF> in the present experiments were much lower, approximately one order, than values predicted with existing correlations.

Report

(3 results)
  • 1997 Annual Research Report   Final Research Report Summary
  • 1996 Annual Research Report
  • Research Products

    (8 results)

All Other

All Publications (8 results)

  • [Publications] 小泉 安郎: "垂直狭隘環状流路内気液二相流の流動機構(フラッディングと限界熱流速)" 第34回日本伝熱シンポジウム講演論文集. VIII. 785-786 (1997)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1997 Final Research Report Summary
  • [Publications] 小泉 安郎: "垂直狭隘環状流路内対向気液二相流の限界熱流速" 日本原子力学会1997年秋の大会予稿集. VII. 495- (1997)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1997 Final Research Report Summary
  • [Publications] 小泉 安郎: "垂直狭隘環状流路内対向気液二相流の限界熱流速" 混相流シンポジウム'98論文集. (発表予定). (1998)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1997 Final Research Report Summary
  • [Publications] Yasuo, Koizumi: "Flow Characteristics of Two-Phase Flow in Vertical-Narrow-Annular Passages (Flooding and Critical Heat Fluxes)" Proc.of 34th National Heat Transfer Symposium of Japan.V III. 785-786 (1997)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1997 Final Research Report Summary
  • [Publications] Yasuo, Koizumi: "Critical Heat Flux of Counter-Current Two-Phase Flow in Vertical-Narrow-Gap Annuli" Proc.1997 Fall Meeting of the Atomic Energy Society of Japan. V II. 495 (1997)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1997 Final Research Report Summary
  • [Publications] Yasuo Koizumi: "Critical Heat Flux of Counter-Current Two-Phase Flow in Vertical-Narrow-Gap Annuli (to be presented.)" Proc.17th Multiphase Flow Symposium '98.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1997 Final Research Report Summary
  • [Publications] 小泉安郎: "垂直狭隘環状流路内気液二相流の流動機構(フラッディングと限界熱流束)" 第34回日本伝熱シンポジウム講演論文集. VIII. 785-786 (1997)

    • Related Report
      1997 Annual Research Report
  • [Publications] 小泉安郎: "垂直狭隘環状流路内対向気液二相流の限界熱流束" 日本原子力学会1997年秋の大会予稿集. VII. 495- (1997)

    • Related Report
      1997 Annual Research Report

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Published: 1996-04-01   Modified: 2016-04-21  

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