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Research on the characteristics of thermal hydraulics in Reduced-Moderation Natural Circulation BWR during startup stage

Research Project

Project/Area Number 14380234
Research Category

Grant-in-Aid for Scientific Research (B)

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear engineering
Research InstitutionTokyo Institute of Technology

Principal Investigator

ARITOMI Masanori  Tokyo Institute of Technology, Research Laboratory for Nuclear Reactors, Professor, 原子炉工学研究所, 教授 (60101002)

Co-Investigator(Kenkyū-buntansha) KIKURA Hiroshige  Tokyo Institute of Technology, Research Laboratory for Nuclear Reactors, Assistant Professor, 原子炉工学研究所, 助手 (00302985)
児玉 英一郎  ビジュアルテクノロジー(株), 主任研究員
Project Period (FY) 2002 – 2004
Project Status Completed (Fiscal Year 2004)
Budget Amount *help
¥15,000,000 (Direct Cost: ¥15,000,000)
Fiscal Year 2004: ¥2,200,000 (Direct Cost: ¥2,200,000)
Fiscal Year 2003: ¥4,100,000 (Direct Cost: ¥4,100,000)
Fiscal Year 2002: ¥8,700,000 (Direct Cost: ¥8,700,000)
KeywordsReduced-Moderation Natural Circulation BWR / Geysering / Density wave oscillation / Doppler effect / Wire-Mesh Tomography / SBWR / Particle-fluid model / Boiling two phase flow / 低減速自然循環沸騰水型
Research Abstract

With an aim of clarifying the thermal hydraulic characteristics in the reduced-moderation natural circulation BWR during start-up stage, fundamental experiments with regard to thermal hydraulic instability has been experimentally and analytically investigated with a natural circulation parallel boiling channels, which simulates the fundamental and representative flow characteristics around the core. The new findings are as follows.
(1)Some thermal hydraulic instabilities that might be occur during the start-up stage due to rapid condensation of steam bubbles or flashing phenomena, such as geysering phenomena and density wave oscillation, have been experimentally investigated under several input thermal conditions and the loop geometries.
(2)Bubble size is one of the important factors to determine the flow characteristics. A bubble generator is implemented to change the bubble size. Using bubble generator newly developed by this study, the results confirmed that the bubble generator could … More control the bubbles size. In order to clarify the effect of bubble size on flow structures, measurements of bubbly flow in vertical pipe were performed using ultrasonic Doppler method(UDM), wire mesh tomography(WMT) and digital image processing(DIP). Combination of the three techniques could clarify not only liquid information, but also bubbles' information.
(3)We developed measurement system to sent and received pulse ultrasound and developed the software to process received echo signal. And these systems are applied to pattern recognition of the flow pattern from bubbly flow to annular flow.
(4)Multidimensional flow analysis code based on the particle-fluid model applied to the experimental results of measured development of bubbly flow in vertical rectangular tube and vertical circular tube. And physical phenomenon to influence a bubbly flow was investigated.
(5)Based on the mentioned above results of study, we suggested stability and rational start-up procedure as well as about the necessity of chimney divide. Less

Report

(4 results)
  • 2004 Annual Research Report   Final Research Report Summary
  • 2003 Annual Research Report
  • 2002 Annual Research Report
  • Research Products

    (28 results)

All 2004 2003 Other

All Journal Article (16 results) Publications (12 results)

  • [Journal Article] Multi Parameters Effect on Thermohydraulic Instability in Natural Circulation Boiling Water Reactor during Startup2004

    • Author(s)
      M.H.Subki, M.Aritomi, N.Watanabe, M.K.Chung, H.Kikura
    • Journal Title

      JSME International Journal, Series B Vol.47, No.2

      Pages: 277-286

    • NAID

      110004826613

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] A Study of Non-symmetric Air Water Flow using Wire Mesh Sensor2004

    • Author(s)
      W.Wangjiraniran, M.Aritomi, H.Kikura, Y.Motegi, H.-M.Prasser
    • Journal Title

      Experimental Thermal and Fluid Science Vol.29, Issue 3

      Pages: 315-322

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Annual Research Report 2004 Final Research Report Summary
  • [Journal Article] On the Accuracy of Wire Mesh Tomography for Gas Liquid Flow Measurement2004

    • Author(s)
      W.Wangjiraniran, M.Justus, H.Kikura, M.Aritomi, T.Yamauchi
    • Journal Title

      Proceedings of 3rd International Symposium on Two-Phase Flow Modeling and Experimentation, Pisa, Italy No.jp28(CD-ROM)

      Pages: 1-8

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] A Study of Non-symmetric Air Water Flow using Wire Mesh Sensor2004

    • Author(s)
      W.Wangjiraniran, M.Aritomi, H.Kikura, Y.Motegi, H.-M.Prasser
    • Journal Title

      Experimental Thermal and Fluid Science, Vol.29, Issue 3

      Pages: 315-322

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] On the Accuracy of Wire Mesh Tomography for Gas Liquid Flow Measurement2004

    • Author(s)
      Weerin WANGJIRANIRAN, Matius JUSTUS, Hiroshige KIKURA, Masanori ARITOMI, Toyoaki YAMAUCHI
    • Journal Title

      Proceedings of 3rd International Symposium on Two-Phase Flow Modeling and Experimentation, Pisa, Italy (CD-ROM)Paper No.jp28

      Pages: 1-8

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Multi Parameters Effect on Thermohydraulic Instability In Natural Circulation Boiling Water Reactor during Startup2004

    • Author(s)
      M.H.Subki, M.Aritomi, N.Watanabe, M.K.Chung, H.Kikura
    • Journal Title

      JSME International Journal, Series B Vol.47, No.2

      Pages: 277-286

    • NAID

      110004826613

    • Related Report
      2004 Annual Research Report
  • [Journal Article] Thermal Hydraulic Instability Characteristic In Natural Circulation Parallel Boiling Channels Upflow System Under Low Pressure2004

    • Author(s)
      N.Watanabe, M.H.Subki, H.Kikura, M.Aritomi
    • Journal Title

      12th International Conference on Nuclear Engineering (ICONE12), Arlington, USA CD-ROM, ICO NE12-49219

      Pages: 1-8

    • Related Report
      2004 Annual Research Report
  • [Journal Article] Bubbly Flow Measurement for Each Bubble Size using Ultrasonic Doppler Method and Wire Mesh Tomography2004

    • Author(s)
      H.Murakawa, M.Shigefuzi, H.Kikura, M.Aritomi
    • Journal Title

      Proceedings of 5th International Conference on Multiphase Flow, ICMF'04 Yokohama, Japan CD-ROM, No.407

      Pages: 1-10

    • Related Report
      2004 Annual Research Report
  • [Journal Article] On the Accuracy of Wire Mesh Tomography for Gas Liquid Flow Measurement2004

    • Author(s)
      W.Wangjiraniran, M.Justus, H.Kikura, M.Aritomi, T.Yamauchi
    • Journal Title

      Proceedings of 3rd International Symposium on Two-Phase Flow Modeling and Experimentation, Pisa, Italy CD-ROM, No.jp28

      Pages: 1-8

    • Related Report
      2004 Annual Research Report
  • [Journal Article] 低減速自然循環沸騰水型炉における起動時の流動安定性に関する基礎研究2004

    • Author(s)
      渡邉紀志, モハマドースブキ, 木倉宏成, 有冨正憲
    • Journal Title

      第9回動力・エネルギー技術シンポジウム講演論文集,東京

      Pages: 557-558

    • Related Report
      2004 Annual Research Report
  • [Journal Article] Transport Mechanism of Thermohydraulic Instabilities in Natural Circulation Boiling Water Reactor during Startup2003

    • Author(s)
      M.H.Subki, M.Aritomi, N.Watanabe, H.Kikura, T.Iwamura
    • Journal Title

      Journal of Nuclear Science and Technology 40・11

      Pages: 918-931

    • NAID

      10012470170

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Intrusive Effect of Wire Mesh Tomography On Gas-liquid Flow Measurement2003

    • Author(s)
      W.Wangjiraniran, Y.Motegi, S.Richter, H.Kikura, M.Aritomi, K.Yamamoto
    • Journal Title

      Journal of Nuclear Science and Technology 40・11

      Pages: 932-940

    • NAID

      10012470188

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Measurement of Liquid Turbulent Structure in Bubbly Flow at Low Void Fraction using Ultrasonic Doppler Method2003

    • Author(s)
      H.Murakawa, H.Kikura, M.Aritomi
    • Journal Title

      Journal of Nuclear Science and Technology 40・11

      Pages: 644-650

    • NAID

      10011377400

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Transport Mechanism of Thermohydraulic Instabilities in Natural Circulation Boiling Water Reactor during Startup2003

    • Author(s)
      M.H.Subki, M.Aritomi, N.Watanabe, H.Kikura, T.Iwamura
    • Journal Title

      Journal of Nuclear Science and Technology 40-11

      Pages: 918-931

    • NAID

      10012470170

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Intrusive Effect of Wire Mesh Tomography On Gas-liquid Flow Measurement2003

    • Author(s)
      W.Wangjiraniran, Y.Motegi, S.Richter, H.Kikura, M.Aritomi, K.Yamamoto
    • Journal Title

      Journal of Nuclear Science and Technology 40-11

      Pages: 932-940

    • NAID

      10012470188

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Measurement of Liquid Turbulent Structure in Bubbly Flow at Low Void Fraction using Ultrasonic Doppler Method2003

    • Author(s)
      H.Murakawa, H.Kikura, M.Aritomi
    • Journal Title

      Journal of Nuclear Science and Technology 40-11

      Pages: 644-650

    • NAID

      10011377400

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Publications] M.H.Subki, M.Aritomi, N.Watanabe, H.Kikura, T.Iwamura: "Transport Mechanism of Thermohydraulic Instabilities in Natural Circulation Boiling Water Reactor during Startup"Journal of Nuclear Science and Technology. 40・11. 918-931 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] W.Wangjiraniran, Y.Motegi, S.Richter, H.Kikura, M.Aritomi, K.Yamamoto: "Intrusive Effect of Wire Mesh Tomography On Gas-liquid Flow Measurement"Journal of Nuclear Science and Technology. 40・11. 932-940 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] H.Murakawa, H.Kikura, M.Aritomi: "Measurement of Liquid Turbulent Structure in Bubbly Flow at Low Void Fraction using Ultrasonic Doppler Method"Journal of Nuclear Science and Technology. 40・11. 644-650 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] W.Wangjiraniran, Y.Motegi, H.Kikura, M.Aritomi, S.Richter, K.Yamamoto: "A Study of Bubbly Flow Characteristics in a Vertical Tube Using Wire Mesh Tomography"11th International Conference on Nuclear Engineering (ICONE-11), Tokyo, Japan. (CD-ROM). 36616 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] M.H.Subki, M.Aritomi, N.Watanabe, H.Kikura, M.Chung: "Transport Process of Thermohydraulic Instabilities in Natural Circulation Boiling Water Reactor during Startup"14th International Symposium on Transport Phenomena (ISTP-14), Bali-Indonesia. (CD-ROM). ISTP14551-556-SubkiMH (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] N.Watanabe, M.H.Subki, H.Kikura, M.Aritomi, M.Chung: "Effect of Channel Gap on Thermo-Hydraulic Instability in Parallel Boiling Natural Circulation Loop"The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea. (CD-ROM). A00508 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] Takemoto, T., Matsuzaki, M, Kikura, H., Aritomi, M., Bunyajitradulya, A.: "Experimental Study for the Characteristics of Steam Bubbles in a Subcooled Boiling Flow"10th International Conference on Nuclear Engineering (ICONE10), Arlington, USA. (CD-ROM), 30-4. 1-7 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] Wangjiraniran, W., Motegi, Y., Richter, S., Kikura, H., Aritomi, M., Yamamoto, K.: "Study on the Influence of Sampling Frequency of a Wire Mesh Tomography on Measured Characteristics of Gas-liquid Flow"10th International Symposium on Flow Visualization, Kyoto, Japan. (CD-ROM), F0091. 1-9 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] Murakawa, H., Kikura, H., Aritomi, M.: "Measurement of Reynolds Stress in Bubbly Flow using Ultrasonic Doppler Method"3rd International Symposium on Ultrasonic Doppler Methods for Fluid Mechanics and Fluid Engineering, Lausanne, Switzerland. 97-102 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] Motegi, Y., Wangjiraniran, W., Richter, S., Kikura, H., Aritomi, M., Yamamoto, K: "Study on Bubbly Flow in Vertical Channel using Wire Mesh Tomograph"3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, Gyeongju, Korea. 244-248 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] Watanabe, N., Subki, M.H., Kikura, H., Aritomi, M.: "Experimental Study on Thermo-Hydraulics Instability on Natural Circulation BWR Concept"3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, Gyeongju, Korea. 445-450 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] Wangjiraniran, W., Motegi, Y., Richter, S., Kikura, H., Aritomi, M.: "Intrusive Effect of Sensor on Gas Liquid flow Measurement by Wire Mesh Tomography"5th Workshop on Measurement Techniques for Steady and Transient Multiphase Flows, Rossendorf, Germany. 1-8 (2002)

    • Related Report
      2002 Annual Research Report

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Published: 2002-04-01   Modified: 2016-04-21  

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