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Hideo Mori Last modified date:2018.02.22



Graduate School
Undergraduate School


E-Mail
Homepage
http://therme.mech.kyushu-u.ac.jp/index-j.html
Phone
092-802-3121
Fax
092-802-3125
Academic Degree
Doctor of Engineering
Field of Specialization
Thermal Engineering
Outline Activities
[Research]
Thermal-Hydraulics in Supercritical Pressure Water Cooled Power Reactor
Boiling and Condensation Heat Transfer for Refrigerants Flowing in Tubes
Heat Transfer to Supercritical Pressure Fluids
Cooling Heat Transfer from Supercritical Pressure Fluids in Plate-type Heat Exchangers
Heat and Mass Transfer in Packed Beds Accompanied by Exthothermic or Endothermic Reaction
[Education]
Two-phase Flow Phenomena, Thermal Engineering
Heat Transfer, Thermal Energy Conversion
Research
Research Interests
  • Forced Convection Heat Transfer of Supercritical Pressure Fluids
    keyword : Heat transfer, Supercritical pressure fluid
    2001.04Heat Transfer to Supercritical Pressure Fluids.
  • Thermal-hydraulics in Supercritical Pressure Water Cooled Power Reactor
    keyword : Supercritical Pressure Fluid, Heat Transfer, Tube Flow, Bundle Flow, Steady State, Transient Process
    2003.04~2014.03Thermal-Hydraulics in Supercritical Pressure Water Cooled Power Reactor.
  • Critical Heat Flux in the Near-critical Pressure Region
    keyword : Critical Heat Flux, Near-critical Pressure
    2007.01Characterisitics of Critical Heat Flux in the Near-Crotical Region.
  • Boiling and Condensation Heat Transfer for Refrigerants Flowing in Small Channels
    keyword : New Refrigerant, Heat Transfer Enhancement, Parallel Small channels, High Performance Heat Exchanger
    2004.04Boiling and Condensation Heat Transfer for Refrigerants Flowing in Small Channels.
  • Liquid-vapor Two-phase Flow Heat Transfer in Micro-scale Porous Material
    keyword : Liquid-vapor Two-phase, Flow Heat Transfer, Micro Porous Material
    2004.04~2010.03Vapor-liquid Two-phase Flow in Micro-scale Porous media.
Current and Past Project
  • Development of Light Water Cooled Super Fast Reactor
  • Research Project of Thermalhydraulics and Safety for the International Research and Development of the Supercritical Water-Cooled Reactor
    Nuclear Energy System
  • Development of Light Water Cooled Super Fast Reactor
  • Development of Supercritical Pressure Water Cooled Reactor
  • Characteristics of Heat Transfer of Fluoroether fluids
Academic Activities
Books
1. Yoshiaki Oka, 森 英夫, Supercritical-Pressure Light Water Cooled Reactors, Springer, 2014.09.
Papers
1. Condensation Heat Transfer of a Refrigerant at Near-critical Pressures in a Chevron-type Plate Heat Exchanger
Kazushi MIYATA, Shuntaro YANAGIHARA, Takahiro TANIGUCHI, Hideo MORI, Yoshinori HAMAMOTO, Shuichi UMEZAWA, Katsuhiko SUGITA
Jounal of JSRAE, Vol.34, No.4, pp.443-452.
2. A Simulation for the Flow Distribution and Unsteady Behavior of Flow Boiling in Parallel Mini-Channels
Takuya KAWASUSO, Kizuku KUROSE, Kazushi MIYATA, Yoshinori HAMAMOTO, Hideo MORI
Jounal of JSRAE, Vol.34, No.4, pp.463-471.
3. Effects of Oscillation on Vapor-liquid Two-phase Flow Patterns in Small Horizontal Rectangular Tube
Masaharu OHNO, Kunihiro NAGAYAMA, Koji ENOKI, Atsushi AKISAWA, Tomio OKAWA, Hideo MORI
Jounal of JSRAE, Vol.34, No.4, pp.335-344.
4. Cooling Heat Transfer of Supercritical Pressure HFO1234ze(E) in a Plate Heat Exchanger
Kazushi MIYATA, Hideo MORI, Takahiro TANIGUCHI, Shuichi UMEZAWA, Katsuhiko SUGITA
Bulletin of the JSME, Vol.83, No.855, p.17-00280.
5. Takahiro Taniguchi, Fuka Ono, Tomoyuki Tanzan, Hideo Mori, Kazushi Miyata, Shuichi Umezawa, Effect of the Chevron Angle on Cooling Heat Transfer Characteristics of a Supercritical Pressure Fluid in Plate Heat Exchangers, Proceedings of the Innovative Materials for Processes in Energy Systems 2016, 2016.10, For the development of industrial heat pump systems supplying a high-temperature heat source over 130 °C, cooling heat transfer characteristics of a supercritical pressure fluid flowing in a chevron type plate heat exchanger (PHE) were experimentally examined. Previously, experiments were made for the PHE of the chevron angle 65°. In the present, experiments were conducted for the 30° chevron angle PHE with the same cross-sectional corrugated configuration. HFC134a was used as the test fluid. The results were compared with the previous 65° angle PHE results. In addition, observation of water flow was carried out in two chevron PHE model channels of 30° and 65° angles. Based on these results, the effect of the chevron angle on the cooling heat transfer characteristics of the supercritical pressure fluid was clarified..
6. Shuro Tanaka, Kento Hirata, Kazushi Miyata, Hideo Mori, Yoshinori Hamamoto, Boiling Heat Transfer and Pressure Drop of a Refrigerant HFO1234yf Flowing in a Small Horizontal Tube, Proceedings of the Innovative Materials for Processes in Energy Systems 2016, 2016.10, For the development of a high-performance heat exchanger using small or mini-channels for air-conditioning systems, boiling heat transfer and pressure drop of HFO1234yf flowing in a horizontal copper circular tube with 1.0 mm inside diameter were experimentally investigated. Local heat transfer coefficients were measured in a range of mass fluxes from 30 to 400 kg/(m2·s), qualities from 0.05 to 0.9 and heat fluxes from 2 to 24 kW/m2 at the saturation temperature of 10 ºC. Pressure drops were also measured from 30 to 400 kg/(m2·s) and qualities from 0.05 to 0.9 at the saturation temperature of 10 ºC under the adiabatic condition.The characteristics were clarified and the comparison was made with data of R410A and R32..
7. Kazushi Miyata, Kento Hirata, Takuya Nakatsuru, Hideo Mori, Yoshinori Hamamoto, Flow Boiling Heat Transfer and Vapor-Liquid Two-Phase Pressure Drop of a Refrigerant in Horizontal Triangular Mini-Channels, Proceedings of the First Pacific Rim Thermal Engineering Conference, 2016.03, For the development of industrial heat pump systems supplying a high-temperature heat source over 130 °C, cooling heat transfer characteristics of a supercritical pressure fluid flowing in a chevron type plate heat exchanger (PHE) were experimentally examined. Previously, experiments were made for the PHE of the chevron angle 65°. In the present, experiments were conducted for the 30° chevron angle PHE with the same cross-sectional corrugated configuration. HFC134a was used as the test fluid. The results were compared with the previous 65° angle PHE results. In addition, observation of water flow was carried out in two chevron PHE model channels of 30° and 65° angles. Based on these results, the effect of the chevron angle on the cooling heat transfer characteristics of the supercritical pressure fluid was clarified..
8. Hideo Mori, Two-Phase Flow and Boiling Heat Transfer in Small-Diameter Tubes, Heat Transfer Engineering, 10.1080/01457632.2015.1067073, 37, 7-8, 686-695, 2016.03, For the development of a high-performance heat exchanger using small channels or minichannels for air-conditioning systems, it is necessary to clarify the characteristics of vapor‐liquid two-phase flow and heat transfer of refrigerants in small-diameter tubes. In this keynote paper, the related research works that have already been performed by the author and coworkers are introduced. Based on the observations and experiments of R410A flowing in small-diameter circular and noncircular tubes with hydraulic diameter of about 1 mm, the characteristics of vapor‐liquid two-phase flow pattern and boiling heat transfer were clarified. In low quality or mass flux and low heat flux condition, in which the flow was mainly slug, the “liquid film conduction evaporation” heat transfer peculiar to small-diameter tubes prevailed and exhibited considerably good heat transfer compared to nucleate boiling and forced convection evaporation heat transfer. The effects of the tube cross-sectional shape and flow direction on the heat transfer primarily appeared in the region of the “liquid film conduction evaporation” heat transfer. A new heat transfer correlation considering all of three contributions has been developed for small circular tubes..
9. Yudai Matsuse, Koji Enoki, Hideo Mori, Keishi Kariya, Yoshinori Hamamoto, Boiling Heat Transfer and Pressure Drop of a Refrigerant R32 Flowing in a Small Horizontal Tube, Heat Transfer Engineering, 10.1080/01457632.2015.1067057, 37, 7-8, 668-678, 2016.03, In this study, experiments were performed to examine characteristics of flow boiling heat transfer and pressure drop of a low global warming potential refrigerant R32 flowing in a horizontal copper circular tube with 1.0 mm inside diameter for the development of a high-performance heat exchanger using small-diameter tubes or minichannels for air conditioning systems. Axially local heat transfer coefficients were measured in the range of mass fluxes from 30 to 400 kg/(m2·s), qualities from 0.05 to 1.0, and heat fluxes from 2 to 24 kW/m2 at the saturation temperature of 10°C. Pressure drops were also measured in the rage of mass fluxes from 30 to 400 kg/(m2·s) and qualities from 0.05 to 0.9 at the saturation temperature of 10°C under adiabatic condition. In addition, two-phase flow patterns were observed through a sight glass fixed at the tube exit with a digital camera. The characteristics of boiling heat transfer and pressure drop were clarified based on the measurements and the comparison with data of R410A obtained previously. Also, measured heat transfer coefficients were compared with two existing correlations..
10. Hideo Mori, Shin Nakamura, Fuka Ono, Keishi Kariya, Shuichi Umezawa, A Study on Characteristics of Cooling Heat Transfer of Supercritical Pressure Fluids in a Plate Heat Exchanger, Heat Transfer Engineering, 10.1080/01457632.2015.1067054, 37, 7-8, 659-667, 2016.03, For the development of industrial heat pump systems supplying a high-temperature heat source over 130°C, experiments were carried out on cooling heat transfer of supercritical pressure fluids flowing in a plate heat exchanger (PHE). Using two refrigerants of HFC134a and HCFC22 as the test fluids, heat transfer coefficient data were obtained at different pressure, flow rate, and heat load conditions. The heat transfer coefficient generally had a maximum in the vicinity of the pseudocritical point and showed seven- to ninefold values compared with tube flow. Based on the measurements, characteristics of cooling heat transfer of supercritical pressure fluids in the PHE were clarified and a correlation of heat transfer coefficient was developed..
11. Takashi Mawatari, Hideo Mori, An Experimental Study on Characteristics of Post-CHF Heat Transfer in the High Subcritical Pressure Region near to the Critical Pressure, Journal of Thermal Science and Technology, 10.1299/jtst.2016jtst0006, 11, 1, 1-14, 2016.02, Supercritical pressurized water cooled reactor (SCWR), which has a once-through water cooled reactor for supplying supercritical pressure steam at high temperature to a turbine system, is one of the next generation reactors for the purpose of improving economic efficiency and safety. In the SCWR system, water pressure passes through the critical pressure during startup, shutdown and in case of loss of coolant accident (LOCA). Similarly, in fossil-fired power plants, once-through boilers of sliding pressure type operate at supercritical pressure during nominal load, but they work near the critical pressure during partial load. In the high subcritical pressure region slightly below the critical pressure, critical heat flux (CHF) phenomenon readily occurs at relatively low heat flux and in a high subcooled region, and then it causes serious damages to fuel rods or boiler tubes due to the abrupt temperature rise in the rod or tube. In this study, experiments on post-CHF heat transfer in such the high subcritical pressure region near the critical pressure (reduced pressure range of 0.924 up to 0.992) in the range of mass flux 400-1000 kg/(m2·s) with a circular tube of 4.4 mm ID in vertical upward flow. HCFC22 and HFC134a were used as the test fluids. Based on the obtained data, characteristics of the post-CHF heat transfer were examined and found to be classified into two distinctive types mainly according to flow rate conditions. The influences of pressure, flow rate and heat flux on the characteristics were also clarified..
12. Modification of the Prediction Correlation for Flow Boiling Heat Transfer in Small Diameter Tubes
Koji ENOKI, Kazushi MIYATA, Hideo MORI
Jounal of JSRAE, Vol.32, No.3, pp.275-283.
13. Flow Boiling Heat Transfer and Liquid-vapor Two-phase Pressure Drop of a Refrigerant in a Horizontal Triangular Mini-channel
Kazushi MIYATA, Takuya NAKATSURU, Kento HIRATA, Hideo MORI, Yoshinori HAMAMOTO
Jounal of JSRAE, Vol.32, No.2, pp.163-174.
14. Study on Performance Improvement of Defrosting for Refrigerator Considering Characteristics of Refrigerant Flow and Heat Transfer inside Evaporator Tube
-4th Report: Evaluation During Defrosting Process using a Two-Row Fin-Tube Model
Katsunori HORII, Keishi KARIYA, Yuki NAKASHIMA, Syunsuke MATSUMOTO, Hideo MORI
Jounal of JSRAE, Vol.31, No.3, pp.277-288.
15. Study on Performance Improvement of Defrosting for Refrigerator Considering Characteristics of Refrigerant Flow and Heat Transfer inside Evaporator Tube
-3rd Report: Evaluation of Refrigerant Flow Characteristics using a Single-Row Staggered Arrangement Model, and Various Two-Row Models
Katsunori HORII, Keishi KARIYA, Yuki NAKASHIMA, Syunsuke MATSUMOTO, Hideo MORI
Jounal of JSRAE, Vol.31, No.3, pp.265-276.
16. Flow patterns of the vapor-liquid two-phase flow in a small triangular channel
Yudai MATSUSE, Takuya NAKATSURU. Koji ENOKI, Hideo MORI, Keishi KARIYA, Yoshinori HAMAMOTO
Jounal of JSRAE, Vol.31, No.1, pp.39-45.
17. Adsorption Equilibrium and Desorption Rate of Adsorbent Coated on Heat Transfer Plate
Takafumi OUCHI, Shou TAKATA, Yoshinori HAMAMOTO, Hideo MORI, Atsuroh ETOH
Trans of JSME, Vol.79, No.808, pp.2602-2606.
18. Measurement of Thermal Resistance of an Adsorbent Coated on Heat Transfer Plate and Comparison of the Resistance with an Adosrbent Pariticle Packed Bed
Takafumi OUCHI, Yoshinori HAMAMOTO, Hideo MORI, Atsuroh ETOH
Jounal of JSRAE, Vol.30, No.4, pp.439-449.
19. Pressure Drop of the Vapor-liquid Two-phase Flow in Small Tubes
-2nd Report: Evaluation during Defrosting Process using Single-Row Model-
Koji ENOKI, Hideo MORI, Kazushi MIYATA, Keishi KARIYA, Yoshinori HAMAMOTO
Jounal of JSRAE, Vol.30, No.4, pp.425-437.
20. Study on Performance Improvement of Defrosting for Refrigerator Considering Characteristics of Refrigerant Flow and Heat Transfer inside Evaporator Tube
-2nd Report: Evaluation during Defrosting Process using Single-Row Model-
Katsunori HORII, Keishi KARIYA, Yusuke MIYAZAKI, Yuki NAKASHIMA, Hideo MORI
Jounal of JSRAE, Vol.30, No.4, pp.377-387.
21. Study on Performance Improvement of Defrosting for Refrigerator Considering Characteristics of Refrigerant Flow and Heat Transfer inside Evaporator Tube
-1st Report: Evaluation of Refrigerant Flow Characteristics using Single-Row Model-
Katsunori HORII, Keishi KARIYA, Yusuke MIYAZAKI, Hideo MORI
Jounal of JSRAE, Vol.30, No.4, pp.365-375.
22. Hideo Mori, Two-phase Flow and Boiling Heat Transfer in Small Diameter Tubes, Proceedings of the Innovative Materials for Processes in Energy Systems 2013, K-52-K-60, 2013.09, For the development of a high-performance heat exchanger using small or mini-channels for air-conditioning systems, it is necessary to clarify the characteristics of vapor-liquid two-phase flow and heat transfer of refrigerants in small diameter tubes. In the present keynote paper, the research works which have already been performed by the author and coworkers are introduced. Based on the observations and experiments of R410A flowing in small diameter circular and noncircular tubes with hydraulic diameter of about 1 mm, the characteristics of vapor-liquid two-phase flow pattern and boiling heat transfer were clarified. In low quality or mass flux and low heat flux condition, in which the flow was mainly slug, the ‘liquid film conduction evaporation’ heat transfer peculiar to small diameter tubes prevailed and exhibited considerably good heat transfer compared to nucleate boiling and forced convection evaporation heat transfer. The effects of the tube cross-sectional shape and flow direction on the heat transfer primarily appeared in the region of the ‘liquid film conduction evaporation’ heat transfer. A new heat transfer correlation considering all of three contributions has been developed for small circular tubes..
23. Yudai MATSUSE, Koji ENOKI, Hideo Mori, Keishi KARIYA, Yoshinori Hamamoto, Boiling Heat Transfer and Pressure Drop of a Refrigerant R32 Flowing in a Small Horizontal Tube
, Proceedings of the Innovative Materials for Processes in Energy Systems 2013, 141-146, 2013.09, In the present study, experiments were performed to examine the characteristics of flow boiling heat transfer and pressure drop of a refrigerant R32 flowing in a horizontal copper circular tube with 1.0 mm inside diameter for the development of a high performance heat exchanger using small diameter tubes or mini-channel for air conditioning systems. Local heat transfer coefficients were measured in a range of mass fluxes from 30 to 400 kg/(m2•s), qualities from 0.05 to 0.9 and heat fluxes from 2 to 24 kW/m2 at the saturation temperature of 10 ºC. Pressure drops were also measured from 30 to 400 kg/(m2•s) and qualities from 0.05 to 0.9 at the saturation temperature of 10 ºC under the adiabatic condition. In addition, two-phase flow patterns were observed with a sight glass fixed at the test tube exit end using a digital camera. Their characteristics of boiling heat transfer and pressure drop of R32 were clarified based on the measurements and the comparison with data of R410A which obtained previously..
24. Flow Patterns of the Vapor-liquid Two-phase Flow in Small Tubes,
Koji ENOKI, Hideo MORI, Kazushi MIYATA, Yoshinori HAMAMOTO,
Jounal of JSRAE, Vol.30, No.2, pp.155-167.
25. Koji Enoki, Kazushi Miyta, Hideo Mori, KEISHI KARIYA, Yoshinori Hamamoto, Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing Vertically Upward in Small Rectangular and Triangular Tubes, Heat Transfer Engineering, 34, 11-12, 966-975, 2013.03, In the present study, experiments were performed to examine the characteristics of flow boiling heat transfer and pressure drop of a refrigerant R410A flowing vertically upward in small copper rectangular and triangular tubes with hydraulic diameters of 1.04 and 0.88 mm, respectively, for the development of a high-performance heat exchanger using small tubes or minichannels for air-conditioning systems. Their characteristics were clarified by comparing the previous experimental data of the small circular tube (1.00 mm internal diameter). In the rectangular and triangular tubes, the pressure drop was found to be slightly lower and the heat transfer was much better than in the circular tube..
26. Kazuyuki Takase, Takeharu Misawa, Hiroyuki Yoshida, Hideo Mori, Numerical Predictions of Crossing-Flow Characteristics of a Supercruitical Fluid in Parallel Circular Ducts with Narrow Rectanngular Channel at Isothermal Condition , Proceedings of the 6th International Symposium on Supercritical-Water-Cooled Reactors, ISSCWR6-13032, 2013.03, Numerical analyses of crossing flows between two parallel circular channels were conducted for a specific geometry that modeled subchannels in a fuel bundle of a supercritical water reactor. The two parallel circular channels were connected by a rectangular channel in the axial direction. Crossing flow occurred in the rectangular channel and was caused by differences in temperatures of fluids flowing in the two channels. The working fluid was supercritical freon. The SST turbulence model was chosen for precisely calculating the boundary layers of temperature and velocity near the channel walls. From the analytical results, relations between crossing flow and fluid temperature were clarified quantitatively. .
27. KEISHI KARIYA, Ken Yoshizumi, Hideo Mori, Takashi Mawatari, Yoshinori Hamamoto, Correlation for Critical Heat Flux at Near-critical Pressure in Tubes, Proceedings of the 6th International Symposium on Supercritical-Water-Cooled Reactors, ISSCWR6-028, 2013.03, The supercritical water cooled reactor (SCWR), which is a once-through water cooled reactor supplying supercritical pressure steam at high temperature to the turbine system, has an innovative and economical potential. During startup process and shutdown procedure of the SCWR, the pressure of water passes through the critical pressure condition. In the region of the pressure slightly below the critical pressure, critical heat flux condition leading to the rapid rise of fuel rod surface temperature caused by development of film boiling tends to occur at relatively low heat flux and high subcooling. In the present study, the critical heat flux at near-critical pressure is measured for vertically upward flow in a circular-tube of 4.4 mm I.D., in order to clarify the critical heat flux condition in the near-critical pressure region. HFC134a and HCFC22 are used as the test fluid. These fluids are easy for handing due to its low critical pressure and temperature, and therefore the experimental conditions can be set easily to make systematic data. As a result, four kinds of characteristics of CHF condition in near critical pressure are found. Based on their characteristics, the correlations of the critical heat flux in tubes are successfully developed with good accuracy including high-subcooled conditions..
28. Y. Oka, S. Morooka, M. Yamakawa, Y. Ishiwatari, Y. Katsumura, Hideo Mori, Yoshinori Hamamoto, T. Kugo, K. Takase, K. Ezato, T. Misawa, Y. Watanabe, H. Abe, K. Sue, Progress of Super Fast Reactor Phase 2 Project and Studies of Waseda University, Proceedings of the 6th International Symposium on Supercritical-Water-Cooled Reactors, ISSCWR6-13035, 2013.03, The concept of Super FR of 1000MWe and 500C outlet coolant temperature is being developed by core design and safety analysis. Improved coolant flow scheme in the RPV was adopted in the design for simplifying upper core structure. The fundamental thermal-hydraulic data are being taken by the experiments at Kyusyu University with the surrogate fluid and at JAEA Naka laboratory with supercritical water. Cross flow between sub-channels are measured at Kyushu University. The cross flow behaviors are analyzed with CFD code at JAEA Tokai. The experimental data of heat transfer coefficient of supercritical water at high temperature is being taken with single tube at JAEA Naka laboratory for accurate prediction of maximum cladding surface temperature by validating the results of the surrogate fluid. The material-coolant interaction and corrosion product transport are being studied at University of Tokyo. High temperature corrosion experiment is conducted at Tohoku University. Fuel cladding tube material of zirconium added austenitic stainless steel that was developed in the 1st phase project has good resistance against oxidation corrosion. The data base for the water chemistry was developed at AIST for understanding of corrosion product transport behavior. The results of heat transfer and materials constitute common data base for the Super FR and Super LWR design and analysis. Super LWR and Super FR design studies are carried out at Waseda University. Super LWR core with double tube water rods is developed for simplifying the upper core structure. Time dependent start-up analysis of Super FR is carried out. The accuracy of nuclear calculation by the SRAC code system is examined in comparison with Monte Carlo calculation. Pin-wise preparation of the blanket fuel assemblies with zirconium hydride layer overestimates plutonium accumulation and breeding. The results are presented at
ISSCWR6 separately. Plutonium breeding by light water cooling is being studied..
29. Hideo Mori, Takenobu Kaida, 大野 正規, Suguru Yoshida, Yoshinori Hamamoto, Heat Transfer to a Supercritical Pressure Fluid Flowing in Sub-bundle Channels, Journal of Nuclear Science and Technology, 49, 4, 373-383, Vol.49, Issue 4, pp.373-383, 2012.04, Supercritical pressure water cooled reactor (SCWR) has been regarded as an innovative nuclear reactor. For the design and development of the SCWR, heat transfer performance under supercritical pressure is one of the most important indicators. In this paper, experimental data are presented on the heat transfer to a supercritical pressure fluid flowing vertically upward and downward in a small diameter heated tube and two sub-bundle channels with three heater rods and seven heater rods, using HCFC22 as the test fluid. Downstream of grid spacer for the sub-bundles, heat transfer enhancement was observed in the upward flow, but not in the downward flow. The enhancement was remarkable especially when the heat transfer deterioration occurs in the fully developed region unaffected by the spacer. The heat transfer correlation for the downstream region of the spacer was developed in the normal heat transfer of subbundles. In the fully developed region for the sub-bundle, occurrence of the heat transfer deterioration was suppressed or degree of the deterioration was moderated. At high mass velocity for downward flow in the seven rod sub-bundle, oscillation of heat transfer was observed in the region of the enthalpy over the pseudocritical point..
30. K. Miyata, H. Mori, Y. Hamamoto , Correlation for the Flow Boiling Heat Transfer in Small Diameter Tubes, Proceedings of the 23rd IIR International Congress of Refrigeration, Paper No.800, 2011.08.
31. Correlation for the Prediction of Flow Boiling Heat Transfer in Small Diameter Tubes,
Kazushi MIYATA, Hideo, MORI, Yoshinori HAMAMOTO,
Jounal of JSRAE, Vol.28, No.2, pp.137-148.
32. T. Kaida, H. Mori, K. Kariya, M. Ohno, Y. hamamoto, Heat Transfer to Supercritical Pressure Fluids Flowing in Tubes in Superheated Vapor Region, Proceedings of the 5th International Symposium on Supercritical-Water-Cooled Reactors, P018, 2011.03.
33. T. Nakatsuka, H. Mori, M. Akiba, K. Ezato, M. Yasuoka, Outline of Research and Development of Thermal-hydraulics and Safety of Japanese Supercritical Water Cooled Reactor (JSCWR) Project, Proceedings of the 5th International Symposium on Supercritical-Water-Cooled Reactors, P072, 2011.03.
34. Y. Oka, S. Morooka, M. Yamakawa, Y. Ishiwatari, S. Ikejiri, Y. Katsumura, Y. Muroya, T. Terai, K. Sasaki, H. Mori, Y. Hamamoto, K. Okumura, T. Kugo, T. Nakatsuka, K. Ezato, N. Akasaka, A. Hotta, Research and Development of Super Light Water Reactors and Super Fast Reactors in JAPAN, Proceedings of the 5th International Symposium on Supercritical-Water-Cooled Reactors, Keynote 002, 2011.03, 超臨界圧水冷却炉であるスーパー軽水炉およびスーパー高速炉は,システムの簡素化,発電効率の向上,経済性また安全性の向上を目的とした次世代型の発電用原子炉であり,日本で発案され,研究開発が日本において世界をリードして活発に進められている.本論文では,これまで得られた原子炉の概念設計,炉心熱流動および材料開発に関する研究成果について,報告されている..
35. K. Enoki, K. Miyata, H. Mori, K. Kariya, Y. Hamamoto , Boiling Heat Transfer and Pressure Drop of A Refrigerant Flowing Vertically Upward in Small Rectangular and Triangular Tubes, Innovative Materials for Processes in Energy Systems, pp447-454, 2010.11.
36. Y. Hamamoto, K. Kariya, H. Mori, A. Etoh, T. Mitani, Estimation of Effective Thermal Conductivity of Metal Hydride Packed Bed Considerring Expansion/Contraction during Adsorption/Desorption Process, Innovative Materials for Processes in Energy Systems, pp440-446, 2010.11.
37. Y.Y. Bae, L.K.H. Leung, J.A.Lycklama, A. Nijeholt, M. Andreani, T. Schulenberg, J. Starflinger, Y. Ishiwatrari, Y. Oka, H. Mori, K. Ezato, Status of Ongoing Research on SCWR Thermal-hydraulics and Safety, Proceedings of GIF Symposium, pp149-161, 2009.09.
38. Biling Heat Transfer of a Refrigerant Flowing Vertically Downward in a Mini-Channel,
Kazushi MIYATA, Koji ENOKI, Hideo MORI, Yoshinori HAMAMOTO,
Jounal of JSRAE, Vol.26, No.3, pp.347-357.
39. Two-phase Pressure Drop of a Refrigerant Flowing Vertically Downward in a Mini-Channel,
Kazushi MIYATA, Koji ENOKI, Hideo MORI, Yoshinori HAMAMOTO,
Jounal of JSRAE, Vol.26, No.3, pp.335-346.
40. Measurement of Emissivity of Water Vapor Adsorbents with Infrared Radiation Thermometer,
Yoshinori HAMAMOTO, Hideo MORI, Takafumi AKAI, Tadafumi MITANI,
Jounal of JSRAE, Vol.26, No.3, pp.295-304.
41. K. Ezato, Y. Seki, M. Dairaku, S. Suzuki, M. Enoeda, M. Akiba, H. Mori, H. Oka, Heat Transfer in a Seven-rod Test Bundle with Supercritical Pressure Water (1) Experiments, Proceedings of the 2009 Int. Congress on Advances in Nuclear Power Plants, Paper No. 9464, 2009.05.
42. Hideo MORI, Yoshinori HAMAMOTO, Masaki OHNO, Experimental Study for Research and Development of a Super Fast Reactor (2) Oscillatory Condensation of High Temperature Vapor Directly Discharged into Sub-cooled liquid Pool, Proceedings of the 2009 Int. Congress on Advances in Nuclear Power Plants, Paper No. 9369, 2009.05.
43. Hideo MORI, Masaki OHNO, Yoshinori HAMAMOTO, Experimental Study for Research and Development of a Super Fast Reactor (1) Critical Heat Flux in the Near-critical Pressure Region, Proceedings of the 2009 Int. Congress on Advances in Nuclear Power Plants, Paper No. 9368, 2009.05.
44. K. Ezato, M. Akiba, M. Enoeda, S. Suzuki, Y. Seki, H. Tanigawa, D. Tsuru, H. Mori, Y. Oka, Research and Development of a Super Fast Reactor (8) Heat Transfer Experiments around A Simulated Fuel Rod with Supercritical Pressure Water, Proceedings of the 16th Pacific Basin Nuclear Conference, Paper P16P1240, 2008.10.
45. Hideo Mori, Masaki Ohno, Katsumi Ohishi, Yoshinori HAMAMOTO, Research and Development of a Super Fast Reactor (7) Heat Transfer to a Supercritical Pressure Fluid Flowing in a Sub-bundle Channel, Proceedings of the 16th Pacific Basin Nuclear Conference, Paper P16P1297, 2008.10.
46. Yoshinori HAMAMOTO, Hideo MORI and Fumio MATSUOKA, Numerical Simulation of a Dehumidification/Humidification Performance of a Descicant Rotor Using Pore Size Controlled Material Regenerated by Low Grade Thermal Energy, Proceedings of the 12th International Refrigerant and Air Conditioning Conference At Purdue, Paper No. 2391, 2008.07.
47. Kazushi MIYATA, Hideo MORI, Katsumi OHISHI and Yoshinori HAMAMOTO, Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing in a Vertical Small Diameter Tube, Proceedings of the 12th International Refrigerant and Air Conditioning Conference At Purdue, Paper No. 2421, 2008.07.
48. Overall Heat and Mass Transfer Coefficient of Water Vapor Adsorption -2nd Report: Transfer Coefficient for Adsorbent Rotor Blocks-,
Yoshinori HAMAMOTO, Hideo MORI, Masazumi GODO, Kunio MIURA, Yutaka WATANABE, Toshihiko ISHIZAWA, Takeshi TAKATSUKA,
Jounal of JSRAE, Vol.24, No.4, pp.473-484.
49. Overall Heat and Mass Transfer Coefficient of Water Vapor Adsorption -1st Report: Transfer Coefficient for Adsorbent Packed Beds-,
Yoshinori HAMAMOTO, Hideo MORI, Masazumi GODO, Kunio MIURA, Yutaka WATANABE, Toshihiko ISHIZAWA, Takeshi TAKATSUKA,
Jounal of JSRAE, Vol.24, No.4, pp.459-472.
50. Boiling Heat Transfer and Pressure Drop of a Refrierant Flowing Vertically Downward in a Small Diameter Tube,
Kazushi MIYATA, Hideo MORI, Katsumi OHISHI, Yoshinori HAMAMOTO,
Jounal of JSRAE, Vol.24, No.4, pp.371-380.
51. Boiling Heat Transfer and Pressure Drop of a Refrierant Flowing Vertically Upward in a Small Diameter Tube,
Kazushi MIYATA, Hideo MORI, Katsumi OHISHI, Yoshinori HAMAMOTO,
Jounal of JSRAE, Vol.24, No.4, pp.359-369.
52. Yoshinori HAMAMOTO, Hideo MORI, Atsuro ETOH, Takaharu YAMASAKI, Mikiya TAOMOTO and Ken-ich YANAGI, Measurement of Effective Thermal Conductivity of an Insulation Concrete Slab, Proceedings of the Asian Thermophysical Properties Conference, Paper No. 013, 2007.08.
53. Yoshinori HAMAMOTO, Hideo MORI and Fumio MATSUOKA, Performance Estimation of a Rotary Dehumidifier with the Influence of Design and Operation Parameter, Proceedings of the 22nd International Congress of Refrigeration, ICR07-B1-1189, 2007.08.
54. S. MOMOKI, S. HIGASHIIUE, T. SHIGECHI, T. YAMAGUCHI, H. MORI, Flow Pattern Identification With Both Wall Temperature Distributions and Heat Transfer Characteristics During Refrigerant Evaporation in Spirally Grooved Tube, Annals of the Assembly for International Heat Transfer Conference 13, Paper MBH-32, 2006.12.
55. Prediction of Evaporation Heat Transfer Coefficient of Refrierants Inside a Horizontal Spirally Grooved Tube Based on Flow Regime Information,
Satoru MOMOKI, Shinya HIGASHIIUE, Toru SHIGECHI, Hideo MORI, Tomohiko YAMAGUCHI,
Jounal of JSRAE, Vol.23, No3, pp.225-235, [URL].
56. Y. OKA, Y. ISHIWATARI, J. LIU, T. TERAI, S. NAGASAKI, Y. MUROYA, H. ABE, H. MORI, M. AKIBA, H. AKIMOTO, K. OKUMURA, N. AKASAKA and S. GOTO, Research Program of a Super Fast Reactor, Proceedings of 2006 International Congress on Advances in Nuclear Power Plants, Paper 6353, 2006.06.
57. The Application of Water Vapor Adsorption phenomena to The Independent Control of Latent and Sensible Heat,
Yoshinori HAMAMOTO, Hideo MORI,
Jounal of HTSJ, Vol.45, No.190, pp.33-38.
58. Enhancement in Heat Transfer of Honeycomb Structure, [URL].
59. Hideo MORI, Suguru YOSHIDA, Shinicni MOROOKA, Hideo KOMITA, Heat Transfer Study under Supercritical Pressure Conditions for Single Rod Test Section, Proceedings of 2005 International Congress on Advances in Nuclear Power Plants, Paper 5303, 2005.06.
60. S. MOMOKI, S. HIGASHIIUE, T. SHIGECHI, T. YAMAGUCHI, H. MORI, Experimental Study of Forced Convective Boiling Heat Transfer for Refrigerants in a Horizontal, Spirally Grooved Steel Tube, Proceedings of 18th International Conference on Efficiency, Cost, Optimization, Simulation and Environmental Impact of Energy Systems (ECOS 2005), p.897-904, 2005.06.
61. T.YAMASHITA, H.MORI, S.YOSHIDA, M.OHNO, Heat Transfer and Pressure Drop of a Supercritical Pressure Fluid Flowing in a Tube of Small Diameter, Memoirs of the Faculty of Engineering, Kyushu University, Vol.63, No.4,pp.227-244, 2003.12.
62. H.KOMITA, S.MOROOKA, S.YOSHIDA, H.MORI, Study on the Heat Transfer to the Supercritical Pressure Fluid for Supercritical Water Cooled Power Reactor Development, Proc. of 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics, CD-ROM, pp.1-11, 2003.10.
63. H.MORI, S.YOSHIDA, K.OHISHI, Boiling and Condensation Heat Transfer for New Refrigerants HFE245mc and HFE143m Flowing in Horizontal Tubes, 日本冷凍空調学会論文集, 第20巻第3号, 387〜396頁, 2003.09.
64. T. YAMASHITA, S.YOSHIDA, H.MORI, S.MOROOKA, H.KOMITA, K.NISHIDA, Heat Transfer Study under Supercritical Pressure Conditions, Proc. of Int. Conf. on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), CD-ROM, paper 1119, pp.1-8, 2003.09.
65. M.OKAWA, H.KOMITA, S.SHIGA, S.YOSHIDA, H.MORI, K.MORIYA, Supercritical Pressure Fluid Heat Transfer Study for Supercritical-water Cooled Power Reactor Development, Proc. of 13th Pacific Basin Nuclear Conf, CD-ROM, Paper TS-8B-5, pp.1〜8, 2002.10.
66. S.YOSHIDA, H.MORI, Heat Transfer to Supercritical Pressure Fluids Flowing in Tubes, Proc. of 1st Int. Symposium on Supercritical Water-Cooled Reactors, Design and Technology, pp.72〜78, 2000.11.
67. H.MORI, S.YOSHIDA, K.OHISHI, Y.KAKIMOTO, Dryout Quality and Post-Dryout Heat Transfer Coefficient in Horizontal Evaporator Tubes, Proc. of 3rd European Thermal Sciences Conf., Vol.2, pp.839〜844, 2000.09.
Presentations
1. Boiling Heat Transfer of a Refrigerant Flowing in a Horizontal Small Triangular Channe.
2. Examination of the measurement method for diffusivity in adsorbent with TGA.
3. Jie Li, Yoshinori Hamamoto, Hideo Mori, Measurement and Prediction of Absorbed Irradiation Energy Distribution in Narrow Channel of Desiccant Rotor, 15th Internat ional Heat Transfer Conference, IHTC-15 , 2014.08.
4. Takashi Mawatari, Hideo Mori, KEISHI KARIYA, A Study on Post-CHF Heat Transfer at Near-Critical Pressure, 15th Internat ional Heat Transfer Conference, IHTC-15 , 2014.08.
5. Takafumi Ouchi, Yoshinori Hamamoto, Hideo Mori, A Measurement Method of Adsorption/Desorption Rate Controlled by Adsorbent Temperature in Moist Air of
Atmospheric Pressure , 15th Internat ional Heat Transfer Conference, IHTC-15 , 2014.08.
6. Hideo Mori, Two-phase Flow and Boiling Heat Transfer in Small Diameter Tubes, Internatinal Symposium on Innovative Materials for Process in Energy Systems 2013, 2013.09.
7. Yudai MATSUSE, Koji ENOKI, Hideo Mori, KEISHI KARIYA, Yoshinori Hamamoto, Boiling Heat Transfer and Pressure Drop of a Refrigerant R32 Flowing in a Small Horizontal Tube, Internatinal Symposium on Innovative Materials for Process in Energy Systems 2013, 2013.09.
8. Yuki NAKASHIMA, Yusuke MIYAZAKI, KEISHI KARIYA, Katsunori HORII, Hideo Mori, Yoshinori Hamamoto, Observation of Refrigerant Flow in an Evaporator of Refrigerator During Heating Condition Simulating Defrosting Process, Internatinal Symposium on Innovative Materials for Process in Energy Systems 2013, 2013.09.
9. Fuka ONO, Shin NAKAMURA, Masahiko YAMADA, Hideo Mori, KEISHI KARIYA, Masaki OHNO, Shuichi UMESAWA, Hiroyuki SHIMADA, A Study on Characteristics of Cooling Heat Transfer of Supercritical Pressure Fluids in a Plate Exchanger, Internatinal Symposium on Innovative Materials for Process in Energy Systems 2013, 2013.09.
10. Takafumi Ouchi, Shou TAKATA, Yoshinori Hamamoto, Hideo Mori, Atsunori ETOH, Water Vapor Adsorption Equilibrium and Desorption Rate of Porous Alumina Film Adsorbent Synthesized with Anodization on Heat Transfer Plate, Internatinal Symposium on Innovative Materials for Process in Energy Systems 2013, 2013.09.
11. Flow Pattern of the Vapor-liquid Two-phase Flow in a Small Triangular Channel .
12. Y. Oka, S. Morooka, M. Yamakawa, Y. Ishiwatari, Y. Katsumura, Hideo Mori, Yoshinori Hamamoto, T. Kugo, K. Takase, K. Ezato, T. Misawa, Y. Watanabe, H. Abe, K. Sue, Progress of Super Fast Reactor Phase 2 Project and Studies of Waseda University, The 6th International Symposium on Supercritical Water-Cooled Reactors, 2013.03, The concept of Super FR of 1000MWe and 500C outlet coolant temperature is being developed by core design and safety analysis. Improved coolant flow scheme in the RPV was adopted in the design for simplifying upper core structure. The fundamental thermal-hydraulic data are being taken by the experiments at Kyusyu University with the surrogate fluid and at JAEA Naka laboratory with supercritical
water. Cross flow between sub-channels are measured at Kyushu University. The cross flow behaviors are analyzed with CFD code at JAEA Tokai. The experimental data of heat transfer coefficient of supercritical water at high temperature is being taken with single tube at JAEA Naka laboratory for accurate prediction of maximum cladding surface temperature by validating the results of the surrogate fluid. The material-coolant interaction and corrosion product transport are being studied at University of Tokyo. High temperature corrosion experiment is conducted at Tohoku University. Fuel cladding tube material of zirconium added austenitic stainless steel that was developed in the 1st phase project has good resistance against oxidation corrosion. The data base for the water chemistry was developed at AIST for understanding of corrosion product transport behavior. The results of heat transfer and materials constitute common data base for the Super FR and Super LWR design and analysis. Super LWR and Super FR design studies are carried out at Waseda University. Super LWR core with double tube water rods is developed for simplifying the upper core structure. Time dependent start-up analysis of Super FR is carried out. The accuracy of nuclear calculation by the SRAC code system is examined in comparison with Monte Carlo calculation. Pin-wise preparation of the blanket fuel assemblies with zirconium hydride layer overestimates plutonium accumulation and breeding. The results are presented at
ISSCWR6 separately. Plutonium breeding by light water cooling is being studied..
13. Kazuyuki Takase, Takeharu Misawa, Hiroyuki Yoshida, Hideo Mori, Numerical Predictions of Crossing-flow Characteristics of a Supercritical Fluid in Parallel Circular Ducts with a Narrow Rectangular Channel at Isothermal Condition, The 6th International Symposium on Supercritical Water-Cooled Reactors, 2013.03, Numerical analyses of crossing flows between two parallel circular channels were conducted for a specific geometry that modeled subchannels in a fuel bundle of a supercritical water reactor. The two parallel circular channels were connected by a rectangular channel in the axial direction. Crossing flow occurred in the rectangular channel and was caused by differences in temperatures of fluids flowing in the two channels. The working fluid was supercritical freon. The SST turbulence model was chosen for precisely calculating the boundary layers of temperature and velocity near the channel walls. From the analytical results, relations between crossing flow and fluid temperature were clarified quantitatively..
14. KEISHI KARIYA, Ken Yoshizumi, Hideo Mori, Takashi Mawatari, 大野 正規, Yoshinori Hamamoto, Correlation for Critical Heat Flux at Near-critical Pressure in Tubes, The 6th International Symposium on Supercritical Water-Cooled Reactors, 2013.03, The supercritical water cooled reactor (SCWR), which is a once-through water cooled
reactor supplying supercritical pressure steam at high temperature to the turbine system,
has an innovative and economical potential. During startup process and shutdown
procedure of the SCWR, the pressure of water passes through the critical pressure
condition. In the region of the pressure slightly below the critical pressure, critical heat
flux condition leading to the rapid rise of fuel rod surface temperature caused by
development of film boiling tends to occur at relatively low heat flux and high subcooling.
In the present study, the critical heat flux at near-critical pressure is measured for
vertically upward flow in a circular-tube of 4.4 mm I.D., in order to clarify the critical heat
flux condition in the near-critical pressure region. HFC134a and HCFC22 are used as the
test fluid. These fluids are easy for handing due to its low critical pressure and temperature, and therefore the experimental conditions can be set easily to make systematic data. As a result, four kinds of characteristics of CHF condition in near critical pressure are found. Based on their characteristics, the correlations of the critical heat flux in tubes are successfully developed with good accuracy including high-subcooled conditions..
15. Characteristics of Critical Heat Flux at Near-Critical Pressure
Takashi Mawatari, Ken Yoshizumi, Hideo Mori, Keishi Kariya and Masaki Ohno.
16. Study on Turbulent Mixing of Supercritical Pressure Fluid in Parallel Circular Channels with a Mixing Region
Yasuhiro SHIRAHAMA, Daisuke NISHI, Hideo MORI, Keishi KARIYA, Masaki OHNO.
17. Takafumi Ouchi, Yoshinori Hamamoto, Hideo Mori, Atsuro Etoh, Measurement and Prediction of the Thermal Resistance of a Thin Film Adsorbent Coated on a Heat Transfer Plate, The Third International Forum on Heat Transfer, 2012.11.
18. Takashi Mawatari, Ken Yoshizumi, Hideo Mori, KEISHI KARIYA, 大野 正規, Study on Critical Heat Flux at Near-critical Pressure, The Third International Forum on Heat Transfer, 2012.11.
19. Koji Enoki, Hideo Mori, Kazushi Miyata, KEISHI KARIYA, Yoshinori Hamamoto, Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing in Small Horizontal Tubes, The Third International Forum on Heat Transfer, 2012.11.
20. Characteristics of Heat Transfer of Supercritical pressure Fluid
Hideo Mori.
21. Study on Characteristics of Refrigerant Flow in an Evaporator During Defrosting Process.
22. Flow patterns of the vapor-liquid two-phase flow in small tubes.
23. Characteristics of Cooling Heat Transfer of Supercritical Pressure Fluids in a Plate Heat Exch,
Shin MAKAMURA, Yusaku INOUE, Hideo MORI, Keishi KARIYA, Masaki OHNO, Shuichi UMESAWA, Hiroyuki SHIMADA
.
24. Cooling Heat Transfer of Supercritical Pressure HFC134a in Plate-type Heat Exchanger,
Keishi KARIYA, Yusaku INOUE, Hideo MORI, Masaki OHNO
.
25. Measurement of Adsorption Equilibrium of Ethanol and Water Azeotropic Mixture on Activated Carbon Fiber and Performance Prediction of its Adsorption Refrigeration System,
Takafumi OUCHI, Keishi KARIYA, Atsuro ETOH, Hideo MORI, B.B. SAHA, Yoshinori HAMAMOTO.
26. Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing in a Small Horizontal Circular Tube,
KOji ENOKI, Hideo MORI, Kazushi MIYATA, Masahiro TASHIRO, Keishi KARIYA, Yoshinori HAMAMOTO.
27. Characteristics of Cooling Heat Transfer of Supercritical Pressure HFC134a in a Plate Heat Exchanger,
Yusaku INOUE, Hideo MORI, Keishi KARIYA, Masaki OHNO, Syuichi UMESAWA, Hiroyuki SHIMADA,
JSME The 16th National Symposium on Power and Energy Systems (SPES 2011).
28. Heat Transfer to Supercritical Pressure Fluid in Superheated Vapor Region,
Takenobu KAIDA, Hideo MORI, Keishi KARIYA, Masaki OHNO, Yoshinori HAMAMOTO,
JSME Thermal Engineering Conference.
29. Observation of the vapor-liquid two-phase flow patterns in a small diameter tubes,
Koji Enoki, Kazushi MIYATA, Hideo MORI, Yoshinori HAMAMOTO,
47th National Heat Transfer Symposium of Japan.
30. Effect of Superheat on Oscillatory Condensation of Vapor Directly Discharged into Subcooled Liquid Pool,
Masayuki NIIMI, Hideo MORI, Yoshinori HAMAMOTO,
JSME Kyushu Branch 63rd General Meeting Conferrence.
31. Study on Heat Transfer Correlations of Supercritical Pressure Fluids in the Superheated Vapor Region,
Takenobu KAIDA, Takeru YANAGIDA, Hideo MORI, Keishi KARIYA, Masaki OHNO, Yoshinori HAMAMOTO,
JSME Kyushu Branch 63rd General Meeting Conferrence.
32. Heat Transfer Regimes of Flow Boiling in Vertical Small Tubes,
Koji Enoki, Kazushi MIYATA, Daisuke OTSUJI, Hideo MORI, Yoshinori HAMAMOTO,
JSME Kyushu Branch 63rd General Meeting Conferrence.
33. Influence of the Expansion and Contraction Phenomena of a Metal Hydride Bed Absorbing and Desorbing Hydrogen on an Estimated Effective Thermal Conductivity of the Bed,
Yoshinori HAMAMOTO, Hideo MORI, Tadafumi MITANI, Yuki KANAYA, Atsuro ETOH,
2009 JSRAE Annual Conference.
34. Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing Vertically Upward in a Small Triangular Tube,
Koji Enoki, Kazushi MIYATA, Hideo MORI, Yoshinori HAMAMOTO,
2009 JSRAE Annual Conference.
35. Numerical Simulation of Heat and Mass Transfer in a Desiccant Rotor Regenerated by Concentrated Solar Irrdiance,
Yoshinori HAMAMOTO, Hideo MORI,
2009 JSRAE Annual Conference.
36. Measurement of an Expansion and a Contraction Ratio of Metal Hydride Bed by Hydrogen Adsorption and Desorption,
Yoshinori HAMAMOTO, Hideo MORI, Atsuro ETOH, Tadafumi MITANI, Yuki KANAYA,
46th National Heat Transfer Symposium of Japan.
37. Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing Vertically Upward in a Small Rectangular Tube,
Kazushi MIYATA, Koji ENOKI, Hideo MORI, Yoshinori HAMAMOTO,
46th National Heat Transfer Symposium of Japan.
38. Measurement of a Spectral Reflectivity, Absorptivity and Transmissivity of Water Vapor Adsorbents,
Yoshinori HAMAMOTO, Hideo MORI, Takafumi AKAI, Tatsuhiro FUKUDA,
46th National Heat Transfer Symposium of Japan.
39. Two-phase Pressure Drop of a Refrigerant Flowing Vertically Downward in Small Triangular Tubes,
Kazushi MIYATA, Hideo MORI, Katsumi OHISHI, Yoshinori HAMAMOTO,
2008 JSRAE Annual Conference.
40. Measuring Apparatus and Measurement of the Equilibrium Water vapor Adsorption with Moisture Measuring System,
Yoshinori HAMAMOTO, Takafumi AKAI, Hideo MORI, Tatsuhiro FUKUDA,
2008 JSRAE Annual Conference.
41. Measurement of Emissivity of Water Vapor Adsorbents with Infrared Radiation Thermometer,
Hamamoto Yoshinori, Hideo MORI, Takafumi Akai, Masafumi Mitani,
45th National Heat Transfer Symposium of Japan 2008.
42. Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing Vertically Downward in a Small Triangular Tube,
Kazushi MIYATA, Hideo MORI, Katsumi OHISHI, Yoshinori HAMAMOTO,
45th National Heat Transfer Symposium of Japan 2008.
43. Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing Vertically Downward in a Small Rectangular Tube,
Kazushi MIYATA, Hideo MORI, Katsumi OHISHI, Yoshinori HAMAMOTO,
2007 JSRAE Annual Conference.
44. Research and Development of Super Fast Reactor 7. Heat Transfer Experiments with Surrogate Test Fluid at Supercritical Pressure,
2007 Fall Meeting of the Atomic Energy Society of Japan
.
45. Measurement of Effective Thermal Conductivity of an Insulating Concrete Slab,
Yoshinori HAMAMOTO, Hideo MORI, Atsuro ETOH, Takaharu YAMASAKI, Mikiya TAOMOTO, Kenichi YANAGI,
44th National Heat Transfer Symposium of Japan.
46. Measurement and Prediction Method of Pressure Drop with Liquid and Gas Two Phase Flow Through a Porous Material,
Hideo MORI, Yoshinori HAMAMOTO, Naoki IWAMURA,
44th National Heat Transfer Symposium of Japan.
47. Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing in a Vertical Small Diameter Tube,
Kazushi MIYATA, Hideo MORI, Katsumi OHISHI, Yoshinori HAMAMOTO,
44th National Heat Transfer Symposium of Japan.
48. Technical Seeds Survey on Heat Exchanger Technology for Refrigerating and Air-conditioning Systems (Summary Report of Subcommittee for Heat Exchanger Technology),
Shigeru KOYAMA, Hideo MORI, Norio SAWADA
2006 JSRAE Annual Conference, [URL].
49. Boiling Heat Transfer and Pressure Drop of a Refrigerant Flowing Upward in a Vertical Small Diameter Tube,
Kazushi MIYATA, Ryohei MATSUO, Hideo MORI, Katsumi OHISHI,
2006 JSRAE Annual Conference.
Membership in Academic Society
  • Japan Society of Mechanical Engineers
  • Japan Society of Refrigerating and Air Conditioning Engineers
  • The Heat Transfer Society of Japan
  • Thermal and Nuclear Power Engineering Society
  • The Atomic Energy Society of Japan
  • Japan Society of Energy and Resources
Awards
  • Best Presentation Award,
    Asian Conference on Refrigeration And Air Conditioning, 2002
    Japan Society of Refrigerating and Air Conditioning Engineers
Educational
Educational Activities
[Graduate School]
Two-phase flow phenomena
Advanced Research in Thermal Engineering
[Undergraduate School]
Heat Transfer and Exercise
Thermal Energy Conversion
Other Educational Activities
  • 2009.01.