Oral Presentation

[1C01-07] Two-Phase Flow and Phase Change 1

Sat. Mar 26, 2016 10:10 AM - 12:00 PM Room C (Lecture Rooms B B103)

Chair: Masahiro Furuya (CRIEPI)

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10:10 AM - 10:25 AM

[1C01] Development of Prediction Technology of Two-Phase Flow Dynamics under Earthquake Acceleration

(31)Three-Dimensional Measurement of a Rising Single Bubble under the Horizontal Structure Vibration.

＊Akifumi Miyazaki¹, Yuki Kato^2,1, Tetsuya Kanagawa¹, Akiko Kaneko¹, Hideaki Monji¹, Hiroyuki yoshida², Yutaka Abe¹ (1.Univ.Tsukuba, 2.JAEA)

10:25 AM - 10:40 AM

[1C02] Flow Structure of Gas-Phase Jet with Pool Scrubbing

＊Kazuki Yamamoto¹, Takaaki Goi¹, Yuki Narushima¹, Akifumi Miyazaki¹, Tetsuya Kanagawa¹, Akiko Kaneko¹, Yutaka Abe¹ (1.University of Tsukuba)

10:40 AM - 10:55 AM

[1C03] Behavior of suspended particles in bubbles

＊Takaaki Goi¹, Kazuki Yamamoto¹, Shimpei Saito¹, Tomohisa Yuasa¹, Tetsuya Kanagawa², Akiko Kaneko², Yutaka Abe² (1.University of Tsukuba Graduate School, 2.University of Tsukuba)

10:55 AM - 11:10 AM

[1C04] Two-phase Flow Measurement in an Upward Pipe Flow Using Wire-Mesh Sensor Technology

＊Lifang Jiao¹, Kazuyuki Takase¹, Wei Liu¹, Taku Nagatake¹, Shinichiro Uesawa¹, Hiroyuki Yoshida¹, Mitsuhiko Shibata¹ (1.Japan Atomic Energy Agency)

11:10 AM - 11:25 AM

[1C05] Study on Seawater Pool Boiling Heat Transfer

(1)Effect of Deposited Minerals on Heat Transfer Surface

＊Shinichiro Uesawa¹, Yasuo Koizumi¹, Mitsuhiko Shibata¹, Hiroyuki Yoshida¹ (1.Japan Atomic Energy Agency)

11:25 AM - 11:40 AM

[1C06] Study on bubble nucleation behavior in subcooled flow boiling

＊Kazuhiro Kaiho¹, Kenta Tuchie², Koji Enoki¹, Tomio Okawa¹ (1.The university of electro-communications (Graduate school), 2.The university of electro-communications)

11:40 AM - 11:55 AM

[1C07] Numerical simulation of subcooled flow boiling using a particle-fluid model

＊Tomio Okawa¹, Naoki Miyano¹, Kazuhiro Kaiho¹, Koji Enoki¹ (1.The University of Electro-Communications)

Time reserved for Chair （11:55 AM - 12:00 PM）

Oral Presentation

[1C08-14] Severe Accident 1

Sat. Mar 26, 2016 2:45 PM - 4:30 PM Room C (Lecture Rooms B B103)

Chair: Yoshiro Kudo (NRA)

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2:45 PM - 3:00 PM

[1C08] Development of Numerical Simulation for Jet Break up Behavior in
Complicated Structure of BWR Lower Plenum

Evaluation of Jet Breakup Length in Complicated Structures using LIF Method

＊Yuki Narushima¹, Yutaka Abe¹, Akiko Kaneko¹, Tetsuya Kanagawa¹, Takayuki Suzuki², Hiroyuki Yoshida² (1.University of Tsukuba, 2.JAEA)

3:00 PM - 3:15 PM

[1C09] Development of Numerical Simulation for Jet Breakup Behavior in Complicated Structure of BWR Lower Plenum

(13)Effects of spatial resolution on the molten material atomization behavior

＊Takayuki Suzuki¹, Hiroyuki Yoshida², Yuki Narushima³, Akiko Kaneko³, Yutaka Abe³ (1.Yamato System Engineer, 2.Japan Atomic Energy Agency, 3.University of Tsukuba)

3:15 PM - 3:30 PM

[1C10] Visualization Experiment of Zirconium-Steam Reaction

1. Outline of the equipment for visualization experiment of zirconium-steam reaction

＊Shunsuke Uchida¹, Hide Okada¹, Masanori Naitoh¹, Yukio Hanamoto², Masahiro Fujikawa³ (1.The Institute of Applied Energy, 2.Kaken, 3.Japan Broadcasting Corporation)

3:30 PM - 3:45 PM

[1C11] Visualization Experiment of Zirconium-Steam Reaction

2. Experimental Results and Their Application for Future Studies

＊Hide Okada¹, Shunsuke Uchida¹, Masanori Naitoh¹, Yukio Hanamoto², Masahiro Fujikawa³ (1.The Institute of Applied Energy, 2.Kaken, 3.Japan Broadcasting Corporation)

3:45 PM - 4:00 PM

[1C12] Experiments on Influences of Injecting Seawater and Boric Acid under Severe Accident Conditions

(4)Sea-salt and Borated-salt co-precipitation in 5x5 bundle geometry due to boiling

＊Masahiro Furuya¹ (1.CRIEPI)

4:00 PM - 4:15 PM

[1C13] Experiments on influences of injecting seawater and boric acid under severe accident conditions

(5)Method for precipitation behavior prediction in rod bundle assemblies

＊Miyuki Akiba¹, Akitoshi Hotta¹ (1.Nuclear regulation authority)

4:15 PM - 4:30 PM

[1C14] Anlysis on NUPEC M-7-1 test based on GOTHIC fully distributed parameter modeling

＊Takeshi Nishimura¹, Akitoshi Hotta¹ (1.S/NRA/R)

Oral Presentation

[1C15-17] Reactor System Code

Sat. Mar 26, 2016 4:30 PM - 5:20 PM Room C (Lecture Rooms B B103)

Chair: Satoshi Nishimura (CRIEPI)

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4:30 PM - 4:45 PM

[1C15] Development of thermal-hydraulic module of DONJON for BWR simulation

＊Kyohei Yoshinaga¹, Augusto Solis², Henrik Sjöstrand², Kenji Takeshita¹ (1.Tokyo Institute of Technology, 2.Uppsala Univ.)

4:45 PM - 5:00 PM

[1C16] Application of the statistical method to the small break LOCA with high pressure injection failure

(14)Statistical Safety Analysis in a PWR, Part1

＊Toshihide Torige¹, Ikuo Kinoshita¹, Minoru Yamada² (1.INSS, 2.MHI NSENG)

5:00 PM - 5:15 PM

[1C17] Application of the statistical method to the small break LOCA with high pressure injection failure

(15)Statistical Safety Analysis in a PWR, Part2

＊Ikuo Kinoshita¹, Toshihide Torige¹, Minoru Yamada² (1.INSS, 2.MHI NS Engineering)

Time reserved for Chair （5:15 PM - 5:20 PM）

Oral Presentation

[1D01-07] Thermal Hydraulics of Sodium-Cooled Fast Reactors 1

Sat. Mar 26, 2016 10:00 AM - 11:50 AM Room D (Lecture Rooms B B104)

Chair: Minoru Takahashi (Tokyo Tech)

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10:00 AM - 10:15 AM

[1D01] Study on Flow-Induced-Vibration Evaluation of Large-Diameter Piping in a Sodium-Cooled Fast Reactor

(45)Visualization of the Flow Field in a Triple Elbow Piping System under Swirling Inflow Conditions

Jun Mizutani¹, ＊Shinji Ebara¹, Hidetoshi Hashizume¹, Hidemasa Yamano² (1.Tohoku Univ., 2.JAEA)

10:15 AM - 10:30 AM

[1D02] Study on Flow-Induced-Vibration Evaluation of Large-Diameter Pipings in a Sodium-Cooled Fast Reactor

(46) Characteristic of pressure fluctuations in a triple elbow flow under swirling inflow conditions

＊Takatoshi Hosoda¹, Jun Mizutani¹, Shinji Ebara¹, Hidetoshi Hashizume¹, Hidemasa Yamano² (1.Tohoku Univ., 2.Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[1D03] Development of a Coupled Sodium Side and Water Side Simulation Model for FBR Steam Generator

Validation by thermal hydraulic tests on 1MWt double-wall-tube SG

＊Ryuji Yoshikawa¹, Yasutomo Imai², Masaaki Tanaka¹, Kazuyoshi Nagasawa³, Hiroyuki Ohshima¹ (1.Japan Atomic Energy Agency, 2.NDD Corporation, 3.NESI Corporation)

10:45 AM - 11:00 AM

[1D04] Parameteric Analysis of Self-wastage phenomena in Sodium-Water Reaction

＊Sunghyon Jang¹, Akira Yamaguchi¹, Hiroyuki Ohshima², Takashi Takata² (1.Department of Nuclear Engineering and Mangement, School of Engineering, The University of Tokyo, 2. Japan Atomic Energy Agency)

11:00 AM - 11:15 AM

[1D05] Study on self-wastage phenomenon at heat transfer tube in steam generator of sodium-cooled fast reactor with consideration of thermal coupling of fluid and structure

＊Saori Kojima¹, Akihiro UCHIBORI², Takashi TAKATA², Shuji OHNO², Takeshi FUKUDA¹, Akira YAMAGUCHI³ (1.Osaka University, 2.JAEA, 3.The University of Tokyo)

11:15 AM - 11:30 AM

[1D06] Study on Cavitation Due to Sub-Surface Vortex at Intake of Hot-Leg Pipe in Sodium Cooled Fast Reactor

(7th report) Modeling of Vortical Velocity Field in Wall Boundary Layer

＊Kei Ito¹, Toshiki Ezure^1,2, Tomoaki Kunugi², Hiroyuki Ohshima¹ (1.JAEA, 2.Kyoto University)

11:30 AM - 11:45 AM

[1D07] Study on Cavitation Due to Sub-Surface Vortex at Intake of Hot-Leg Pipe in Sodium Cooled Fast Reactor

Evaluation of Vortex Cavitation Considering Turbulent Viscosity

＊Toshiki Ezure^1,3, Kei Ito¹, Yuri Kameyama², Akikazu Kurihara¹, Tomoaki Kunugi³ (1.JAEA, 2.NDD Corp., 3.Kyoto Univ.)

Time reserved for Chair （11:45 AM - 11:50 AM）

Oral Presentation

[1D08-13] Thermal Hydraulics of Sodium-Cooled Fast Reactors 2

Sat. Mar 26, 2016 2:45 PM - 4:15 PM Room D (Lecture Rooms B B104)

Chair: Kazuyuki Takase (JAEA)

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2:45 PM - 3:00 PM

[1D08] Analysis of core thermal hydraulics under natural circulation condition with plant dynamics analysis code Super-COPD

(2)Applicability evaluation of the inter-subassembly heat transfer model -

＊Erina HAMASE¹, Norihiro DODA¹, Kunihiko NABESHIMA¹, Ayako ONO¹, Hiroyuki Ohshima¹ (1.Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1D09] IAEA benchmark analysis on the natural circulation tests of fast reactor EBR-II

燃料集合体内サブチャンネル解析

＊KOMEI Muranaka¹, HIROYASU Mochizuki¹ (1.University of Fukui)

3:15 PM - 3:30 PM

[1D10] Validation of natural circulation heat removal evaluation method by using EBR-II shutdown heat removal test data

＊Norihiro Doda¹, kennichi igawa², masaki minami², takashi iwasaki², hiroaki ohira¹ (1.JAEA, 2.NESI)

3:30 PM - 3:45 PM

[1D11] Study on reactor vessel coolability of sodium-cooled fast reactor under severe accident condition

(3)Design study of large scale sodium test facility AtheNa-RV

＊Kunihiko NABESHIMA¹, Norihiro DODA¹, Nobuyuki ISHIKAWA¹, Katsunori AMANO¹, Hiroyuki OHSHIMA¹ (1.JAEA)

3:45 PM - 4:00 PM

[1D12] Study on quench behavior at core disruptive accident for fast breeder reactor

(29)Droplet formation of a liquid jet in another immiscible liquid

＊Shimpei Saito¹, Yutaka Abe¹, Akiko Kaneko¹, Tetsuya Kanagawa¹, Yuzuru Iwasawa¹, Sakaba Hiroshi², Kazuya Koyama³, Hideki Nariai¹ (1.Univ. of Tsukuba, 2.MHI, 3.MFBR)

4:00 PM - 4:15 PM

[1D13] Study on Quench Behavior at Core Disruptive Accident for Fast Breeder Reactor

(30)Fragmentation of a melt jet with surface solidification

＊Yuzuru Iwasawa¹, Abe Yutaka¹, Akiko Kaneko¹, Tetsuya Kanagawa¹, Shimpei Saito¹, Hiroshi Sakaba², Kazuya Koyama³, Hideki Nariai¹ (1.University of Tsukuba, 2.Mitsubishi Heavy Industries, Ltd., 3.Mitsubishi FBR Systems, Inc.)

Oral Presentation

[1D14-16] Source Term

Sat. Mar 26, 2016 4:15 PM - 5:00 PM Room D (Lecture Rooms B B104)

Chair: Murase Michio (INSS)

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4:15 PM - 4:30 PM

[1D14] Preliminary analysis of Fission Product distribution at Fukushima Daiichi Nuclear Power Plants with MAAP 5.03

(1)Unit-2 analysis

＊Kenichi Kanda¹, Kazuma Abe¹, Yoshihisa Nishi¹, Satoshi Nishimura¹, Koichi Nakamura¹, Masahiro Furuya¹, Atsushi Ui¹ (1.Central Research Institute of Electric Power Industry)

4:30 PM - 4:45 PM

[1D15] Preliminary analysis of Fission Product distribution at Fukushima Daiichi Nuclear Power Plants with MAAP 5.03

(2)Unit-3 analysis

＊Kazuma Abe¹, Kenichi Kanda¹, Yoshihisa Nishi¹, Satoshi Nishimura¹, Koichi Nakamura¹, Masahiro Furuya¹, Atsushi Ui¹ (1.Central Research Institute of Electric Power Industry)

4:45 PM - 5:00 PM

[1D16] Evaluation of Fission Products Released during the NPP Severe Accident

Validation of pool scrubbing model for aerosol fission products

＊Ayumi Itoh¹ (1.The Institute of Applied Energy)

Oral Presentation

[1D17-21] Filtered Vent

Sat. Mar 26, 2016 5:00 PM - 6:15 PM Room D (Lecture Rooms B B104)

Chair: Arai Takahiro (CRIEPI)

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5:00 PM - 5:15 PM

[1D17] Development of evaluation method for two-phase flow in Venturi scrubber for filtered venting

(1)Measurement of liquid film thickness in diffuser part

＊Yasuhiro Nakao¹, Naoki Horiguchi^1,2, Hiroyuki Yoshida², Tetsuya Kanagawa¹, Akiko Kaneko¹, Yutaka Abe¹ (1.University of Tsukuba, 2.JAEA)

5:15 PM - 5:30 PM

[1D18] Development of evaluation method for two-phase flow in Venturi scrubber for filtered venting

(2)Measurement with visualization of cross-sectional distribution of droplets

＊Naoki Horiguchi^1,2, Hiroyuki Yoshida¹, Yasuhiro Nakao², Tetsuya Kanagawa¹, Akiko Kaneko¹, Yutaka Abe¹ (1.Univ. of Tsukuba, 2.JAEA)

5:30 PM - 5:45 PM

[1D19] Sophistication of filtered containment venting system operation

(6)Numerical modeling of aerosol decontamination performance

＊Taizo Kanai¹, Masahiro Furuya¹, Takahiro Arai¹, Yoshihisa Nishi¹ (1.CRIEPI)

5:45 PM - 6:00 PM

[1D20] Development of a high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core debris

(1)Outline of this study and schedule

＊Tadashi Narabayashi¹, Go Chiba¹, Tamotsu Kozaki¹, Takao masuda¹, Yuta Makasaka¹, Masanobu Sato², Daisuke Akiyama² (1.Hokkaido Univ., 2.Tohoku Univ.)

6:00 PM - 6:15 PM

[1D21] Development of a high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core debris

(2)Evaluation of Sorption and Desorption Behavior of Methyl Iodine by Silver Doped Zeolite

＊Daisuke Akiyama¹, Tasuku Ishii¹, Nobuaki Sato¹, Akira Kirishima¹, Tadashi Narabayashi² (1.Tohoku Univ., 2.Hokkaido Univ.)

Oral Presentation

[2C01-05] Fukushima NPP Accident 1

Sun. Mar 27, 2016 9:30 AM - 10:50 AM Room C (Lecture Rooms B B103)

Chair: Kenichi Katono (Hitachi)

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9:30 AM - 9:45 AM

[2C01] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(59)Model improvements of SAMPSON code based on the previous analysis results

＊Hiroaki Suzuki¹, Masanori Naitoh¹, Hidetoshi Okada¹, Marco Pellegrini¹ (1.The Institute of Applied Energy)

9:45 AM - 10:00 AM

[2C02] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(60)Accident Analysis of Fukushima Daiichi Unit 1 by SAMPSON Severe Accident Code

＊Yoshihiro Morita¹, Marco Pellegrini¹, Youko Yamane¹, Masanori Naitoh¹, Hiroaki Suzuki¹ (1.The Institute of Applied Energy)

10:00 AM - 10:15 AM

[2C03] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(61)Accident Analysis of Fukushima Daiichi Unit 2 by SAMPSON Severe Accident Code

＊Naotoshi Tominaga¹, Masanori Naitoh¹, Hiroaki Suzuki¹, Marco Pellegrini¹ (1.The Institute of Applied Energy)

10:15 AM - 10:30 AM

[2C04] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(62)Accident Analysis of Fukushima Daiichi Unit 3 by SAMPSON Severe Accident Code

＊Marco Pellegrini¹, Hiroaki Suzuki¹, Masanori Naitoh¹ (1.The Institute of Applied Energy)

10:30 AM - 10:45 AM

[2C05] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(63)Validation of Debris Freezing Model in a penetration tube with GEYSER Experiment

＊Hiroyuki Suzuki¹, Marco Pellegrini¹, Hiroaki Suzuki¹, Masanori Naitoh¹ (1.Institute of Applied Energy)

Time reserved for Chair （10:45 AM - 10:50 AM）

Oral Presentation

[2C06-10] Fukushima NPP Accident 2

Sun. Mar 27, 2016 10:50 AM - 12:10 PM Room C (Lecture Rooms B B103)

Chair: Shinya Mizokami (TEPCO)

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10:50 AM - 11:05 AM

[2C06] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(64)Validation of SAMPSON/DCA creep model against OLHF experiments

＊Filippo Scarpa¹, Marco Pellegrini¹, Masanori Naitoh¹ (1.IAE)

11:05 AM - 11:20 AM

[2C07] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(65)Validation of fragmentation and heat transfer model for molten corium using FARO

＊Chiaki Kino¹, Hidetoshi Okada¹, Masanori Naito¹ (1.The Institute of Applied Energy)

11:20 AM - 11:35 AM

[2C08] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(66)Assessment of Condensation Performance and Experiment with Instrument of Simulated Isolation Condenser

Hiroshige Kikura¹, Satoru Ito¹, ＊Takao Ishizuka¹ (1.Tokyo Institute of Technology)

11:35 AM - 11:50 AM

[2C09] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(67)Experimental Investigation of Spreading Behaviors of Molten Core Debris

＊Tatsuki Matsumoto¹, Takahito Ogura¹, Zaiyong Ma², Sora Nishigaki¹, Shuichiro Miwa¹, Hiroto Sakashita¹, Michitsugu Mori¹ (1.Hokkaido univ., 2.Xi'an Jiaotong Univ.)

11:50 AM - 12:05 PM

[2C10] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(68)A new heat transfer model for simulating Corium-Concrete Interaction in DSA module of SAMPSON code

＊Mirco Giuli¹, Marco Pellegrini¹, Masanori Naitoh¹ (1.IAE The institute of Applied Energy)

Time reserved for Chair （12:05 PM - 12:10 PM）

Oral Presentation

[2C11-17] Fukushima NPP Accident 3

Sun. Mar 27, 2016 2:45 PM - 4:35 PM Room C (Lecture Rooms B B103)

Chair: Koji Nishida (HGNE)

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2:45 PM - 3:00 PM

[2C11] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(69)Parametric Analysis of Cross-flow Effect at CCFL Condition during MCCI

＊Masaya Kondo¹, Jun Sugimoto² (1.Thermohydraulics Laboratory, 2.Kyoto University)

3:00 PM - 3:15 PM

[2C12] Assessment of Core Status of TEPCO’s Fukushima Daiichi Nuclear Power Plants

(70)Development of Model for Advection and Diffusion of Eroded Concrete in Analysis of Molten Core Concrete Interaction

＊Masataka Hidaka¹, Tadashi Fujii¹, Takeshi Sakai¹ (1.Hitachi-GE Nuclear Energy, Ltd.)

3:15 PM - 3:30 PM

[2C13] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(71)Estimation of the FP transfer path from CAMS dose rate measurement in Fukushima Daiichi unit 2

＊Shinya MIZOKAMI¹, Daichi YAMADA¹, Takeshi HONDA¹, Daisuke YAMAUCHI¹, Shoichi SUEHIRO², Yusuke MATSUI², Yasunori YAMANAKA¹ (1.Tokyo Electric Power Company, 2.Tepco Systems Inc.)

3:30 PM - 3:45 PM

[2C14] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(72)Water level and temperature transient in the suppression chamber at Unit 2

＊Takahiro Hirano¹ (1.Nuclear Safety Gropu Nuclear Safety Management Department TOKYO ELECTRIC POWER COMPANY)

3:45 PM - 4:00 PM

[2C15] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(73)Study on Unit 2 RCIC Exhaust Flow after SBO

Shinya MIZOKAMI², Takeshi HONDA², Daisuke YAMAUCHI², ＊Shoichi SUEHIRO¹, Hiroshi SHIRAI¹, Kenichiro NOZAKI¹ (1.TEPSYS, 2.TEPCO)

4:00 PM - 4:15 PM

[2C16] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(74)Analysis of temperature distribution in pool induced by RCIC and SRV steam discharge

＊Kenichiro Nozaki¹, Shoichi Suehiro¹, Hiroshi Shirai¹, Shinya Mizokami², Takeshi Honda², Daisuke Yamauchi² (1.TEPSYS, 2.TEPCO)

4:15 PM - 4:30 PM

[2C17] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(75)Leakage and massive steam release from the PCV at Unit 3

＊TAKESHI HONDA¹, Shinya Mizokami¹, Daisuke Yamauchi¹, Yasunori Yamanaka¹ (1.TEPCO)

Time reserved for Chair （4:30 PM - 4:35 PM）

Oral Presentation

[2C18-24] Severe Accident 2

Sun. Mar 27, 2016 4:35 PM - 6:25 PM Room C (Lecture Rooms B B103)

Chair: Yoshihisa Nishi (CRIEPI)

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4:35 PM - 4:50 PM

[2C18] Development of Numerical Simulation Method for Relocation Behavior of Molten Materials in Nuclear Reactors

(6)Consideration of the melt diffusion model on interfaces

＊Susumu Yamashita¹, Kazuyuki Takase¹, Hideaki Monji², Hiroyuki Yoshida¹ (1.JAEA, 2.Univ. of Tsukuba)

4:50 PM - 5:05 PM

[2C19] Development of Numerical Simulation Method for Relocation Behavior of Molten Materials in Nuclear Reactors

(7)Visualization of Interface Behavior of Simulated Molten Fluid

＊Kota Matsuura¹, Hideaki Monji¹, Susumu Yamashita², Hiroyuki Yoshida² (1.University of Tsukuba, 2.JAEA)

5:05 PM - 5:20 PM

[2C20] Thermal hydraulics in reactor core under rod bundle uncovery conditions

(10)Void fraction measurement in 5X5 non-heated rod bundle at low flow rate and low pressure conditions

＊Kenichi Katono¹, Kiyoshi Fujimoto¹, Goro Aoyama¹, Takuji Nagayoshi¹, Kenichi Yasuda¹, Takahiro Arai² (1.Hitachi-GE Nuclear Energy, 2.Central Research Institute of Electric Power Industry)

5:20 PM - 5:35 PM

[2C21] Thermal hydraulics in reactor core under rod bundle uncovery conditions

(11)Pressure effect on boiling two-phase flow development in heated rod bundle under low flow rate during accidents

＊Takahiro Arai¹, Masahiro Furuya¹, Kenetsu Shirakawa¹, Yoshihisa Nishi¹ (1.CRIEPI)

5:35 PM - 5:50 PM

[2C22] First experiments using the CIGMA facility on LWR containment thermal hydraulics

＊Yasuteru Sibamoto¹, Satoshi Abe¹, Masahiro Ishigaki¹, Taisuke Yonomoto¹ (1.Japan Atomic Energy Institute)

5:50 PM - 6:05 PM

[2C23] Necessity of a fundamental experiment for evaluating two-phase flow bahavior in a RCIC of the Fukushima Dai-ichi nuclear power plant No.2 unit

＊Kazuyuki Takase¹, Hiroyuki Yoshida¹, Hidetoshi Okada², Souji Koikari², Nobuyoshi Tsuzuki² (1.Japan Atomic Energy Agency, 2.Institute of Advanced Energy)

6:05 PM - 6:20 PM

[2C24] Development on Flat and High Thermal Conductivity Core-Catcher

(2)Cooling characteristic estimation test

＊Kazuyoshi Aoki¹, Ryoma Fujihara¹, Tomohisa Kurita¹, Mikihide Nakamaru¹, yoichi Onitsuka¹ (1.Toshiba)

Time reserved for Chair （6:20 PM - 6:25 PM）

Oral Presentation

[2D01-05] Thermal Hydraulics Fundamental Technology 1

Sun. Mar 27, 2016 9:30 AM - 10:50 AM Room D (Lecture Rooms B B104)

Chair: Kei Ito (JAEA)

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9:30 AM - 9:45 AM

[2D01] Study on Liquid film Impingement Phenomena of Liquid Jet

＊Naoki Oya¹, Tomio Okawa¹, Koji Enoki¹, Shuji Ohno², Mitsuhiro Aoyagi² (1.The University of Electro-Communications, 2.Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[2D02] Countercurrent Flow Limitation in the Vertical Pipe of a Pressurizer Surge Line

＊Michio Murase¹, Takayoshi Kusunoki¹, Yasunori Yamamoto¹, Katsuya Mori², Akio Tomiyama² (1.Institute of Nuclear Safety System, Inc., 2.Kobe University)

10:00 AM - 10:15 AM

[2D03] Study on Counter-Current Flow Limitation in Inclined Rectangular Channels

＊Touma Furukawa¹, Jun Sugimoto¹ (1.Kyoto Univ.)

10:15 AM - 10:30 AM

[2D04] Mechanism of Subcooled Water Flow Boiling Critical Heat Flux in a Platinum Circular Tube at High Liquid Reynolds Number

＊Koichi Hata¹, Katsuya FUKUDA¹, Suguru MASUZAKI² (1.Graduate School of Maritime Sciences, Kobe University , 2.National Institute for Fusion Science)

10:30 AM - 10:45 AM

[2D05] Experimental study on characteristic of natural circulation flow in the expanding and reduction pipe

＊Takuma Yamaguchi¹, Shinichi Morooka¹, Kasumi Fujioka¹ (1.Waseda Univ.)

Time reserved for Chair （10:45 AM - 10:50 AM）

Oral Presentation

[2D06-09] Thermal Hydraulics Fundamental Technology 2

Sun. Mar 27, 2016 10:50 AM - 11:55 AM Room D (Lecture Rooms B B104)

Chair: Shinji Ebara (Tohoku Univ.)

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10:50 AM - 11:05 AM

[2D06] Influence of the Height of Support on the Convection Behavior and Heating Efficiency Under Microwave Heating

＊Fuminori Chonan¹, Yutaka Abe¹, Akiko Kaneko¹, Tetsuya Kanagawa¹, Tomohisa Yuasa¹, Tomoomi Segawa², Yoshikazu Yamada² (1.University of Tsukuba, 2.Japan Atomic Energy Agency)

11:05 AM - 11:20 AM

[2D07] Fundamental Study of Ultrasonic Visualization Technique for Identifying Leakage Point

＊Takuya Kawachi¹, Tomonori Ihara¹, Hiroshige Kikura¹, Naoyuki Kono² (1.Tokyo Tech, 2.Hitachi R&D)

11:20 AM - 11:35 AM

[2D08] Numerical analysis of instability of plane gas sheets in a quiescent liquid phase

＊Yuria Okagaki¹, Taisuke Yonomoto¹, Masahiro Ishigaki¹ (1.Japan Atomic Energy Agency)

11:35 AM - 11:50 AM

[2D09] Flow transition caused by nonuniform wall heating in a vertical annular channel

＊Toshiro Kamidani¹, Tomoaki Kunugi¹, Takehiko Yokomine¹ (1.Kyoto Univ.)

Time reserved for Chair （11:50 AM - 11:55 AM）

Oral Presentation

[3C01-04] Core Thermal Hydraulics

Mon. Mar 28, 2016 9:30 AM - 10:35 AM Room C (Lecture Rooms B B103)

Chair: Hiroyuki Yoshida (JAEA)

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9:30 AM - 9:45 AM

[3C01] Critical Heat Flux in Tight Lattice Three-Pin Bundle with and without Wire Spacer

Dan Le¹, ＊Sho Tanabe¹, Minoru Takahashi², Masatoshi Kondo² (1.Department of Nuclear Engineering, Tokyo Institute of Technology, 2.Research Laboratory for Nuclear Reactor, Tokyo Institute of Technology)

9:45 AM - 10:00 AM

[3C02] Development of RBWR for Long-lived Transuranium Elements Burner

(11)Investigation of Flow Integrity of Fuel Assembly Components

＊Shiro Takahashi¹, Kiyoshi Fujimoto¹, Hideaki Hosoi¹, Masaya Ohtsuka¹ (1.Hitachi, Ltd.,)

10:00 AM - 10:15 AM

[3C03] Development of RBWR for Long-lived Transuranium Elements Burner

(12)Investigation of Core Inlet Flow Characteristics

＊Hideaki Hosoi¹, Shiro Takahashi¹, Kiyoshi Fujimoto¹, Naohisa Watahiki¹, Masaya Ohtsuka¹ (1.Hitachi, Ltd)

10:15 AM - 10:30 AM

[3C04] Measurement of void fraction distribution in two-phase flow in a 4×4 bundle

(1)Experiments with air-water two-phase flow under atmospheric pressure condition

＊Wei Liu¹, Taku Nagatake¹, Lifang Jiao¹, Mitsuhiko Shibata¹, Masao Komatsu¹, Kazuyuki Takase¹, Hiroyuki Yoshida¹ (1.Japan Atomic Energy Agency)

Time reserved for Chair （10:30 AM - 10:35 AM）

Oral Presentation

[3C05-09] Severe Accident Analytical Method

Mon. Mar 28, 2016 10:35 AM - 11:55 AM Room C (Lecture Rooms B B103)

Chair: Hidetoshi Okada (IAE)

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10:35 AM - 10:50 AM

[3C05] Development of eutectic reaction model on MPS method for stainless steel/boron carbide system

＊Shota Ueda¹, Hirosih Madokoro¹, Byeongnam Jo², Masahiro Kondo², Nejdet Erkan², Koji Okamoto² (1.Dept. of NEM, School of Engineering, The University of Tokyo, 2.Nuclear Professional School, The University of Tokyo)

10:50 AM - 11:05 AM

[3C06] Fuel-Coolant interaction analysis based on SERENA2

＊Akinobu Morita¹, Akitoshi Hotta¹ (1.S/NRA/R)

11:05 AM - 11:20 AM

[3C07] Develpoment of Evaluation Method of Air Cooling Performance for Fuel Debris

(1)Outline of Research Project

＊Hiroyuki Yoshida¹, Susumu Yamashita¹, Shinichiro Uesawa¹, Fumihisa Nagase¹ (1.Japan Atomic Energy Agency)

11:20 AM - 11:35 AM

[3C08] Development of Analytical Method for Behavior of Fuel Melting by Particle Method

(6)Consideration of Melting Model for Multi-component Analysis

＊Taku Nagatake¹, Kazuyuki Takase¹, Hiroyuki Yoshida¹ (1.Japan Atomic Energy Agency)

11:35 AM - 11:50 AM

[3C09] Development status of hydrogen behavior simulation for NPP containment

hydrogen combustion simulation

＊Atsuhiko Terada¹, Yu Kamiji¹, Hino Ryutaro¹, Masaaki Matsumoto², Hitoshi Sugiyama³, Satoshi Kadowaki⁴ (1.JAEA, 2.MRI, 3.Utsunomiya Univ., 4.Nagaoka Univ. of Tech.)

Time reserved for Chair （11:50 AM - 11:55 AM）

Oral Presentation

[3C10-14] Two-Phase Flow and Phase Change 2

Mon. Mar 28, 2016 2:45 PM - 4:05 PM Room C (Lecture Rooms B B103)

Chair: Tomio Okawa (UEC)

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2:45 PM - 3:00 PM

[3C10] Numerical Study on Bubbly Flow Coupling with Probability Density Function

＊Kana Fukuoka¹, Takashi Takata¹, Eiji Hoashi¹, Takeshi Fukuda¹, Akira Yamaguchi² (1.Osaka Univ., 2.The University of Tokyo)

3:00 PM - 3:15 PM

[3C11] Development of liquid and gas velocity measurement method in two-phase flow

＊Hiroki Takiguchi¹, Masahiro Furuya¹, Takahiro Arai¹, Taizo Kanai¹ (1.Central Research Institute of Electric Power Industry)

3:15 PM - 3:30 PM

[3C12] Characteristics of the Steam Injector as the Passive Reactor Cooling System

＊Hiroto Endo¹, Shuichiro Miwa¹, Michitsugu Mori¹ (1.Hokkaido University Graduate School of Engineering)

3:30 PM - 3:45 PM

[3C13] Experimental Study on Chugging Phenomena in Steam-Water Direct Contact Condennsation

Giuseppe Gregu², ＊Minoru Takahashi¹, Riccardo Mereu², Marco Pellegrini³ (1.Tokyo Tech RLNR, 2.Politecnico di Milano, 3.Inst. Applied Energy)

3:45 PM - 4:00 PM

[3C14] Study on condition occuring thermal stratification in suppression chamber using model of steam condensation

＊Daisuke YAMAUCHI¹, Nejdet ERKAN², Byeongnam JO², Koji OKAMOTO² (1.Department of Nuclear Engineering and Management, School of Engineering, the University of Tokyo, 2.Nuclear Professional School The University of Tokyo)

Time reserved for Chair （4:00 PM - 4:05 PM）

Sessions

III. Fission Energy Engineering » 304-1. Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[1C01-07] Two-Phase Flow and Phase Change 1

(31)Three-Dimensional Measurement of a Rising Single Bubble under the Horizontal Structure Vibration.

(1)Effect of Deposited Minerals on Heat Transfer Surface

[1C08-14] Severe Accident 1

Evaluation of Jet Breakup Length in Complicated Structures using LIF Method

(13)Effects of spatial resolution on the molten material atomization behavior

1. Outline of the equipment for visualization experiment of zirconium-steam reaction

2. Experimental Results and Their Application for Future Studies

(4)Sea-salt and Borated-salt co-precipitation in 5x5 bundle geometry due to boiling

(5)Method for precipitation behavior prediction in rod bundle assemblies

[1C15-17] Reactor System Code

(14)Statistical Safety Analysis in a PWR, Part1

(15)Statistical Safety Analysis in a PWR, Part2

[1D01-07] Thermal Hydraulics of Sodium-Cooled Fast Reactors 1

(45)Visualization of the Flow Field in a Triple Elbow Piping System under Swirling Inflow Conditions

(46) Characteristic of pressure fluctuations in a triple elbow flow under swirling inflow conditions

Validation by thermal hydraulic tests on 1MWt double-wall-tube SG

(7th report) Modeling of Vortical Velocity Field in Wall Boundary Layer

Evaluation of Vortex Cavitation Considering Turbulent Viscosity

[1D08-13] Thermal Hydraulics of Sodium-Cooled Fast Reactors 2

(2)Applicability evaluation of the inter-subassembly heat transfer model -

燃料集合体内サブチャンネル解析

(3)Design study of large scale sodium test facility AtheNa-RV

(29)Droplet formation of a liquid jet in another immiscible liquid

(30)Fragmentation of a melt jet with surface solidification

[1D14-16] Source Term

(1)Unit-2 analysis

(2)Unit-3 analysis

Validation of pool scrubbing model for aerosol fission products

[1D17-21] Filtered Vent

(1)Measurement of liquid film thickness in diffuser part

(2)Measurement with visualization of cross-sectional distribution of droplets

(6)Numerical modeling of aerosol decontamination performance

(1)Outline of this study and schedule

(2)Evaluation of Sorption and Desorption Behavior of Methyl Iodine by Silver Doped Zeolite

[2C01-05] Fukushima NPP Accident 1

(59)Model improvements of SAMPSON code based on the previous analysis results

(60)Accident Analysis of Fukushima Daiichi Unit 1 by SAMPSON Severe Accident Code

(61)Accident Analysis of Fukushima Daiichi Unit 2 by SAMPSON Severe Accident Code

(62)Accident Analysis of Fukushima Daiichi Unit 3 by SAMPSON Severe Accident Code

(63)Validation of Debris Freezing Model in a penetration tube with GEYSER Experiment

[2C06-10] Fukushima NPP Accident 2

(64)Validation of SAMPSON/DCA creep model against OLHF experiments

(65)Validation of fragmentation and heat transfer model for molten corium using FARO

(66)Assessment of Condensation Performance and Experiment with Instrument of Simulated Isolation Condenser

(67)Experimental Investigation of Spreading Behaviors of Molten Core Debris

(68)A new heat transfer model for simulating Corium-Concrete Interaction in DSA module of SAMPSON code

[2C11-17] Fukushima NPP Accident 3

(69)Parametric Analysis of Cross-flow Effect at CCFL Condition during MCCI

(70)Development of Model for Advection and Diffusion of Eroded Concrete in Analysis of Molten Core Concrete Interaction

(71)Estimation of the FP transfer path from CAMS dose rate measurement in Fukushima Daiichi unit 2

(72)Water level and temperature transient in the suppression chamber at Unit 2

(73)Study on Unit 2 RCIC Exhaust Flow after SBO

(74)Analysis of temperature distribution in pool induced by RCIC and SRV steam discharge

(75)Leakage and massive steam release from the PCV at Unit 3

[2C18-24] Severe Accident 2

(6)Consideration of the melt diffusion model on interfaces

(7)Visualization of Interface Behavior of Simulated Molten Fluid

(10)Void fraction measurement in 5X5 non-heated rod bundle at low flow rate and low pressure conditions

(11)Pressure effect on boiling two-phase flow development in heated rod bundle under low flow rate during accidents

(2)Cooling characteristic estimation test

[2D01-05] Thermal Hydraulics Fundamental Technology 1

[2D06-09] Thermal Hydraulics Fundamental Technology 2

[3C01-04] Core Thermal Hydraulics

(11)Investigation of Flow Integrity of Fuel Assembly Components

(12)Investigation of Core Inlet Flow Characteristics

(1)Experiments with air-water two-phase flow under atmospheric pressure condition

[3C05-09] Severe Accident Analytical Method

(1)Outline of Research Project