*Shohei Kobayashi¹, Yutaka Abe¹, Akiko Kaneko¹, Akihiro Futsuta¹, Kouta Fujiwara¹, Tomoomi Segawa², Koichi Kawaguchi², katsunori ishii², Takeji Kaito² (1. Univ. of Tsukuba , 2. JAEA)

3:00 PM - 3:15 PM

[1F08] Study on improvement of PWR thermal efficiency by using Economizers in Steam Generators

*Amane Kato¹, Shinichi Morooka¹ (1. WASEDA Univ.)

3:15 PM - 3:30 PM

[1F09] Reverse flow to the branch line of a mixing tee pipe and influence of temperature difference

*Yoichi Utanohara¹, Koji Miyoshi¹, Masayuki Kamaya¹ (1. INSS)

Time reserved for Chair （3:30 PM - 3:35 PM）

Oral presentation

[1F10-14] Molten Debris Behavior 1

Wed. Sep 11, 2019 3:35 PM - 4:55 PM Room F (Common Education Bildg. 2F C21)

Chair:Kei Ito(Kyoto Univ.)

+Add all to schedule

3:35 PM - 3:50 PM

[1F10] Modeling of anisotropic molten debris spreading and simulation of ECOKATS test

*Akitoshi Hotta¹, Miyuki Akiba¹, Akinobu Morita¹ (1. Nuclear Regulation Authority)

3:50 PM - 4:05 PM

[1F11] Development of molten core spreading model at severe accident

*Nobuhide Hara¹, Takuo Oda¹, Yoshiteru Komuro¹, Hironori Noguchi¹, Kouichi Tanimoto¹, Satoru Kamohara¹, Hiroshi Goda¹ (1. MHI)

4:05 PM - 4:20 PM

[1F12] Study for Evaluation of Spreading Behavior of Molten Core Free Fall under Dry Condition

*Yuta Watanabe¹, Yasunori Yamamoto¹, Tomomasa Ito¹ (1. Hokkaido University Graduate School of Engineering)

4:20 PM - 4:35 PM

[1F13] Experimental study on liquid melt spreding in water pool under devere accident

*Miyuki Akiba¹, Akitoshi Hotta¹, Akinobu Morita¹ (1. Nuclear Regulation Authority)

4:35 PM - 4:50 PM

[1F14] Study on Boiling Heat Transfer Characteristics in Debris Beds

4th:Visualization of boiling behaviors on a heating surface

*Taira Kawakami¹, Hiroto Sakashita¹, Ayako Ono², Hiroyuki Yoshida² (1. Hokkaido Univ., 2. JAEA)

Time reserved for Chair （4:50 PM - 4:55 PM）

Oral presentation

[1F15-18] Molten Debris Behavior 2

Wed. Sep 11, 2019 4:55 PM - 6:00 PM Room F (Common Education Bildg. 2F C21)

Chair:Hiroyuki Yoshida(JAEA)

+Add all to schedule

4:55 PM - 5:10 PM

[1F15] Development of Steam Explosion Retardant with Carbonated Water

*Masahiro Furuya¹, Takahiro Arai¹, Tsugumasa Iiyama¹, Riichiro Okawa¹, Atsushi Ui¹ (1. CRIEPI)

5:10 PM - 5:25 PM

[1F16] Development of three-dimensional Molten Core Concrete Interaction analysis method

*Akinobu Morita¹, Akitoshi Hotta¹ (1. Nuclear Regulation Authority)

5:25 PM - 5:40 PM

[1F17] Designing melting core cooling system for existing ABWR

*Akira Kirihara¹, Shinichi Morooka¹ (1. WASEDA University)

5:40 PM - 5:55 PM

[1F18] Accuracy improvement of natural circulation flow rate prediction by void fraction correlation modification

*Shusuke Yoshimura¹, Shinichi Morooka¹ (1. Waseda University, Cooperating Major in Nuclear Energy)

Time reserved for Chair （5:55 PM - 6:00 PM）

Oral presentation

[2F01-04] Gas-Liquid Two-Phase Flow

Thu. Sep 12, 2019 9:30 AM - 10:35 AM Room F (Common Education Bildg. 2F C21)

Chair:Tomio Okawa(UEC)

+Add all to schedule

9:30 AM - 9:45 AM

[2F01] Interfacial Friction in Vertical Pipes under Countercurrent Flows

(1)Flooding at the Bottom End

*Naoki Sano¹, Michio Murase¹, Toshiya Takaki¹, Koji Nishida¹, Raito Goda², Akio Tomiyama² (1. INSS, 2. Kobe Univ.)

9:45 AM - 10:00 AM

[2F02] Interfacial Friction in Vertical Pipes under Countercurrent Flows

(2)Flooding at the Top End

*Michio Murase¹, Toshiya Takaki¹, Koji Nishida¹, Akio Tomiyama² (1. Institute of Nuclear safety System, Inc., 2. Kobe University)

10:00 AM - 10:15 AM

[2F03] Numerical Simulation of Bubble Behavior in PWR Rod Bundle by Interface Tracking Method

*Hiroyuki Yoshida¹, Ayako Ono¹, Masaaki Okano², Yasushi Makino² (1. JAEA, 2. NDC)

10:15 AM - 10:30 AM

[2F04] Large-scale simulation on two-phase flow in the fuel assemblies of LWR by the mechanistically based method

*Ayako Ono¹, Susumu Yamashita¹, Takayuki Suzuki¹, Hiroyuki Yoshida¹ (1. JAEA)

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

Oral presentation

[2F05-09] Fast Reactor Thermal Hydraulics 1

Thu. Sep 12, 2019 10:35 AM - 12:00 PM Room F (Common Education Bildg. 2F C21)

Chair:Masahiro Furuya(CRIEPI)

+Add all to schedule

10:35 AM - 10:50 AM

[2F05] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(10)Development of coupling method for basic modules in multi-level simulation system

*norihiro doda¹, kenji yokoyama¹, masaaki tanaka¹, takashi takata¹, hiroyuki ohshima¹ (1. JAEA)

10:50 AM - 11:05 AM

[2F06] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(11)Development of physical models related to severe accident analysis

*Mitsuhiro Aoyagi¹, Masateru Sonehara¹, Akihiro Uchibori¹, Takashi Takata¹, Hiroyuki Ohshima¹ (1. JAEA)

11:05 AM - 11:20 AM

[2F07] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(12)Fundamental experiment on sodium-concrete reaction (second report)

*Shin Kikuchi¹, Nobuyoshi Koga², Akikazu Kurihara¹, Takashi Takata¹, Hiroyuki Ohshima¹ (1. JAEA, 2. Hiroshima Univ.)

11:20 AM - 11:35 AM

[2F08] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(13)Experimental study on aerosol transport behavior using the multi-cell facility

*Ryota Umeda¹, Akikazu Kurihara¹, Shin Kikuchi¹, Norihiro Kikuchi¹, Takata Takashi¹, Ohshima Hiroyuki¹ (1. JAEA)

11:35 AM - 11:50 AM

[2F09] Coupled Neutronics and Thermalhydraulics of Molten Salt Fast Reactor

*Hiroyasu MOCHIZUKI^1,3, Michio YAMAWAKI^2,3 (1. Tokyo Institute of Technology, 2. The University of Tokyo, 3. BERD)

Time reserved for Chair （11:50 AM - 12:00 PM）

Oral presentation

[2F10-14] Fast Reactor Thermal Hydraulics 2

Thu. Sep 12, 2019 2:45 PM - 4:10 PM Room F (Common Education Bildg. 2F C21)

Chair:Yoichi Utanohara(INSS)

+Add all to schedule

2:45 PM - 3:00 PM

[2F10] Basic Research on Visualization Measurement of Dynamic Behavior of Gas-Liquid Interface in Liquid Sodium Multiphase Flow

*Yuta Akimoto¹, Yosuke Ogino¹, Takeshi Fukuda¹ (1. Osaka Univ.)

3:00 PM - 3:15 PM

[2F11] Evaluation of Target-wastage for Steam Generator Tubes of Sodium-cooled Fast Reactor

Applicability of local wastage influencing factors to conventional correlation

*Akikazu Kurihara¹, Ryota Umeda¹ (1. JAEA)

3:15 PM - 3:30 PM

[2F12] Behavior of Entrained Droplets in a High-Speed Gas Jet into a Liquid Pool

*Taro Sugimoto¹, Akiko Kaneko¹, Yutaka Abe¹, Akihiro Uchibori², Akikazu Kurihara², Takashi Takata², Hiroyuki Ohshima² (1. Univ. of Tsukuba, 2. JAEA)

3:30 PM - 3:45 PM

[2F13] Study on coolant behavior in damaged core of sodium-cooled fast reactor

(5)Effect of pipe and particle sizes on pressure drop in simulated debris bed

*Akinari Ishikuro¹, Daisuke Ito¹, Kei Ito¹, Yasushi Saito¹, Yuya Imaizumi², Kenichi Matsuba², Kenji Kamiyama² (1. Kyoto Univ., 2. JAEA)

3:45 PM - 4:00 PM

[2F14] Solidification behavior of single molten droplet falling through coolant

*Kota Kawasaki¹, Akiko Kaneko¹, Yutaka Abe¹, Kazuya Koyama² (1. University of Tsukuba, 2. Mitsubishi FBR Systems, Inc.)

Time reserved for Chair （4:00 PM - 4:10 PM）

Oral presentation

[2F15-20] Emergent Equipment

Thu. Sep 12, 2019 4:10 PM - 5:45 PM Room F (Common Education Bildg. 2F C21)

Chair:Michio Murase(INSS)

+Add all to schedule

4:10 PM - 4:25 PM

[2F15] Study to evaluate operating limit of isolation condenser during hydrogen injection

*Yasunori YAMAMOTO¹, Masayoshi MORI¹ (1. Hokkaido University)

4:25 PM - 4:40 PM

[2F16] Effect of non-condensable gas on flow resistance of isolation condenser

*Masayoshi Mori¹, Yasunori Yamamoto¹ (1. Hokkaido University)

4:40 PM - 4:55 PM

[2F17] A passive method for solving thermal stratification of spent fuel pools -Evaluation by flow visualization experiment-

*Katsuki Ochiai¹, Shinichi Morooka¹ (1. Waseda Univ.)

4:55 PM - 5:10 PM

[2F18] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

Numerical Simulation of Spray Cooling Experiment by 4x4 Simulated Fuel Bundle

Taku Nagatake¹, *Hiroyuki Yoshida¹, Yoshiyuki Nemoto¹, Yoshiyuki Kaji¹ (1. JAEA)

5:10 PM - 5:25 PM

[2F19] Prediction of the Thermal-hydraulic and Operative Characteristics of Steam Injector

*Yuki HARA¹, Yuhei TERAMACHI¹, Shuichiro MIWA¹ (1. HOKKAIDO Univ.)

5:25 PM - 5:40 PM

[2F20] Flow structure related to operating mechanism of supersonic steam injector

*Yuki Kamata¹, Eita Koyama¹, Akiko Kaneko¹, Yutaka Abe¹ (1. Univ. of Tsukuba)

Time reserved for Chair （5:40 PM - 5:45 PM）

Oral presentation

[3F01-04] Scrubbing and Aerosol

Fri. Sep 13, 2019 9:45 AM - 10:50 AM Room F (Common Education Bildg. 2F C21)

Chair:Tomonori IHARA(TUMSAT)

+Add all to schedule

9:45 AM - 10:00 AM

[3F01] Transition of bubble diameter and decontamination effect in gas-liquid two-phase flow during pool scrubbing

*Yuki Nakamura¹, Kota Fujiwara¹, Kohei Yoshida¹, Akiko Kaneko¹, Yutaka Abe¹ (1. Univ. of Tsukuba)

10:00 AM - 10:15 AM

[3F02] Aerosol Decontamination Behavior from a Single Bubble during Pool Scrubbing

*Kota Fujiwara¹, Yuki Nakamura¹, Kohei Yoshida¹, Akiko Kaneko¹, Yutaka Abe¹ (1. University of Tsukuba)

10:15 AM - 10:30 AM

[3F03] Development of the Evaluation Method for the Aerosol Particle Deposition Amounts in the Containment Vessel and the Reactor Building

(7)Observation of Aerosol Particle Behavior in Narrow Channel

*Shinichiro Uesawa¹, Naoya Miyahara¹, Naoki Horiguchi¹, Hiroyuki Yoshida¹, Masahiko Osaka¹ (1. JAEA)

10:30 AM - 10:45 AM

[3F04] The Influence of Gas Species on Gas-Liquid Two-Phase Flow

(2)Single-Bubble Behaviours of Helium Gas and Nitrogen Gas

*Miki Saito¹, Taizo Kanai¹, Satoshi Nishimura¹, Yoshihisa Nishi¹ (1. CRIEPI)

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

Oral presentation

[3F05-08] Fukushima Daiichi Accident

Fri. Sep 13, 2019 10:50 AM - 12:00 PM Room F (Common Education Bildg. 2F C21)

Chair:Chiaki Kino(IAE)

+Add all to schedule

10:50 AM - 11:05 AM

[3F05] Estimation of plant condition of Fukushima Daiichi Nuclear Power Station

(2)Analysis of measured values of released radionuclide into atmosphere

*Masashi himi Himi¹, Naotoshi Tominaga¹, Koichi Nakamura² (1. AdvanceSoft Co., 2. CRIEPI)

11:05 AM - 11:20 AM

[3F06] Estimation of plant condition of Fukushima Daiichi Nuclear Power Station

(3)Estimation of Core Damage Process

*Naotoshi Tominaga¹, Masashi Himi¹, Koichi Nakamura² (1. Advancesoft, 2. Central Research Institute of Electric Power Industry)

11:20 AM - 11:35 AM

[3F07] Inverse analysis of steam and hydrogen generation history of Fukushima Daiichi Nuclear Power Plant unit 3

*Shinji Yoshikawa¹, Ikken Sato¹ (1. Japan Atomic Energy Agency)

11:35 AM - 11:50 AM

[3F08] Fukushima-Daiichi Plant Data Analysis Focusing on Core Material Relocation to Pedestal

Estimation of core-material-relocation behavior to pedestal based on availabe data such as pressure, water level and radiation dose rate measurements

*IKKEN SATO¹, Shinji Yoshikawa¹ (1. Japan Atomic Energy Agency)

Time reserved for Chair （11:50 AM - 12:00 PM）

Oral presentation

[3F09-14] Severe Accident Analysis

Fri. Sep 13, 2019 2:45 PM - 4:20 PM Room F (Common Education Bildg. 2F C21)

Chair:Atsushi Ui(CRIEPI)

+Add all to schedule

2:45 PM - 3:00 PM

[3F09] Severe accident analysis of 2 loop PWR by MAAP 5.01

Part 1: Construction of analysis model and selection of accident sequence

*Genta Aoki¹, Taku Shibata¹, Masaaki Satake², Satoshi Nishimura², Yoshihisa Nishi² (1. HEPCO, 2. CRIEPI)

3:00 PM - 3:15 PM

[3F10] Severe accident analysis of 2 loop PWR by MAAP 5.01

Part 2: Discretization effect of containment vessel model on the TMLB 'and ADCB' sequences

*Masaaki Satake¹, Satoshi Nishimura¹, Yoshihisa Nishi¹, Genta Aoki², Taku Shibata² (1. CRIEPI, 2. HEPCO)

3:15 PM - 3:30 PM

[3F11] SAMPSON PWR Validation by TMI-2 Accident

*Alexandre Nakata Ezzidi¹, Atsuo Takahashi², Masanori Naitoh¹ (1. IAE/NUPEC, 2. AdvanceSoft)

3:30 PM - 3:45 PM

[3F12] CIGMA experiment on thermal hydraulic behavior in a containment vessel during a severe accident

(1)Experimental study on density stratification break-up by an outer cooling

*Satoshi Abe¹, Masahiro Ishigaki¹, Yasuteru Sibamoto¹, Taisuke Yonomoto¹ (1. JAEA)

3:45 PM - 4:00 PM

[3F13] CIGMA experiment on thermal hydraulic behavior in a containment vessel during a severe accident

(2)Verification of Capability of Gas Injection Nozzle

*Hiroki Watanabe¹, Satoshi Abe², Masahiro Ishigaki², Yasuteru Sibamoto² (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority(S/NRA/R), 2. Japan Atomic Energy Agency)

4:00 PM - 4:15 PM

[3F14] CIGMA experiment on thermal hydraulic behavior in a containment vessel during a severe accident

(3)Numerical Simulation of a Buoyant Heated Air Jet in Large Containment Vessel CIGMA with Outer Surface Cooling

*Ari Hamdani¹, Satoshi Abe¹, Masahiro Ishigaki¹, Yasuteru Sibamoto¹, Taisuke Yonomoto¹ (1. JAEA)

Time reserved for Chair （4:15 PM - 4:20 PM）

Sessions

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

[1F01-06] Thermal Hydraulics Experiment/Analysis 1

(1)Large-scale unsteady flow simulation by JUPITER

[1F07-09] Thermal Hydraulics Experiment/Analysis 2

[1F10-14] Molten Debris Behavior 1

4th:Visualization of boiling behaviors on a heating surface

[1F15-18] Molten Debris Behavior 2

[2F01-04] Gas-Liquid Two-Phase Flow

(1)Flooding at the Bottom End

(2)Flooding at the Top End

[2F05-09] Fast Reactor Thermal Hydraulics 1

(10)Development of coupling method for basic modules in multi-level simulation system

(11)Development of physical models related to severe accident analysis

(12)Fundamental experiment on sodium-concrete reaction (second report)

(13)Experimental study on aerosol transport behavior using the multi-cell facility

[2F10-14] Fast Reactor Thermal Hydraulics 2

Applicability of local wastage influencing factors to conventional correlation

(5)Effect of pipe and particle sizes on pressure drop in simulated debris bed

[2F15-20] Emergent Equipment

Numerical Simulation of Spray Cooling Experiment by 4x4 Simulated Fuel Bundle

[3F01-04] Scrubbing and Aerosol

(7)Observation of Aerosol Particle Behavior in Narrow Channel

(2)Single-Bubble Behaviours of Helium Gas and Nitrogen Gas

[3F05-08] Fukushima Daiichi Accident

(2)Analysis of measured values of released radionuclide into atmosphere

(3)Estimation of Core Damage Process

Estimation of core-material-relocation behavior to pedestal based on availabe data such as pressure, water level and radiation dose rate measurements

[3F09-14] Severe Accident Analysis

Part 1: Construction of analysis model and selection of accident sequence

Part 2: Discretization effect of containment vessel model on the TMLB 'and ADCB' sequences

(1)Experimental study on density stratification break-up by an outer cooling

(2)Verification of Capability of Gas Injection Nozzle

(3)Numerical Simulation of a Buoyant Heated Air Jet in Large Containment Vessel CIGMA with Outer Surface Cooling

Authentication