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High Density Array of Tubes in Horizontal Tube-Bundle Evaporator

Research Project

Project/Area Number 05555067
Research Category

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

Allocation TypeSingle-year Grants
Research Field Thermal engineering
Research InstitutionKYUSHU UNIVERSITY

Principal Investigator

FUJITA Yasunobu  Kyushu Univ., Fac.of Eng., Professor, 工学部, 教授 (90037763)

Co-Investigator(Kenkyū-buntansha) UCHIDA Satoru  Kyushu Univ., Fac.of Eng., Res.Associate, 工学部, 助手 (80038041)
日高 澄具  九州大学, 工学部, 技官
Project Period (FY) 1993 – 1994
Project Status Completed (Fiscal Year 1994)
Budget Amount *help
¥6,900,000 (Direct Cost: ¥6,900,000)
Fiscal Year 1994: ¥2,500,000 (Direct Cost: ¥2,500,000)
Fiscal Year 1993: ¥4,400,000 (Direct Cost: ¥4,400,000)
KeywordsBoiling in Tube Bundle / Nucleate Boiling / In-line Array / Staggered Array / Critical Heat Flux / 高密度管配列
Research Abstract

An experimental study on nucleate boiling heat transfer was performed to investigate various effects on heat transfer characteristics in horizontal tube bundle and to gain useful information for developing an evaporator with horizontal tubes more densely arrayd. Experiments were done for in-line and ataggered tube arrangement under the conditions of natural circulation and forced circulation of fluid within a tube bundle. Findings are as follows.
(1) Compared with the performance of a single horizontal tube in pool boiling, heat transfer coefficient of tube bundle shows the same level at higher heat flux where nucleate boiling is fully established, while at lower heat flux the boiling heat transfer is highly enhanced in a bundle.
(2) The above mentioned difference in performance between a single tube and a tube bundle is true for both bundles of in-line and staggered arrangement.
(3) Under the condition of natural circulation a rise of heat transfer coefficient at lower heat flux is more enhanced as the location of tube is higher in a bundle.
(4) In the case of forced circulation, heat transfer coefficient at lower heat flux increases with an increase of circulating flow velocity. Heat transfer coefficient increases vertically at first for lower tubes, then decreases for higher tubes.
(5) As for an effect of tube pitch, a pitch to diameter ratio P/D of 1.5 shows better performance under the natural circulation, while a P/D of 1.3 is preferable for the forced circulation.

Report

(3 results)
  • 1994 Annual Research Report   Final Research Report Summary
  • 1993 Annual Research Report
  • Research Products

    (7 results)

All Other

All Publications (7 results)

  • [Publications] 藤田恭伸、日高澄具、寺野誠司: "水平管群の沸騰熱伝達と限界熱流束" 日本機械学会講演論文集. No.938-2. 54-57 (1993)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] 藤田恭伸、日高澄具、橋口卓弘: "水平管群の沸騰熱伝達と限界熱流束" 第31回日本伝熱シンポジウム講演論文集. 25-27 (1994)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] Fujita Yasunobu: "Boiling Heat Transfer and Critical Heat Flux in Horizontal Tube Bundle" Proceedings of 31st Japan Heat Transfer Symposium. 25-27 (1994)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] 藤田恭伸、日高澄具、寺野誠司: "水平管群の沸騰熱伝達と限界熱流束" 日本機械学会講演論文集. No.938-2. 54-57 (1993)

    • Related Report
      1994 Annual Research Report
  • [Publications] 藤田恭伸、日高澄具、橋口卓弘: "水平管群の沸騰熱伝達と限界熱流束" 第31回日本伝熱シンポジウム講演論文集. 25-27 (1994)

    • Related Report
      1994 Annual Research Report
  • [Publications] 藤田恭伸: "水平管群の沸騰熱伝達と限界熱流束" 日本機械学会講演論文集. No.938-2. 54-57 (1993)

    • Related Report
      1993 Annual Research Report
  • [Publications] 藤田恭伸: "水平管群の沸騰熱伝達と限界熱流束(発表予定)" 第31回日本伝熱シンポジウム講演論文集. (1994)

    • Related Report
      1993 Annual Research Report

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Published: 1993-04-01   Modified: 2016-04-21  

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