Oral presentation

[1I01-07] Severe Accident

Wed. Mar 20, 2019 10:00 AM - 11:55 AM Room I (Common Education Bildg. 2 3F No.30)

Chair:Chiaki Kino(IAE)

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10:00 AM - 10:15 AM

[1I01] Advanced Multi-Scale Modeling and Experimental Tests on Fuel Degradation in Severe Accident Conditions (2)

(No.1) Project outline

*Yuji Nagae¹, Masaki Kurata¹ (1. Japan Atomic Energy Agency)

10:15 AM - 10:30 AM

[1I02] Advanced Multi-Scale Modeling and Experimental Tests on Fuel Degradation in Severe Accident Conditions (2)

(No.2) Development of a numerical simulation method of melt relocation behavior

*Susumu Yamashita¹, Yuji Nagae¹, Masaki Kurata¹, Hiroyuki Yoshida¹ (1. Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[1I03] Advanced Multi-Scale Modeling and Experimental Tests on Fuel Degradation in Severe Accident Conditions (2)

(No.3) Validation and Verification for the multi-physics models in JUPITER code

*Penghui Chai¹, Susumu Yamashita¹, Yuji Nagae¹, Masaki Kurata¹ (1. Japan Atomic Energy Agency)

10:45 AM - 11:00 AM

[1I04] Advanced Multi-Scale Modeling and Experimental Tests on Fuel Degradation in Severe Accident Conditions (2)

(No.4) High Temperature Interaction between UO₂ and Zr

*Noriko Shirasu¹, Akihiro Suzuki², Yuji Nagae¹, Masaki Kurata¹ (1. JAEA, 2. NFD)

11:00 AM - 11:15 AM

[1I05] Advanced Multi-Scale Modeling and Experimental Tests on Fuel Degradation in Severe Accident Conditions (2)

(No.5) Development of solidification model

*Takumi Sato Sato¹, Katsunari Oikawa², Yuji Nagae¹, Masaki Kurata¹ (1. Japan Atomic Energy Agency, 2. Tohoku university)

11:15 AM - 11:30 AM

[1I06] Fuel Damage of a Reactor Core in Severe Accident

(1) SFD 1-4 Test and Analytical Conditions

*KOJI NISHIDA¹, Toshihide Torige¹, Naoki Sano¹, Takayoshi Kusunoki¹, Michio Murase¹ (1. Institute of Nuclear Safety System, Inc.)

11:30 AM - 11:45 AM

[1I07] Fuel Damage of a Reactor Core in Severe Accident

(2) Analytical Evaluation of SFD 1-4 Test Results

*Naoki Sano¹, Koji Nishida¹, Toshihide Torige¹, Takayoshi Kusunoki¹, Michio Murase¹ (1. INSS)

Time reserved for Chair （11:45 AM - 11:55 AM）

Oral presentation

[1I08-12] Thermal hydraulic Experiments 1

Wed. Mar 20, 2019 2:45 PM - 4:05 PM Room I (Common Education Bildg. 2 3F No.30)

Chair:Tomio Okawa(UEC)

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2:45 PM - 3:00 PM

[1I08] Measurement of Void Fraction Distribution in Two-Phase Flow in a 4×4 Bundle

(3) Measurement of Void Fraction and Velocity in Steam-Water Condition

*Taku Nagatake¹, Shinichiro Uesawa¹, Ayako Ono¹, Mitsuhiko Shibata¹, Hiroyuki Yoshida¹ (1. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1I09] Measurements of Velocity Distribution in Wire Wrapped Fuel Assembly (Evaluation of Reynolds Number Dependence in 3-Pin Bundle)

*Tomoyuki HIYAMA¹, Kousuke AIZAWA¹, Masahiro NISHIMURA¹, Akikazu KURIHARA¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[1I10] Visualized observation of droplet dynamics passing through a spacer in BWR fuel subchannels

*Riichiro Okawa¹, Masahiro Furuya¹, Takahiro Arai¹, Hiroki Takiguchi¹, Tsugumasa Iiyama¹ (1. CRIEPI)

3:30 PM - 3:45 PM

[1I11] Experimental Study on Droplet-Entrainment Phenomena at the Interface of High-Speed Gas Jet into a Liquid Pool

*Taro Sugimoto¹, Shimpei Saito¹, Akiko Kaneko¹, Yutaka Abe¹, Akihiro Uchibori², Akikazu Kurihara², Takashi Takata², Hiroyuki Ohshima² (1. University of Tsukuba, 2. JAEA)

3:45 PM - 4:00 PM

[1I12] Evaluation of liquid film front bahavior during rewetting process based on visualization experiment

*DAN TRI LE¹, Yasuteru Sibamoto¹, Yuki Wada¹, Taisuke Yonomoto¹ (1. Japan Atomic Energy Agency)

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

Oral presentation

[1I13-17] Thermal hydraulic Experiments 2

Wed. Mar 20, 2019 4:05 PM - 5:25 PM Room I (Common Education Bildg. 2 3F No.30)

Chair:Masahiro Furuya(CRIEPI)

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4:05 PM - 4:20 PM

[1I13] Evaluation of Void Fraction in a Vertical Pipe under Countercurrent Flow Limitation at Upper End

*Michio Murase¹, Koji Nishida¹, Toshiya Takaki¹, Raito Goda², Takeyuki Shimamura², Akio Tomiyama² (1. Institute of Nuclear Safety System, Inc., 2. Kobe University)

4:20 PM - 4:35 PM

[1I14] Effect of L/D ratio on drag coefficient of cylinder in coaxial flow

*Tsugumasa Iiyama¹, Masahiro FURUYA¹, Kenetsu SHIRAKAWA¹, Yoshiaki MAEDA², Yoshiaki KAWA², Michihiro KOIKE², Taro Shimada³ (1. CRIEPI, 2. CERES, 3. JAPC)

4:35 PM - 4:50 PM

[1I15] Tow phase flow behavior and pressure rise phenomenon of a supersonic steam injector

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

4:50 PM - 5:05 PM

[1I16] CIGMA experiment on density stratification behavior by containment venting

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

5:05 PM - 5:20 PM

[1I17] Experimental Study to Improve Freeze Valve Performance in the Molten Salt Reactor

*Tatsuya Tokushima¹, Indarta Kuncoro Aji¹, Koji Enoki¹, Motoyasu Kinoshita^1,2, Tomio Okawa¹ (1. The University of Electro-Communications , 2. Molten Salt Laboratory Inc.)

Time reserved for Chair （5:20 PM - 5:25 PM）

Oral presentation

[2I01-05] Fukushima Daiichi

Thu. Mar 21, 2019 9:30 AM - 10:45 AM Room I (Common Education Bildg. 2 3F No.30)

Chair:Koji Nishida(INSS)

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9:30 AM - 9:45 AM

[2I01] Evaluation of Fission Products Released during the NPP Severe Accident

25. FP Behavior Analysis in the PCV of the Unit 1-3 with SAMPSON Code

*Hidetoshi Karasawa¹, Shunsuke Uchida¹, Chiaki Kino¹, Marco Pellegrini¹, Masanori Naito¹ (1. IAE)

9:45 AM - 10:00 AM

[2I02] Evaluation of Fission Products Released during the NPP Severe Accident

26. Validation of the analytical results on FP behavior in the Units 1- 3 by comparing with CAMS data

*Shunsuke Uchida¹, Hidetoshi Karasawa¹, Chiaki Kino¹, Marco Pellegrini¹, Masanori Naitoh¹ (1. IAE)

10:00 AM - 10:15 AM

[2I03] Development of long term FP behavior analysis method for TEPCO's Fukushima Daiichi Nuclear Power Plants

*Chiaki Kino¹, Hidetoshi Karasawa^1,2, Shunsuke Uchida^1,2, Shunichiro Nishioka², Masahiko Ohsaka² (1. IAE, 2. JAEA)

10:15 AM - 10:30 AM

[2I04] Estimation of plant condition of Fukushima Daiichi Nuclear Power Station

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

*Masashi Himi¹, Naotoshi Tominaga¹, Yoko Yamane¹, Keigo Murata¹, Koichi Nakamura² (1. Advancesoft co., 2. CRIEPI)

10:30 AM - 10:45 AM

[2I05] Sensitivity Analyses on Hydrogen Explosion at TEPCO's Fukushima Daiichi Nuclear Power Plant Unit 4

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

Oral presentation

[2I06-11] Phase Change

Thu. Mar 21, 2019 10:45 AM - 12:15 PM Room I (Common Education Bildg. 2 3F No.30)

Chair:Hiroyuki Yoshida(JAEA)

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10:45 AM - 11:00 AM

[2I06] Experimental Studies on Heat Transfer and Flow Characteristics in Microchannels

*Kazuya Goto¹, Kentaro Tanaka¹, Nariatsu Hujino¹, Tino Sawadi¹, Tatsuya Matsumoto¹, Wei Liu¹, Koji Morita¹ (1. Kyushu-University)

11:00 AM - 11:15 AM

[2I07] A study of copper oxidation for critical heat flux in downward-faced flow boiling

*Kai Wang¹, Koji Okamoto ², Nejdet Erkan¹ (1. Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 2. Nuclear Professional School, The University of Tokyo)

11:15 AM - 11:30 AM

[2I08] Experimental analysis of clad rewetting in downward water/air flow

*Marco Pellegrini¹, Tomio Okawa², Masanori Naitoh¹ (1. The Institute of Applied Energy, 2. University of Electrocommunications)

11:30 AM - 11:45 AM

[2I09] Effect of permitivity on microwave heating characteristics

*Shouhei Kobayashi¹, Shunya Fujita¹, Akiko Kaneko¹, Yutaka Abe¹, Tomohisa Yuasa¹, Tomoomi Segawa², Yoshiyuki Kato², Koichi kawaguchi², Katsunori ishii² (1. TSUKUBA Univ., 2. Japan Atomic Energy Agency)

11:45 AM - 12:00 PM

[2I10] Analysis of the Supersonic Steam Injector Performance and Two-phase Flow Modeling

*Shuichiro Miwa¹, Nozomu Akiyama¹ (1. Hokkaido University)

12:00 PM - 12:15 PM

[2I11] Study on dependency of pressure on boiling behavior on vertical heating surface in pool boiling

*Ayako Ono¹, Shinichiro Uesawa¹, Mitsuhiko Shibata¹, Hiroyuki Yoshida¹, Yasuo Koizumi¹ (1. Japan Atomic Energy Agency)

Oral presentation

[2I12-14] Debris Cooling Behavior

Thu. Mar 21, 2019 3:15 PM - 4:00 PM Room I (Common Education Bildg. 2 3F No.30)

Chair:Koji Morita(Kyushu Univ.)

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3:15 PM - 3:30 PM

[2I12] A status of evaluation methods and experimental researches for formation and coolability of debris bed

*Akitoshi Hotta¹, Miyuki Akiba¹, Retsu Kojo¹, Takeshi Nishimura¹ (1. Nuclear Regulation Authority JAPAN)

3:30 PM - 3:45 PM

[2I13] Experimental study on remelting of multicomponent debris and debris-structure interactions

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

3:45 PM - 4:00 PM

[2I14] Study on Boiling Heat Transfer Characteristics in Debris Beds

3rd:Effects of Volumetric Heated Rate and Bed Height on Critical Heat Flux

*Taira Kawakami¹, Keishi Sakurada¹, Hiroto Sakashita¹, Ayako Ono², Hiroyuki Yoshida² (1. Laboratory of Nuclear System Safety Engineering, Division of Energy and Environmental Systems, Hokkaido University, 2. Japan Atomic Energy Agency)

Oral presentation

[2I15-17] Thermal Hydaulics at Accident

Thu. Mar 21, 2019 4:00 PM - 4:45 PM Room I (Common Education Bildg. 2 3F No.30)

Chair:Yasuteru Sibamoto(JAEA)

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4:00 PM - 4:15 PM

[2I15] 3D-CFD and FEM Based Deterministic PTS Analysis for Optimizing RPV Maintenance Strategy

*Xiaoyong RUAN¹, Toshiki Nakasuji¹, Kazunori Morishita¹ (1. Kyoto University)

4:15 PM - 4:30 PM

[2I16] Study on Air Ingress Phenomena during a Depressurization Accident of VHTR

(4) Air ingress process during a double coaxial pipe rupture

*Tetsuaki Takeda¹, Naoki Saito¹ (1. University of Yamanashi)

4:30 PM - 4:45 PM

[2I17] Loss of Cooling System and Loss of Coolant Accident Progression Analysis for Spent Fuel Pools

Accident Progression Analysis using Oxidation Models under Air-Steam Mixture Environments

*Retsu Kojo¹, Akitoshi Hotta¹ (1. S/NRA/R)

Oral presentation

[2I18-22] Thermal hydaulic Numerical Simulation

Thu. Mar 21, 2019 4:45 PM - 6:00 PM Room I (Common Education Bildg. 2 3F No.30)

Chair:Kei Ito(Kyoto Univ.)

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4:45 PM - 5:00 PM

[2I18] Deepening Understanding of Ex-Vessel Corium Behavior by Multi-Physics Modeling

(6) Overview and Progress on Spreading Analysis by MPS Method(3)

*Akifumi Yamaji¹, Masahiro Furuya², Yuji Ohishi³, Jubaidah¹, Guangtao Duan¹ (1. Waseda University, 2. Central Research Institute of Electric Power Industry, 3. Osaka University)

5:00 PM - 5:15 PM

[2I19] Analyses of LSTF experiment and PWR plant for loss of coolant accident

*Tadashi Watanabe¹, Masahiro Ishigaki¹, Jinya Katsuyama² (1. Univ. Fukui, 2. JAEA)

5:15 PM - 5:30 PM

[2I20] Subchannel analysis of boiling two-phase flow in a rod bundle at high pressure and low flow rate

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

5:30 PM - 5:45 PM

[2I21] CFD analysis of hydrogen flame propagation with burning velocity models.

*Kosuke Motegi¹, Trianti Nuri¹, Toshinori Matsumoto¹, Tomoyuki Sugiyama¹, Yu Maruyama¹ (1. JAEA)

5:45 PM - 6:00 PM

[2I22] Experiments and numerical analysis on the geysering phenomenon in vertical pipe.

*Yutaro Hakozaki¹, Kunihito Matsumura¹ (1. Ibaraki Univ)

Oral presentation

[3I01-06] Scrubbing and Aerosol

Fri. Mar 22, 2019 10:15 AM - 11:55 AM Room I (Common Education Bildg. 2 3F No.30)

Chair:Yasushi Saito(Kyoto Univ.)

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10:15 AM - 10:30 AM

[3I01] Effect of Steam Condensation on Decontamination during Pool Scrubbing

*Yuki Nakamura¹, Kota Fujiwara¹, Kikuchi Wataru¹, Shimpei Saito¹, Tomohisa Yuasa¹, Akiko Kaneko¹, Yutaka Abe¹ (1. University of Tsukuba)

10:30 AM - 10:45 AM

[3I02] Measurement of Aerosol Decontamination Behavior from a Single Bubble during Pool Scrubbing

*Kota Fujiwara¹, Yuki Nakamura¹, Wataru Kikuchi¹, Shimpei Saito¹, Tomohisa Yuasa¹, Akiko Kaneko¹, Yutaka Abe¹ (1. University of Tsukuba)

10:45 AM - 11:00 AM

[3I03] Evaluation of the Removal Properties of Organic Iodide by an AgNO₃Solution

*Taizo Kanai¹, Masahiro Furuya¹, Satoshi Nishimira¹ (1. CRIEPI)

11:00 AM - 11:15 AM

[3I04] The Influence of Gas Species on Gas-Liquid Two-Phase Flow

(1) A Comparison of Void Behaviours in Helium Gas and Nitrogen Gas

*Miki Saito¹, Taizo Kanai¹, Satoshi Nishimura¹, Yoshihisa Nishi¹ (1. Central Research Institute of Electric Power Industry)

11:15 AM - 11:30 AM

[3I05] Development of the Evaluation Method for the Aerosol Particle Deposition Amounts in the Containment Vessel and the Reactor Building

(6)Investigation of Aerosol Particle Deposition Behavior with Direct Observation of Particle Behavior

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

11:30 AM - 11:45 AM

[3I06] Development of Numerical Simulation Method for Aerosol Particle Behavior in Two-Phase Flow

(1) Outline of Simulation Method and Results of Preliminary Simulation

*Hiroyuki Yoshida¹, Shinichiro Uesawa¹ (1. Japan Atomic Energy Agency)

Time reserved for Chair （11:45 AM - 11:55 AM）

Oral presentation

[3I07-11] Fast Reactor Thermal Hydraulics

Fri. Mar 22, 2019 2:45 PM - 4:10 PM Room I (Common Education Bildg. 2 3F No.30)

Chair:Tohru Suzuki(Tokyo City Univ.)

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2:45 PM - 3:00 PM

[3I07] Elucidation and Control of Liquid Sodium Multiphase Flow Dynamics: Visualization Measurement of Gas-Liquid interface

*Yuta Akimoto¹, Takeshi Fukuda¹ (1. Osaka University)

3:00 PM - 3:15 PM

[3I08] Development of reactor vessel thermal hydraulic evaluation method under natural circulation decay heat removal conditions in sodium-cooled fast reactor

(1) Applicability of subchannel based CFD analysis method using porous body model

*Erina HAMASE¹, Yasutomo Imai², Norihiro KIKUCHI ¹, Norihiro DODA¹, Masaaki TANAKA¹ (1. JAEA, 2. NDD)

3:15 PM - 3:30 PM

[3I09] Study on Cooling Process of Decay Heat Removal Systems in a Reactor Vessel of Sodium-cooled fast Reactor by Scaled Water Experiments

(2)PIV measurements of flow field in a reactor vessel simulating operation of dipped-type DHX

*Mitsuyo Tsuji¹, Ayako Ono¹, Kosuke Aizawa¹, Jun Kobayashi¹, Akikazu Kurihara¹, Yasuhiro Miyake² (1. JAEA, 2. NDD)

3:30 PM - 3:45 PM

[3I10] Consideration on Heat Transfer Coefficient of Liquid Metal in Tube Flow

*Hiroyasu MOCHIZUKI¹ (1. Tokyo Institute of Technology)

3:45 PM - 4:00 PM

[3I11] study on droplet generation during upward liquid jet collision onto ceiling surface

*yi zhan¹, Kiyotaka Maruyama¹, Yusuke Kuwata¹, Koji Enoki¹, Tomio Okawa¹, Mitsuhiro Aoyagi², Takashi Takata² (1. The University of Electro-Communications, 2. Japan Atomic Energy Agency)

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

Sessions

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

[1I01-07] Severe Accident

(No.1) Project outline

(No.2) Development of a numerical simulation method of melt relocation behavior

(No.3) Validation and Verification for the multi-physics models in JUPITER code

(No.4) High Temperature Interaction between UO2 and Zr

(No.5) Development of solidification model

(1) SFD 1-4 Test and Analytical Conditions

(2) Analytical Evaluation of SFD 1-4 Test Results

[1I08-12] Thermal hydraulic Experiments 1

(3) Measurement of Void Fraction and Velocity in Steam-Water Condition

[1I13-17] Thermal hydraulic Experiments 2

[2I01-05] Fukushima Daiichi

25. FP Behavior Analysis in the PCV of the Unit 1-3 with SAMPSON Code

26. Validation of the analytical results on FP behavior in the Units 1- 3 by comparing with CAMS data

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

[2I06-11] Phase Change

[2I12-14] Debris Cooling Behavior

3rd:Effects of Volumetric Heated Rate and Bed Height on Critical Heat Flux

[2I15-17] Thermal Hydaulics at Accident

(4) Air ingress process during a double coaxial pipe rupture

Accident Progression Analysis using Oxidation Models under Air-Steam Mixture Environments

[2I18-22] Thermal hydaulic Numerical Simulation

(6) Overview and Progress on Spreading Analysis by MPS Method(3)

[3I01-06] Scrubbing and Aerosol

(1) A Comparison of Void Behaviours in Helium Gas and Nitrogen Gas

(6)Investigation of Aerosol Particle Deposition Behavior with Direct Observation of Particle Behavior

(1) Outline of Simulation Method and Results of Preliminary Simulation

[3I07-11] Fast Reactor Thermal Hydraulics

(1) Applicability of subchannel based CFD analysis method using porous body model

(2)PIV measurements of flow field in a reactor vessel simulating operation of dipped-type DHX

Authentication

(No.4) High Temperature Interaction between UO₂ and Zr