Basic Information

Affiliated programs (koza)

• Graduate School of Engineering, 原子核工学専攻 核システム工学講座, 助教

Email Address

• Email Address

  shen.xiuzhong.5vkyoto-u.ac.jp

Professional Memberships

• From Apr. 2017, To Present

  The Heat Transfer Society of Japan
• From May 2003, To Present

  The Japanese Society for Multiphase Flow
• From Dec. 2002, To Present

  Atomic Energy Society of Japan
• From Oct. 2002, To Present

  The Japan Society of Mechanical Engieers

Academic Degree

• Master(Shanghai Jiaotong University)
• Doctor(Shanghai Jiaotong University)

Language of Instruction

• Japanese
• English
• Chinese

ID,URL

• J-Global ID

  200901083510816707

• External link

  https://scholar.google.co.jp/citations?hl=ja&user=hTS4TYUAAAAJ&view_op=list_works&authuser=1&gmla=AJsN-F5NeFfKYtD_N5qudm3Hb2tikJbtCaBTolJ4C-siGChJhROEucPxc8JrEV6WUSBCXQ3vTrhy4puZXEVItppY5f47fk_UVLA6_mwYtfrU_rys8TiT0FqwIqZWIKo96bOvTVFieSCTr7PTF6rEmSlypQalW1nJ_H9A54II_ObNzz9YIsWnODleQwN0Ts7XfOg7QXR7C7MUqVR5VXVXq3IypZe65XjnTQ&sciund=1916400973058003826

researchmap URL

• https://researchmap.jp/read0096718

Research

Research Topics, Overview of the research

• Research Topics

  Safety analysis for nuclear reactor, Efficient energy transport, Boiling heat transfer, Multi-dimensional two-phase flow

• Overview of the research

  We pursue safe and efficient use of high-density thermal energy produced in various next generation nuclear energy systems, such as an advanced nuclear reactor, fusion reactor and an accelerator-driven nuclear energy system. The research activity covers basic studies on the characteristics and the control of thermal-hydraulic phenomena under various extreme conditions which are encountered in the next generation nuclear energy systems.

Research Interests

• 熱工水力
• 伝熱
• 二相流
• Thermohydraulics
• Heat Transfer
• Two-phase flow

Research Areas

• Energy, Nuclear engineering
• Manufacturing technology (mechanical, electrical/electronic, chemical engineering), Thermal engineering
• Manufacturing technology (mechanical, electrical/electronic, chemical engineering), Fluid engineering

Papers

• A full-flow-range drift-flux model for adiabatic and boiling two-phase flows in vertical narrow rectangular flow channels

  Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima; Takashi Hibiki

  International Journal of Thermal Sciences, Aug. 2024, Peer-reviewed, Lead author, Corresponding author

  
• Corrigendum to ‘Interfacial area concentration in gas-liquid bubbly to churn flow regimes in large diameter pipes’ [International Journal of Heat and Fluid Flow 54 (2015) 107–118]

  Xiuzhong Shen; Takashi Hibiki

  International Journal of Heat and Fluid Flow, Dec. 2018

  
• Corrigendum to “Development of interfacial area concentration correlations for small and large bubbles in gas-liquid two-phase flows” [Int. J. Multiph. Flow 87 (2016) 136–155]

  Xiuzhong Shen; Baoqing Deng

  International Journal of Multiphase Flow, Nov. 2018

  
• Corrigendum to ‘Interfacial area concentration in gas-liquid bubbly to churn flow regimes in large diameter pipes’ (Interfacial area concentration in gas–liquid bubbly to churn flow regimes in large diameter pipes (2015) 54 (107–118), (S0142727X1500048X) (10.1016/j.ijheatfluidflow.2015.05.002))

  Shen, X.; Hibiki, T.

  International Journal of Heat and Fluid Flow, 2018

  
• Corrigendum to “Development of interfacial area concentration correlations for small and large bubbles in gas-liquid two-phase flows” [Int. J. Multiph. Flow 87 (2016) 136–155] (International Journal of Multiphase Flow (2016) 87 (136–155), (S030193221630043X) (10.1016/j.ijmultiphaseflow.2016.07.017))

  Shen, X.; Deng, B.

  International Journal of Multiphase Flow, 2018

  
• Flow Characteristics and Void Fraction Prediction in Large Diameter Pipes

  Xiuzhong Shen; Joshua P. Schlegel; Shaowen Chen; Somboon Rassame; Matthew J. Griffiths; Takashi Hibiki; Mamoru Ishii

  Frontiers and Progress in Multiphase Flow I, 2014

  
• Simulated experimental research on flow field near control rod guide tubes

  Yu, Ping{'}an; Shen, Xiuzhong; Yang, Guanyue; He, Fangzheng; Gao, Weiguo; Zhang, Zhiyi; Tian, Ji{'}an

  Hedongli Gongcheng/Nuclear Power Engineering, 1997

  
• Prediction of interfacial area transport in a coupled two-fluid model computation

  Joshua P. Schlegel; Takashi Hibiki; Xiuzhong Shen; Santosh Appathurai; Hariprasad Subramani

  Journal of Nuclear Science and Technology, 11 Jul. 2016, Peer-reviewed

  
• Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly

  Vikrant Siddharudh Chalgeri; Xiuzhong Shen; Toshihiro Yamamoto

  Annals of Nuclear Energy, Jun. 2024, Peer-reviewed, Corresponding author

  
• Experimental investigation on local flow structures of upward cap-bubbly flows in a vertical large-size square channel

  Haomin Sun; Tomoaki Kunugi; Takehiko Yokomine; Xiuzhong Shen; Takashi Hibiki

  Experimental Thermal and Fluid Science, May 2024, Peer-reviewed

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• Void fraction and interfacial area concentration of two-phase flow in a rod bundle fuel assembly

  Zuo, Jiaxu; Shen, Xiuzhong; Chalgeri, Vikrant Siddharudh; Yamamoto, Toshihiro

  第58回京都大学複合原子力科学研究所学術講演会，論文番号：P22，pp. 34，2024年1月31日-2月1日。, Jan. 2024, Corresponding author

  
• Experimental study on local interfacial parameters in gas-liquid two-phase flow within a plate-type fuel element

  Chalgeri, Vikrant Siddharudh; Shen, Xiuzhong; Yamamoto, Toshihiro

  第58回京都大学複合原子力科学研究所学術講演会，論文番号：P21，pp. 33，2024年1月31日-2月1日。, Jan. 2024, Corresponding author

  
• Assessment of INSS drift-flux correlation for rod bundle at low-flow and low-pressure conditions

  Kinoshita, Ikuo; Hibiki, Takashi; Shen, Xiuzhong

  Proceedings of the 11th International Conference on Multiphase Flow (ICMF) 2023 at Kobe, Japan, Paper No.: ICMF2023-248, April 2-7, 2023., Apr. 2023, Last author

  
• MTR型燃料要素の冷却流路内気液二相流界面積濃度に関する研究

  沈秀中; 山本俊弘; 日引俊詞

  第56回京都大学複合原子力科学研究所学術講演会，論文番号：D-7，pp. 46，2022年2月9-10日, Feb. 2022, Lead author, Corresponding author

  
• Multi-dimensional characteristics of upward bubbly flows in a vertical large-size square channel

  Haomin Sun; Tomoaki Kunugi; Takehiko Yokomine; Xiuzhong Shen; Takashi Hibiki

  International Journal of Heat and Mass Transfer, 01 Sep. 2023

  
• Multi-dimensional characteristics of upward bubbly flows in a vertical large-size square channel

  Haomin Sun; Tomoaki Kunugi; Takehiko Yokomine; Xiuzhong Shen; Takashi Hibiki

  INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, Sep. 2023

  
• Dynamic mode decomposition application to dominance ratio assessment in Monte Carlo k-eigenvalue calculation

  Toshihiro Yamamoto; Xiuzhong Shen; Hiroki Sakamoto

  Annals of Nuclear Energy, Sep. 2022

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• Advances in time-dependent Monte Carlo simulations for void velocity determination using neutron noise techniques

  Toshihiro Yamamoto; Xiuzhong Shen; Hiroki Sakamoto

  Progress in Nuclear Energy, Jun. 2021, Peer-reviewed

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• Interfacial area concentration in gas-liquid metal two-phase flow

  Xiuzhong Shen; Toshihiro Yamamoto; Xu Han; Takashi Hibiki

  Experimental and Computational Multiphase Flow, 01 Mar. 2023, Peer-reviewed, Lead author, Corresponding author

  
• Distribution parameter and drift velocity for upward gas-liquid metal two-phase flow

  Shen, X.; Hibiki, T.

  Applied Thermal Engineering, Feb. 2021, Peer-reviewed, Lead author, Corresponding author

  
• ロッドバンドル流路における高低圧気液二相流の分布パラメーターとドリフト速度

  韓旭; 沈秀中; 山本俊弘; 中島健; 日引俊

  第55回京都大学複合原子力科学研究所学術講演会，論文番号：P01，pp. 12，2021年1月28-29日, Jan. 2021, Corresponding author

  
• Drift-flux correlation for upward gas-liquid two-phase flow in vertical rod bundle flow channel

  Xu Han; Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima; Takashi Hibiki

  International Journal of Heat and Mass Transfer, Dec. 2020, Peer-reviewed, Corresponding author

  
• Flow characteristics of upward two-phase flows in a rod bundle geometry

  Han, Xu; Shen, Xiuzhong; Yamamoto, Toshihiro; Nakajima, Ken; Hibiki, Takashi

  Proceedings of ASME’s Power 2020 and Nuclear Engineering Conference powered by ICONE, Paper No.: ICONE28-POWER2020-14568, Virtual Conference, August 4-5, 2020, Aug. 2020, Peer-reviewed, Corresponding author

  
• A two-phase flow database in a light-water-reactor-simulated rod bundle

  Han, Xu; Shen, Xiuzhong; Yamamoto, Toshihiro; Nakajima, Ken; Hibiki, Takashi

  54th Annual Conference of Kyoto University Institute for Integrated Radiation and Nuclear Science, Paper No.: P32, Feb. 2020, Corresponding author

  
• 

  Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6 × 6 rod bundle

  Xu Han; Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima; Haomin Sun; Takashi Hibiki

  International Journal of Heat and Mass Transfer, Dec. 2019, Peer-reviewed

  
• 

  Local measurements of upward air-water two-phase flows in a vertical 6×6 rod bundle

  Shen, X.; Miwa, S.; Xiao, Y.; Han, X.; Hibiki, T.

  Experimental and Computational Multiphase Flow, Sep. 2019, Peer-reviewed

  
• Study on flow mechanism of multi-dimensional gas-liquid two-phase flow in large-diameter channels

  Shen, Xiuzhong; Hibiki, Takashi; Nakamura, Hideo

  The 53rd Annual Conference of Kyoto University Institute for Integrated Radiation and Nuclear Science, Paper No.: T6，pp. 78-80, Feb. 2019

  
• Experimental study on interfacial area concentration in gas-liquid two-phase flows in a rod bundle flow channel

  Shen, Xiuzhong; Miwa, Shuichiro; Xiao, Yigeng; Sun, Haomin; Hibiki, Takashi

  The 53rd Annual Conference of Kyoto University Institute for Integrated Radiation and Nuclear Science，Paper No.：P8，pp. 16, Feb. 2019

  
• 

  Bubble coalescence and breakup model evaluation and development for two-phase bubbly flows

  Xiuzhong Shen; Takashi Hibiki

  International Journal of Multiphase Flow, Dec. 2018, Peer-reviewed

  
• Constitutive equations for vertical upward two-phase flow in rod bundle

  Takashi Hibiki; Tetsuhiro Ozaki; Xiuzhong Shen; Shuichiro Miwa; Ikuo Kinoshita; Tatsuya Hazuku; Somboon Rassame

  International Journal of Heat and Mass Transfer, Dec. 2018, Peer-reviewed

  
• An evaluation of one-group interfacial area transport equation with its constitutive bubble coalescence and breakup models in bubbly two-phase flows

  Shen, Xiuzhong; Hibiki, Takashi

  Proceeding of the 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) at Qingdao, China, Paper No.: 568, Oct. 2018, Peer-reviewed

  
• Local Gas-Liquid Two-Phase Flow Characteristics in Rod Bundle Geometry

  Xiao, Yigeng; Shen, Xiuzhong; Miwa, Shuichiro; Sun, Haomin; Hibiki, Takashi

  JSMF Multiphase Flow Symposium, Aug. 2018

  
• Some characteristics of gas–liquid two-phase flow in vertical large-diameter channels

  Xiuzhong Shen; Joshua P. Schlegel; Takashi Hibiki; Hideo Nakamura

  Nuclear Engineering and Design, 01 Jul. 2018, Peer-reviewed

  
• Experimental study on bubble dispersion phenomena in gas-liquid two-phase flows in a fuel assembly channel box

  Shen, Xiuzhong; Hibiki, Takashi

  The 52nd Annual Conference of Kyoto University Research Reactor Institute, Paper No., P18，pp. 32, Jan. 2018

  
• Experimental study on interfacial area transport of two-phase bubbly flow in a vertical large-diameter,square duct

  Xiuzhong Shen; Haomin Sun; Baoqing Deng; Takashi Hibiki; Hideo Nakamura

  INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, Oct. 2017, Peer-reviewed

  
• Axial flow characteristics of bubbly flow in a vertical large-diameter square duct

  Shen, Xiuzhong; Sun, Haomin; Deng, Baoqing; Hibiki, Takashi; Nakamura, Hideo

  Proceeding of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) at Xi'an, Shaanxi, China, Paper No.: NURETH-17-20863, Sep. 2017, Peer-reviewed

  
• Multi-dimensional gas-liquid two-phase flow in vertical large-diameter channels

  Shen, Xiuzhong; Schlegel, Joshua P; Hibiki, Takashi; Nakamura, Hideo

  Proceeding of the 11th Japan-U.S. Seminar on Two-Phase Flow Dynamics at Sapporo, Hokkaido, Japan, Jun. 2017

  
• Interfacial area concentration transport model for gas-liquid two-phase flows in rod bundle channels

  Shen, Xiuzhong; Deng, Baoqing

  The 51st Annual Conference of Kyoto University Research Reactor Institute, Paper No.: P22，pp. 36, Jan. 2017

  
• Prediction of interfacial area transport in a coupled two-fluid model computation

  Joshua P. Schlegel; Takashi Hibiki; Xiuzhong Shen; Santosh Appathurai; Hariprasad Subramani

  JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2017, Peer-reviewed

  
• Development of interfacial area concentration correlations for small and large bubbles in gas-liquid two-phase flows

  Xiuzhong Shen; Baoqing Deng

  INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, Dec. 2016, Peer-reviewed

  
• Estimation of interfacial area concentrations for two-group bubbles in gas-liquid two-phase flows

  Shen, Xiuzhong; Deng, Baoqing

  Proceeding of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11) at Gyeongju, Korea, Paper No.: N11P0136, Oct. 2016, Peer-reviewed

  
• 

  Gas-liquid bubbly flow structure in a vertical large-diameter square duct

  Xiuzhong Shen; Haomin Sun; Baoqing Deng; Takashi Hibiki; Hideo Nakamura

  PROGRESS IN NUCLEAR ENERGY, May 2016, Peer-reviewed

  
• Flow characteristics study on low-flow-rate gas-liquid two-phase flows in a LWR rod bundle channel

  SHEN Xiuzhong; HIBIKI Takashi

  The 50th Annual Conference of Kyoto University Research Reactor Institute, Paper No.: P23, Jan 27-28, 2016, Jan. 2016

  
• CFD simulation of an unbaffled stirred tank reactor driven by a magnetic rod: assessment of turbulence models

  Jiajia Li; Baoqing Deng; Bing Zhang; Xiuzhong Shen; Chang Nyung Kim

  WATER SCIENCE AND TECHNOLOGY, Oct. 2015, Peer-reviewed

  
• CFD simulation on hydrodynamics in fluidized beds: assessment of gradient approximations and turbulence models

  Yuan Guo; Baoqing Deng; Daqiang Ge; Xiuzhong Shen

  HEAT AND MASS TRANSFER, Aug. 2015, Peer-reviewed

  
• Evaluation of interfacial area transport equation in coupled two-fluid model computation

  Schlegel, Joshua P; Hibiki, Takashi; Shen, Xiuzhong; Appathurai, S; Subramani, H

  Proceeding of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) at Hyatt Regency, Chicago, Illinois, USA, Paper No.: NURETH-16-13363, Aug. 2015, Peer-reviewed

  
• Interfacial area concentration in gas-liquid bubbly to churn flow regimes in large diameter pipes

  Xiuzhong Shen; Takashi Hibiki

  INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, Aug. 2015, Peer-reviewed

  
• Two-group interfacial area concentration correlations of two-phase flows in large diameter pipes

  Shen, Xiuzhong; Hibiki, Takashi

  Proceeding of the 23rd International Conference on Nuclear Engineering (ICONE-23) at Makuhari Messe, Chiba, Japan, Paper No.: ICONE23-1795, May 2015, Peer-reviewed

  
• Bubbly-to-cap bubbly flow transition in a long-26 m vertical large diameter pipe at low liquid flow rate

  Xiuzhong Shen; Takashi Hibiki; Hideo Nakamura

  INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, Apr. 2015, Peer-reviewed

  
• Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode

  Jian Zhang; Xiuzhong Shen; Yasuyuki Fujihara; Tadafumi Sano; Toshihiro Yamamoto; Ken Nakajima

  Annals of Nuclear Energy, Feb. 2015, Peer-reviewed

  
• Development of four-sensor probe method for gas-liquid two-phase flow measurement

  Shen, Xiuzhong; Nakamura, Hideo

  The 49th Annual Conf. Kyoto University Research Reactor Institute, Jan. 2015

  
• Local measurements of 3-D bubble velocity vector, bubble diameter and interfacial area concentration in a vertical large diameter square duct

  Shen, Xiuzhong; Hibiki, Takashi; Sun, Haomin; Nakamura, Hideo

  Proceeding of the 9th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Buyeo, Korea, Paper No.: N9P0011, Nov. 2014, Peer-reviewed

  
• Studies on ADS as a neutron source at the Kyoto University Research Reactor Institute

  T. Yoshiie; K. Fukumoto; Y. Ishi; D. Ito; Y. Kuriyama; T. Misawa; Y. Mori; T. Nagasaka; K. Nakajima; Y. Oki; C. H. Pyeon; Y. Saito; K. Sato; X Shen; S. Shibata; T. Uesugi; Q. Xu

  JOURNAL OF NUCLEAR MATERIALS, Jul. 2014, Peer-reviewed

  
• Implementation of two-group interfacial area transport in a one-dimensional computational environment

  Schlegel, Joshua P; Hibiki, Takashi; Ishii, Mamoru; Shen, Xiuzhong; Appathurai, S

  Proceeding of International Topical Meeting on Advances in Thermal Hydraulics 2014 (ATH’14), Reno, Nevada, USA, Paper No.: 042, pp. 555-567, Jun. 2014, Peer-reviewed

  
• Spherical-bubble-based four-sensor probe signal processing algorithm for two-phase flow measurement

  Xiuzhong Shen; Hideo Nakamura

  INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, Apr. 2014, Peer-reviewed

  
• Upward air-water bubbly flow characteristics in a vertical square duct

  Haomin Sun; Tomoaki Kunugi; Xiuzhong Shen; Dazhuan Wu; Hideo Nakamura

  JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, Mar. 2014, Peer-reviewed

  
• One-group interfacial area transport equation and its sink and source terms in narrow rectangular channel

  Xiuzhong Shen; Takashi Hibiki

  INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, Dec. 2013, Peer-reviewed

  
• Studies of ADS for neutron source in the Kyoto University Research Reactor Institute

  Yoshiie, Toshimasa; Fukumoto, K; Ishi, Yoshihiro; Ito, Daisuke; Kuriyama Yasutoshi; Misawa, Tsuyoshi; Mori, Yoshiharu; Nagasaka, T; Nakajima, Ken; Oki, Yuichi; Pyeon, Cheolho; Saito, Yasushi; Sato, Koichi; Shen Xiuzhong; Shibata, Seiichi; Uesugi, Tomonori; Xu , Qiu

  The 11th International Workshop on Spallation Materials Technology, at Ghent, Belgium, November 5-9, 2012, Nov. 2013, Peer-reviewed

  
• 大口径正方形管内気液二相流の流動特性研究

  沈秀中; 日引俊; 中村秀夫

  日本混相流学会混相流シンポジウム2013，論文番号：A314，信州大学工学部，長野県、2013年8月9-11日, Aug. 2013, Peer-reviewed

  
• Experimental Investigation on Natural Circulation Capability of Kyoto University Research Reactor

  Zhang, Jian; Shen, Xiuzhong; Fujihara, Yasuyuki; Sano, Tadafumi; Yamamoto, Toshihiro; Nakajima, Ken; Oono, Kazuomi; Nakamori, Akira; Maruyama, Naoya; Hasegawa, Kiyoshi; Tsuchiyama, Tatsuo; Takahashi, Yoshiyuki; Minami, Kaoru; Okumura, Kiyoshi

  The 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Pisa, Italy, Paper No.: NURETH15-125, May 2013, Peer-reviewed

  
• Interfacial area transport of Gas-liquid bubbly flow in mini channel

  Shen, Xiuzhong; Hibiki, Takashi

  The 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Pisa, Italy, Paper No.: NURETH15-439, May 2013, Peer-reviewed

  
• A Study on Air-water Two-phase Upward Turbulent Flow in a Large Square Duct

  Sun, Haomin; Kunugi, Tomoaki; Shen, Xiuzhong; Nakamura, Hideo

  The 8th International Conference on Multiphase Flow (ICMF) 2013, Jeju, Korea, May 26-31, 2013, Paper No.: ICMF2013-244., May 2013, Peer-reviewed

  
• Local interfacial velocity measurement method using a four-sensor probe

  Xiuzhong Shen; Hideo Nakamura

  International Journal of Heat and Mass Transfer, 2013, Peer-reviewed

  
• Reactivity insertion transient analysis for KUR low-enriched uranium silicide fuel core

  Xiuzhong Shen; Ken Nakajima; Hironobu Unesaki; Kaichiro Mishima

  Annals of Nuclear Energy, 2013, Peer-reviewed

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• 研究炉安全に関する炉心模擬流路内気液二相流の界面積濃度輸送モデルの開発

  沈秀中; 日引俊

  第47回京都大学原子炉実験所学術講演会(47th Annual Conf. Kyoto University Research Reactor Institute)，論文番号：P27，pp. 166-171，2013年1月29-30日, Jan. 2013

  
• New Four-Sensor Probe Theory for Multi-Dimensional Two-Phase Flow Measurement

  Shen, Xiuzhong; Nakamura, Hideo

  The 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), Beppu, Japan, December 9-12, 2012, Paper No.: N8P1006, Dec. 2012, Peer-reviewed

  
• One-dimensional interfacial area transport of vertical upward bubbly flow in narrow rectangular channel

  Xiuzhong Shen; Takashi Hibiki; Takafumi Ono; Kenichi Sato; Kaichiro Mishima

  INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, Aug. 2012, Peer-reviewed

  
• Developing structure of two-phase flow in a large diameter pipe at low liquid flow rate

  Xiuzhong Shen; Takashi Hibiki; Hideo Nakamura

  INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, Apr. 2012, Peer-reviewed

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• 研究炉燃料要素の彎曲狭隘矩形流路内の伝熱と流動研究

  沈秀中; 鄧保慶

  第46回京都大学原子炉実験所学術講演会(46th Annual Conf. Kyoto University Research Reactor Institute), Feb. 2012

  
• GAS-LIQUID BUBBLY TURBULENT UPWARD FLOW IN SQUARE DUCT

  HaoMin Sun; Tomoaki Kunugi; DaZhuan Wu; HongNa Zhang; Hideo Nakamura; XiuZhong Shen

  PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 5, 2012, Peer-reviewed

  
• Interfacial Drag Model and Numerical Analysis for Gas-Liquid Two-Phase Flow in a Large Diameter Pipe

  Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

  Japanese Journal of Multiphase Flow, Mar. 2011, Peer-reviewed

  
• 京都大学原子炉実験所における加速器駆動未臨界炉の基礎研究（3）材料照射効果と除熱技術研究

  義家敏正; 齊藤泰司; 佐藤紘一; 徐ぎゅう; 沈秀中; 中島健

  日本原子力学会“2011年春の年会”，福井大学文京キャンパス，論文番号：N03，pp. 655, Mar. 2011

  
• FLOW-INDUCED VOID FRACTION TRANSITION PHENOMENON IN TWO-PHASE FLOW

  Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

  PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 4 PTS A AND B, 2011, Peer-reviewed

  
• Distribution parameter and drift velocity for two-phase flow in a large diameter pipe

  Xiuzhong Shen; Ryota Matsui; Kaichiro Mishima; Hideo Nakamura

  NUCLEAR ENGINEERING AND DESIGN, Dec. 2010, Peer-reviewed

  
• Axial development of gas-liquid flow parameters in a narrow rectangular channel

  Shen, Xiuzhong; Mishima, Kaichiro; Nakamura, Hideo

  Transactions of the American Nuclear Society, 07 Nov. 2010, Peer-reviewed, Invited

  
• Development of Beam Window Materials for Accelerator Driven System in the Kyoto University

  Toshimasa YOSHIIE; Yoshihiro ISHI; Yasutoshi KURIYAMA; Yoshiharu MORI; Tsuyoshi MISAWA; Ken NAKAJIMA; Yuichi OKI; Yasushi SAITO; Koichi SATO; Xiu-Zhong SHEN; Seiichi SHIBATA; Tomonori UESUGI; Qiu Xu

  The 10th Japan-China Symposium (JCS-10) on Materials for Advanced Energy Systems and Fission & Fusion Engineering, at Uji, Kyoto, Japan, Oct. 2010, Peer-reviewed

  
• 大口径管内気液二相流の界面抗力モデルと数値解析

  沈秀中; 三島嘉一郎; 中村秀夫

  日本混相流学会年会講演会２０１０講演論文集，論文番号：130，pp. 400-401，静岡大学，静岡県, Jul. 2010, Peer-reviewed

  
• Measurement of Two-Phase Flow in a Vertical Large Diameter Pipe using Hot-Film Anemometer

  Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

  Japanese Journal of Multiphase Flow, Mar. 2010, Peer-reviewed

  
• Safety Assessment of KUR Low-Enriched Uranium Silicide Core

  Xiuzhong Shen; Kaichiro Mishima; Ken Nakajima

  Technical Report of Research Reactor Institute、 Kyoto University、 KURRI-TR-442, 2010, Peer-reviewed

  
• 熱線流速計による垂直大口径管内の気液二相流の計測

  沈秀中; 三島嘉一郎; 中村秀夫

  日本混相流学会年会講演会２００９講演論文集，論文番号：E326，pp. 326-327，熊本大学，熊本県, Aug. 2009, Peer-reviewed

  
• Shape measurement of bubble in a liquid metal

  Y. Saito; X. Shen; K. Mishima; M. Matsubayashi

  NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, Jun. 2009, Peer-reviewed

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• Distribution Parameter and Drift Velocity for Two-Phase Flow in a Large Diameter Pipe

  Shen, Xiuzhong; Matsui, Ryota; Mishima, Kaichiro; Nakamura, Hideo

  Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), Okinawa, Japan, Paper No.: N6P1121, Nov. 2008, Peer-reviewed

  
• Shape measurement of bubble in a liquid metal

  Saito, Yasushi; Shen, Xiuzhong; Mishima, Kaichiro; Matsubayashi, Masahito

  6th International Topical Meeting on Neutron Radiography at Kobe, Japan, Paper No.: P313, Sep. 2008, Peer-reviewed

  
• A method for measuring local instantaneous interfacial velocity vector in multi-dimensional two-phase flow

  Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

  INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, May 2008, Peer-reviewed

  
• Error reduction, evaluation and correction for the intrusive optical four-sensor probe measurement in multi-dimensional two-phase flow

  Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

  INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, Feb. 2008, Peer-reviewed

  
• A study on the characteristics of upward air-water two-phase flow in a large diameter pipe

  Xiuzhong Shen; Yasushi Saito; Kaichiro Mishima; Hideo Nakamura

  EXPERIMENTAL THERMAL AND FLUID SCIENCE, Oct. 2006, Peer-reviewed

  
• Methodology of local instantaneous interfacial velocity measurement in multi-dimensional two-phase flow

  Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

  International Conference on Nuclear Engineering, Proceedings, ICONE, 2006, Peer-reviewed

  
• 大口径管内の二相流の流動特性

  沈秀中; 三島嘉一郎; 中村秀夫

  日本混相流学会年会講演会２００５講演論文集，論文番号：E143，pp. 175-176，2005年8月1-3日, Aug. 2005, Peer-reviewed

  
• Methodological improvement of an intrusive four-sensor probe for the multi-dimensional two-phase flow measurement

  X Shen; Y Saito; K Mishima; H Nakamura

  INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, May 2005, Peer-reviewed

  
• Two-phase phase distribution in a vertical large diameter pipe

  X Shen; K Mishima; H Nakamura

  INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, Jan. 2005, Peer-reviewed

  
• Two-Phase Phase Distribution Effect on Drift-Flux Parameters in a Vertical Large Diameter Pipe

  Shen, Xiuzhong; Saito, Yasushi; Mishima, Kaichiro; Nakamura, Hideo

  The 3rd Int. Symp. on Two-Phase Flow Modeling and Experimentation, Pisa, Italy, Paper No. JP26, Sep. 2004, Peer-reviewed

  
• Error Reduction, Evaluation and Correction for the Intrusive Optical Four-Sensor Probe Measurement in Multi-Dimensional Two-Phase Flow

  Shen, Xiuzhong; Mishima, Kaichiro; Nakamura, Hideo

  The 5th International Conference on Multiphase Flow, Yokohama, Japan, Paper No. 355, Jun. 2004, Peer-reviewed

  
• Physics and thermodynamics study on lead cooled fast breeder reactor

  Shen, Xiuzhong; Yang, Xiuzhou; Yu, Ping’an

  Nuclear Techniques, Dec. 2003, Peer-reviewed

  
• Gas-liquid two-phase phase distribution in vertical large diameter pipe

  Shen, Xiuzhong; Saito, Yasushi; Mishima, Kaichiro; Nakamura, Hideo

  The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, Paper No.: A00311, Oct. 2003, Peer-reviewed

  
• 大口径管内の界面面積濃度計測

  沈秀中; 齊藤泰司; 三島嘉一郎; 中村秀夫

  日本混相流学会年会講演会２００３講演論文集，論文番号：E3，pp. 99-101，2003年7月23-25日, Jul. 2003, Peer-reviewed

  
• A study on the characteristics of upward air-water two-phase flow in a large pipe

  Shen, Xiuzhong; Mishima, Kaichiro; Nakamura, Hideo

  The 11th International Conference on Nuclear Engineer at Tokyo, Japan, Paper No.: ICONE11-36062, Apr. 2003, Peer-reviewed

  
• 垂直大口径管内気液二相流の相分布

  沈秀中; 齊藤泰司; 三島嘉一郎; 中村秀夫

  日本原子力学会“2003年春の年会”，アルカス佐世保，論文番号：J31，pp. 457，2003年3月27-29日, Mar. 2003

  
• Improved measurement method for interfacial area concentration in a large-diameter tube

  Shen, Xiuzhong; Mishima, Kaichiro; Nakamura, Hideo

  Proceeding of the 6th ASME-JSME Thermal Engineering Joint Conference at Hawaii, USA, TED-AJ03-389, Mar. 2003, Peer-reviewed

  
• Liquid Metal Magnetohydrodynamic Power Generation Systems

  Liu, Yang; Shen, Xiuzhong; Chen, Ke

  Power Equipment, Oct. 2002, Peer-reviewed

  
• Hydromechanical investigation on 3 PWR upper plenum core structures

  Shen, X.; Yu, P.; Yang, G.

  Nuclear Engineering and Design, Sep. 2002, Peer-reviewed

  
• The inherent safety analysis for lead cooled fast breeder reactor

  Shen, Xiuzhong; Yu, Ping’an; Yang, Xiuzhou; Xu, Jijun

  Nuclear Power Engineering, Aug. 2002, Peer-reviewed

  
• Modularization and simulation of facial heater

  Cai, Riji; Zhang, Qinshun; Zou, Wenjun; Chen, Ke; Shen, Xiuzhong; Dai, Zhengxi

  Chinese Journal of System Simulation, May 2002, Peer-reviewed

  
• A flow boiling heat transfer correlation for narrow channel

  Shen, Xiuzhong; Liu, Yang; Zhang, Qinshun

  Nuclear Power Engineering, Feb. 2002, Peer-reviewed

  
• A study on liquid lithium flow in rectangular duck perpendicular to a intense magnetic field

  Shen, Xiuzhong; Chen, Ke; Liu, Yang; Zhang, Qinshun

  Chinese Journal of Nuclear Science and Engineering, Dec. 2001, Peer-reviewed

  
• Real-time dynamic simulation of the steam generator

  Chen, Ke; Zhang,Qinshun; Shen, Xiuzhong; Cai Riji

  Boiler Technology, Nov. 2001, Peer-reviewed

  
• Simulation of Candu 9 steam generator

  Dai, Zhengxi; Chen, Ke; Zhang, Qinshun; Shen, Xiuzhong; Cai, Riji

  Modern Machinery, Oct. 2001, Peer-reviewed

  
• A study on the flow boiling heat transfer characteristics in narrow inside heating annuli

  Shen, Xiuzhong; Miyazaki, Keiji; Xu, Jijun

  Chinese Journal of Nuclear Science and Engineering, Sep. 2001, Peer-reviewed

  
• Modularization and simulation of steam-water separator

  Cai, Riji; Zhang, Qinshun; Zou, Wenjun; Chen, Ke; Shen, Xiuzhong; Dai, Zhengxi; Li, Xiaoyan; Xu, Jijun

  Modern Machinery, Jul. 2001, Peer-reviewed

  
• Modularization and simulation of reheater

  Zhang, Q.S.; Zou, W.J.; Cai, R.J.; Chen, K.; Shen, X.Z.; Dai, Z.X.; Li, X.Y.; Wang, X.B.

  Dongli Gongcheng/Power Engineering, Jun. 2001, Peer-reviewed

  
• Application probe of fractal theory to reactor core layout

  Zou, Wenjun; Zhang, Qinshun; Shen, Xiuzhong; Li, Xiaoyan; Xu, Jijun

  Bulletin of science and technology, May 2001, Peer-reviewed

  
• Study on flow boiling heat transfer characteristics in narrow double-side heating annulus

  Shen, X.Z.; Miyaazaki, K.; Imura, S.; Xu, J.J.

  Hedongli Gongcheng/Nuclear Power Engineering, Apr. 2001, Peer-reviewed

  
• Modularization and simulation of condenser

  Zhang, Qinshun; Zou, Wenjun; Shen, Xiuzhong; Dai, Zhengxi; Wang, Xiaobing; Chen, Ke; Cai, Riji; Xu, Jijun

  Computer Engineering, Feb. 2001, Peer-reviewed

  
• A study on the well-posedness of one-dimensional heat transfer in steam generator

  Zhang, Qinshun; Shen, Xiuzhong; Deng, Baoqing

  Chinese Journal of Nuclear Science and Engineering, Jun. 2000, Peer-reviewed

  
• Narrow Space heat transfer in vertical narrow annulus with inner-side heating

  Shen, Xiuzhong; Imura, Satoshi; Miyazaki, Keiji; Xu, Jijin; Horiike, Hiroshi

  Proceedings of International Conference on Boiling 2000 Phenomena & Emerging Applications at Anchorage, Alaska; pp.427-446, Apr. 2000, Peer-reviewed

  
• Hydraulic analysis code of PWR upper plenum with flow fraction

  Shen, Xiuzhong; Yu, Pingan; Yang, Guanyue

  Chinese Journal of Nuclear Science and Engineering, Mar. 1998, Peer-reviewed

  
• Hydromechanical investigation on two upper plenum core structures

  Shen, X.; Yu, P.; Yang, G.

  Kung Cheng Je Wu Li Hsueh Pao/Journal of Engineering Thermophysics, Jan. 1998, Peer-reviewed

  
• Simulated experimental Investigation of the flow field near control rod guide bundles

  Yu, Pingan; Shen, Xiuzhong; Yang, Guanyue

  Nuclear Power Engineering, Jun. 1997, Peer-reviewed

  
• Investigation on the flow in PWR upper plenum after its core structure improvement

  Yu, Pingan; Shen, Xiuzhong; Yang, Guanyue

  Chinese Journal of Nuclear Science and Engineering, Jun. 1997, Peer-reviewed

  
• Hydromechanical investigation on different PWR upper plenum core structures

  Shen, Xiuzhong; Yu, Pingan; Yang, Guanyue

  Proceeding of the Fifth International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety (NUTHO-5), pp. C4-1-6, Beijing, China, Apr. 1997, Peer-reviewed

  
• The investigation on steady flow in PWR upper plenum

  Shen, Xiuzhong; Yu, Pingan; Yang, Guanyue

  Proceeding of 10th Pacific Basin Nuclear Conference, Vol. 1, pp. 425-430, Kobe, Japan, Oct. 1996, Peer-reviewed

  
• Influence of structure improvement of guide tubes and bundles in PWR on drop of control rods

  Shen, Xiuzhong; Yu, Pingan; Yang, Guanyue

  Journal of Shanghai Jiao-Tong University, Sep. 1996, Peer-reviewed

  
• The experimental study on steady flow in PWR upper plenum

  Xiuzhong Shen

  Chinese Journal of Nuclear Science and Engineering, Mar. 1996, Peer-reviewed

  
• Channel size effect on drift-flux parameters for adiabatic and boiling two-phase flows

  Hibiki, T.; Ju, P.; Rassame, S.; Miwa, S.; Shen, X.; Ozaki, T.

  International Journal of Heat and Mass Transfer, Apr. 2022, Peer-reviewed

  
• Thermal-hydraulic characteristics of upward two-phase flows in vertical large size square channels

  Hibiki, T.; Katono, K.; Shen, X.

  Nuclear Engineering and Design, Dec. 2021, Peer-reviewed, Last author

  
• Flow regime and void fraction predictions in vertical rod bundle flow channels

  Han, X.; Shen, X.; Yamamoto, T.; Nakajima, K.; Sun, H.; Hibiki, T.

  International Journal of Heat and Mass Transfer, Oct. 2021, Peer-reviewed, Corresponding author

  
• Two-phase interfacial structure development in vertical narrow rectangular channels

  Xiuzhong Shen; Takashi Hibiki

  International Journal of Heat and Mass Transfer, Aug. 2022, Peer-reviewed, Lead author, Corresponding author

  

Misc.

• Prediction of interfacial area transport in a coupled two-fluid model computation

  Joshua P. Schlegel; Takashi Hibiki; Xiuzhong Shen; Santosh Appathurai; Hariprasad Subramani

  Journal of Nuclear Science and Technology, 02 Jan. 2017, Peer-reviewed

  
• Experimental Study of Two Phase Flow in a Large Diameter Vertical Pipe Using Hot-Film Anemometer

  Matsui, Ryota; Mishima, Kaichiro; Shen, Xiuzhong; Nakamura, Hideo

  Korea-Japan Student Seminar on Nuclear Thermal Hydraulics and Safety Okinawa, Japan, Nov. 2008, Peer-reviewed

  

Books and Other Publications

• Flow Characteristics and Void Fraction Prediction in Large Diameter Pipes (Chapter 2 (pp. 55-103) at Forntiers and Progress in Multiphase Flow I (edited by L. Cheng))

  Shen, Xiuzhong; Schlegel, Joshua P; Chen, Shaowen; Rassame, Somboon; Griffiths, Matthew J; Hikiki, Takashi; Ishii, Mamoru, Joint work, Chapter 2

  Springer International Publishing Switzerland, Print ISBN 978-3-319-04357-9, Online ISBN 978-3-319-04358-6, Apr. 2014, Not refereed

  
• Nuclear Reactor Thermal Hydraulics(ISBN7-313-02868-7/TL.02)

  Yu, Pingan; Zhu, Ruian; Yu Zhenwan; Shen, Xiuzhong, Joint work, Chapter 5

  Shanghai Jiaotong University Press, Feb. 2002, Not refereed

  

Industrial Property Rights

• 特許第5916509号, 特願特願2012-111619, Measurement system for two-phase flow parameters(3D bubble velocity, bubble diameter and interfacial area concentration)

  Shen, Xiuzhong

  
• 特許4918639, 特願2004-365069, Measurement device, measurement method, measurement system, measurement program, and recording medium with measurement program recorded thereon

  Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

  
• 特許00116352.3, Automatic aerofluxus pressure reducing air sac for wreck removal

  Shen, Xiuzhong; Hong, Chong; Yang, Guanyue; Gu, Ruilin

  

Works

• 三次元気液二相流の界面運動と界面微細構造を解明出来る計測方法の開発

  From 2006

  
• 混相流の多次元微視的構造に関する研究

  From 01 Apr. 2001, To 31 Mar. 2003

  
• Study on Multi-dimensical Nictoscopic Structure of Multiphase Flow

  From 01 Apr. 2001, To 31 Mar. 2003

  

Awards

• 18 Feb. 2025

  2024年度日本機械学会関西支部賞 研究賞
• 23 Jun. 2007

  The Japanese Society for Multiphase Flow, The Incentive Award of The Japanese Society for Multiphase Flow
• 27 Mar. 2014

  Atomic Energy Society of Japan (AESJ), The 46th AESJ (Atomic Energy Society of Japan) Best Paper Award
• 01 Oct. 2014

  Japan Atomic Energy Agency, The Research and Development Achievement Award
• 08 Jun. 2018

  The Japanese Society for Multiphase Flow, The JSMF (The Japanese Society for Multiphase Flow) Best Paper Award (2017)
• 16 Mar. 2021

  Thermal-hydraulic Division of Atomic Energy Society of Japan, The 33rd Engineering Achievement Award of Thermal-hydraulic Division of Atomic Energy Society of Japan
• 18 Nov. 2000

  上海交通大学, 2000年度上海交通大学優秀学生指導教員

External funds: Kakenhi

• Study on flow characteristics and interfacial transport mechanism in gas-liquid two-phase flow between fuel plates in research reactor

  Grant-in-Aid for Scientific Research (C)

  Basic Section 31010:Nuclear engineering-related

  Kyoto University

  沈 秀中

  From 01 Apr. 2021, To 31 Mar. 2024, Granted

  試験研究炉;燃料板間流路;気液二相流;流動特性測定;ボイド率;界面積濃度;流動様式遷移;界面積濃度輸送方程式;界面輸送モデリング

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-21K04941/
• Study on the interfacial area transport and gas phase diffusion in gas-liquid two-phase flows in a rod bundle flow channel

  Grant-in-Aid for Scientific Research (C)

  Kyoto University

  Xiuzhong Shen

  From 01 Apr. 2017, To 31 Mar. 2020, Project Closed

  熱流動;ロッドバンドル流路;気液二相流;気相拡散;界面積濃度輸送方程式;気液二相流計測;データベース構築;国際研究者交流

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-17K07009/
• Study on flow characteristics and interfacial area transport machanism in low flow rate gas-liquid two-phase flows in a rod bundle flow channel

  Grant-in-Aid for Scientific Research (C)

  Kyoto University

  Xiuzhong Shen

  From 01 Apr. 2014, To 31 Mar. 2017, Project Closed

  燃料集合体内気液二相流;ボイド率;界面積濃度;ドリフトフラックスモデル;界面輸送モデル;気液二相流計測;データベース構築;国際研究者交流

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-26420870/
• A study on interfacial area transport in gas-liquid two-phase flow in mini-channels

  Grant-in-Aid for Scientific Research (C)

  Kyoto University

  Xiuzhong SHEN

  From 01 Apr. 2011, To 31 Mar. 2014, Project Closed

  ミニチャンネル内気液二相流;気泡流の画像処理計測法;界面積濃度;ボイド率;界面積濃度輸送方程式の開発;気泡合一と分裂のモデル化;フォーセンサープローブ;国際研究者交流;多センサープローブ;ミニチャネル内気液二相流;流体工学

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-23561011/
• A study on the bubble accumulation and coalescence phenomena in liquid and gas two-phase flow

  Grant-in-Aid for Scientific Research (C)

  Kyoto University

  Xiuzhong SHEN

  From 01 Apr. 2008, To 31 Mar. 2011, Project Closed

  熱流動・構造;気液二相流の流動現象;多次元気液二相流;流れ誘起の気泡成長;多センサープローブ;熱線流速計;界面輸送モデル;レイノルズ応力;乱流モデル;ドリフトフラックスモデル;流れ誘起の気泡集積

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-20560774/
• Fundamental structure of Pb-Bi Two-phase flow

  Grant-in-Aid for Scientific Research (B)

  Kyoto University

  Yasushi SAITO

  From 01 Apr. 2008, To 31 Mar. 2011, Project Closed

  溶融金属;混相流;中性子ラジオグラフィ;気液界面積;熱伝達;気液二相流;液体金属;界面積濃度;高速増殖炉;4センサープローブ;二流体モデル

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-20360418/
• 複雑な多次元気液二相流の相間相互作用と界面輸送構造に関する研究

  Grant-in-Aid for Young Scientists (B)

  Kyoto University

  沈 秀中

  From 01 Apr. 2006, To 31 Mar. 2008, Project Closed

  多次元気液二相流;界面輸送モデル;界面速度測定;界面方向測定;界面面積濃度測定;多センサー・プローブ;大口径管データベース;二流体モデル

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-18760653/
• Study on Direct Contact Heat Transfer from Water Droplets Dispersed in a Molten Metal Pool

  Grant-in-Aid for Scientific Research (C)

  Kyoto University

  Kaichiro MISHIMA

  From 01 Apr. 2005, To 31 Mar. 2008, Project Closed

  中性子ラジオグラフィ;沸騰伝熱;液液界面;液体金属;高速増殖炉;直接接触熱伝達;混相流;可視化;液体金属流れ;鉛ビスマス;熱交換器;自然循環;液滴蒸発;沸騰熱伝達, neutron radiography;boiling heat transfer;liquid-liquid interface;liquid metal;fast breeder reactor;direct contact heat transfer;multiphase flow;visulalization

  https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-17560751/

External funds: others

• Development of interfacial movement and structure measurement method for 3D twophase flows

  関西エネルギー・リサイクル科学研究振興財団第１４回研究助成、若手奨励研究

  From 01 Apr. 2006, To 31 Mar. 2007

  沈秀中
• A study on interfacial transport mechanism of multi-dimensional two-phase flow

  京都大学若手研究者スタートアップ研究費

  From 01 Apr. 2005, To 31 Mar. 2006

  沈秀中
• The behavior elucidation of the materials for FFAG accelerator driven subcritical reactor

  独立行政法人科学技術振興機構、原子力システム研究開発事業、原子力基礎基盤戦略研究イニシアティブ

  From 01 Apr. 2010, To 31 Mar. 2013

  義家敏正
• The utilization enhancement of Kyoto University Research Reactor and its hot laboratory

  独立行政法人科学技術振興機構、原子力システム研究開発事業、原子力基礎基盤戦略研究イニシアティブ

  From 01 Apr. 2008, To 31 Mar. 2011

  川端祐司
• Interfacial area transport equation development for multi-dimensional two-phase flow

  関西原子力懇談会学術振興研究助成金

  From 01 Apr. 2013, To 31 Mar. 2016

  沈秀中
• 複雑な気液二相流の計測手法開発とデータベース構築

  関西原子力懇談会学術振興研究助成金

  From 01 Apr. 2017, To 31 Mar. 2020

  沈秀中
• 試験研究炉燃料要素内気液二相流挙動に関する研究

  関西原子力懇談会学術振興研究助成金

  From 01 Apr. 2021, To 31 Mar. 2024

  沈秀中

Education

Teaching subject(s)

• From 01 Apr. 2019, To 30 Sep. 2019

  原子核工学特別セミナーA

  Spring, 工学研究科
• From 01 Oct. 2019, To 31 Mar. 2020

  原子核工学特別セミナーB

  Fall, 工学研究科
• From 01 Apr. 2020, To 30 Sep. 2020

  原子核工学特別セミナーC

  Spring, 工学研究科
• From 01 Oct. 2020, To 31 Mar. 2021

  原子核工学特別セミナーD

  Fall, 工学研究科
• From 01 Apr. 2021, To 30 Sep. 2021

  原子核工学特別セミナーE

  Spring, 工学研究科

Student achievements: Awards

• 第20回原子力工学国際会議学生論文賞（ICONE20 Student Best Paper Award）

  Sun, Haomin, ICONE20-POWER2012 STEERING COMMITTEE, 30 Jul. 2012
• Then Best Paper—Asia/Japan Award of NUCLEAR2020-ICONE Conference

  Han, Xu, The Organizers of ASME's Nuclear Engineering Conference powered by ICONE, 04 Aug. 2020

Administration

Faculty management (title, position)

• From 01 Apr. 2023, To 31 Mar. 2024

  出版チーム員
• From 01 Apr. 2015, To 31 Mar. 2016

  所員会議委員