Oral presentation

[1B01-07] Thermal-hydraulics of Fast Reactor

Mon. Mar 26, 2018 10:05 AM - 12:00 PM Room B (C1-311 -C1 Building)

Chair: Tohru Suzuki (Tokyo City Univ.)

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10:05 AM - 10:20 AM

[1B01] Validation of three-dimensional finite volume particle method for simulations of two-liquid mixture flow behavior

*Masatsugu Kato¹, Ryusei Ogawa¹, Kanji Funakoshi¹, Xiaoxing Liu¹, Tatsuya Matsumoto¹, Wei Liu¹, Koji Morita¹, Kenji Kamiyama² (1. Kyushu Univ., 2. Japan Atomic Energy Agency)

10:20 AM - 10:35 AM

[1B02] Study on coolant behavior in damaged core of sodium-cooled fast reactor

(2)Design for a sodium two-phase flow experiment with boiling in a simulated debris

*Mitsuhiro Aoyagi¹, Ken-ichi Matsuba¹, Kenji Kamiyama¹, Daisuke Ito², Kei Ito², Saito Yasushi² (1. JAEA, 2. Kyoto Univ.)

10:35 AM - 10:50 AM

[1B03] Study on coolant behavior in damaged core of sodium-cooled fast reactor

(3)Measurement of air-water two phase pressure drop in a simulated debris bed

*Tatsuya Kurisaki¹, Daisuke Ito², Kei Ito², Yasushi Saito², Mitsuhiro Aoyagi³, Kennichi Matsuba³, Kenji Kamiyama³ (1. Kyoto Grad. Sch. Energy Science, 2. KURRI, 3. JAEA)

10:50 AM - 11:05 AM

[1B04] Droplet-Entrainment Behavior in a High-Speed Gas Jet into a Liquid Pool

*Taro Sugimoto¹, Shimpei Saito¹, Akiko Kaneko¹, Yutaka Abe¹, Akihiro Uchibori², Hiroyuki Ohshima² (1. Univ. of Tsukuba, 2. JAEA)

11:05 AM - 11:20 AM

[1B05] Effect of viscosity on liquid jet impact on solid surface

*Yusuke Kuwata¹, Yi Zhan¹, Koji Enoki¹, Tomio Okawa¹, Mitsuhiro Aoyagi², Takashi Takata² (1. The University of Electro-Communications, 2. Japan Atomic Energy Agency)

11:20 AM - 11:35 AM

[1B06] Study on gas entrainment from unsteady drifting vortexes on liquid free surface

(1)Observation of gas entrainment by PIV measurement

*Yuichiro Kikuchi¹, Yota Takei¹, Moe Hirakawa¹, Takaaki Sakai¹, Masaaki Tanaka², Hiroyuki Ohshima² (1. Tokai Univ, 2. JAEA)

11:35 AM - 11:50 AM

[1B07] Study on gas entrainment from unsteady drifting vortexes on liquid free surface

(2)Evaluation of gas entrainment by CFD analysis

*Moe Hirakawa¹, Yuichiro Kikuchi¹, Takaaki Sakai¹, Masaaki Tanaka², Hiroyuki Ohshima² (1. Tokai Univ., 2. JAEA)

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

Oral presentation

[1B08-14] Boiling and Condensation

Mon. Mar 26, 2018 2:45 PM - 4:40 PM Room B (C1-311 -C1 Building)

Chair: Masahiro Furuya (CRIEPI)

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2:45 PM - 3:00 PM

[1B08] Study on Boilling Heat Transfer Characteristics in Debris Beds

1st: Dryout Heat Flux for Bottom Heated Debris Beds

*Keishi Sakurada¹, Taira Kawakami¹, Hiroto Sakashita¹, Ayako Ono², Hiroyuki Yoshida² (1. Hokkaido University, 2. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1B09] The Effect of Honeycomb Porous Plate on Critical Heat Flux in Saturated Pool Boiling of Artificial Seawater

*Kousuke Imanishi¹, Shoji Mori¹, Wilton Fogaça², Kunito Okuyama¹ (1. Yokohama National University, 2. University of São Paulo)

3:15 PM - 3:30 PM

[1B10] Mechanism of Flashing Phenomena in Microwave Heating

*Shunya FUJITA¹, Yutaka ABE¹, Akiko KANEKO¹, Tomohisa YUASA¹, Tomoomi SEGAWA², Yoshikazu YAMADA², Yoshiyuki KATO², Katsunori ISHII² (1. University of Tsukuba, 2. Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[1B11] OSV generating mechanism in subcooled flow boiling for low pressure conditions

*Ohori Hiroki¹, Sakamoto Shintaro¹, Okawa Tomio¹, Enoki Koji¹ (1. The University of Electro-Communications)

3:45 PM - 4:00 PM

[1B12] Mechanism of CHF during Flow Boiling of Subcooled Water in a Pt Circular Tube at High Liquid Reynolds Number

(2)3 mm inner diameter and 100 mm heated length

*Koichi Hata¹, Katsuya Fukuda¹, Suguru Masuzaki² (1. Graduate School of Maritime Sciences, Kobe University , 2. National Institute for Fusion Science )

4:00 PM - 4:15 PM

[1B13] Study on behavior of bubbles and process of coalescence by using CMFD simulation code TPFIT

(1)Effect of pressure on the behavior of bubbles and process of coalescence

*Ayako Ono¹, Takayuki Suzuki¹, Hiroyuki Yoshida¹ (1. Japan Atomic Energy Agency)

4:15 PM - 4:30 PM

[1B14] CHF and Near-Wall Boiling Behaviors in Saturated and Subcooled Pool Boiling on Vertical Surface

*Tsubasa Yamamoto¹, Katsuya Udagawa¹, Hiroto Sakashita¹ (1. Hokkaido University)

Time reserved for Chair （4:30 PM - 4:40 PM）

Oral presentation

[1B15-19] Fission Product Behavior

Mon. Mar 26, 2018 4:40 PM - 6:00 PM Room B (C1-311 -C1 Building)

Chair: Ayako Ono (JAEA)

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4:40 PM - 4:55 PM

[1B15] Development of the Evaluation Method for the Aerosol Deposition Amounts in the Containment Vessel and the Reactor Building

(1)Effect of Surface Materials on the Aerosol Deposition Behavior

*Naoya Miyahara¹, Eriko Suzuki¹, Shinichiro Uesawa¹, Isamu Sato², Haruaki Matsuura², Naoto Hagura², Hiroki Koshigoe², Masahiko Osaka¹ (1. JAEA, 2. Tokyo City University)

4:55 PM - 5:10 PM

[1B16] Development of the Evaluation Method for the Aerosol Deposition Amounts in the Containment Vessel and the Reactor Building

(2)Observation of Aerosol Behavior near Solid Wall

*Shinichiro Uesawa¹, Naoya Miyahara¹, Naoki Horiguchi¹, Eriko Suzuki¹, Hiroyuki Yoshida¹, Masahiko Osaka¹ (1. Japan Atomic Energy Agency)

5:10 PM - 5:25 PM

[1B17] Development of the evaluation method for the aerosol deposition amounts in the containment vessel and the reactor building

(3)Basic study on the aerosol deposition effect in the reactor building using a CFD

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

5:25 PM - 5:40 PM

[1B18] Evaluation of Fission Products Released during the NPP Severe Accident

21. Evaluation of FP deposition behavior in the containment using SAMPSON code

*Hidetoshi Karasawa¹, Shunsuke Uchida¹, Chiaki Kino¹, Marco Pellegrini¹, Masao Chaki¹, Masanori Naitoh¹ (1. Institute of Applied Energy )

5:40 PM - 5:55 PM

[1B19] Evaluation of Fission Products Released during the NPP Severe Accident

22. Validation of the analytical results on FP behavior by comaring with CAMS data

*Shunsuke Uchida¹, Hidetoshi Karasawa¹, Chiaki Kino¹, Marco Pellegrini¹, Masao Chaki¹, Masanori Naitoh¹ (1. Institute of Applied Energy )

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

Oral presentation

[2B01-04] Fukushima Accident 1

Tue. Mar 27, 2018 9:30 AM - 10:35 AM Room B (C1-311 -C1 Building)

Chair: Michio Murase (INSS)

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9:30 AM - 9:45 AM

[2B01] Development of Severe Accident Analysis Code SAMPSON

(1)熱流動解析モジュールの開発

*Shingo Ohtsuka¹, Hiroyuki Suzuki¹, Chiaki Kino¹, Masao Chaki¹ (1. The Institute of Applied Energy)

9:45 AM - 10:00 AM

[2B02] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(99)1F accident progression scenario for SAMPSON 3 weeks analysis (Unit-1)

*Masao Chaki¹, Hiroyuki Suzuki¹, Chiaki Kino¹, Marco Pellegrini¹ (1. IAE)

10:00 AM - 10:15 AM

[2B03] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(100)1F accident progression scenario for SAMPSON 3 weeks analysis (Unit-2)

*Chiaki Kino¹, Hiroyuki Suzuki¹, Marco Pellegrini¹, Masao Chaki¹ (1. IAE)

10:15 AM - 10:30 AM

[2B04] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(101)1F accident progression scenario for SAMPSON 3 weeks analysis (Unit-3)

*Hiroyuki Suzuki¹, Marco Pellegrini¹, Chiaki Kino¹, Masao Chaki¹ (1. IAE)

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

Oral presentation

[2B05-09] Fukushima Accident 2

Tue. Mar 27, 2018 10:35 AM - 12:00 PM Room B (C1-311 -C1 Building)

Chair: Hidemasa Yamano (JAEA)

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10:35 AM - 10:50 AM

[2B05] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(102)3 weeks analysis using SAMPSON code (Unit-1)

*Asao Nishikawa¹, Chiaki Kino¹, Masao Chaki¹ (1. IAE)

10:50 AM - 11:05 AM

[2B06] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(103)3 weeks analysis using SAMPSON code (Unit-2)

*Itsuo Yoshioka¹, Chiaki Kino¹, Masao Chaki¹ (1. IAE)

11:05 AM - 11:20 AM

[2B07] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(104)3 weeks analysis using SAMPSON code (Unit-3)

*Marco Pellegrini¹, Chiaki Kino¹, Masao Chaki¹ (1. The Institute of Applied Energy)

11:20 AM - 11:35 AM

[2B08] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(105)3D-MCCI analysis for 1F Unit-2&3 using SAMPSON code

*Davide Concu¹, Marco Pellegrini¹, Masao Chaki¹ (1. IAE)

11:35 AM - 11:50 AM

[2B09] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(106)Improvements of SAMPSON debris to lower head wall heat transfer models

*Alexandre EZZIDI¹, Chiaki KINO¹, Masao CHAKI¹ (1. IAE - NUPEC)

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

Oral presentation

[2B10-13] Scrubbing

Tue. Mar 27, 2018 2:45 PM - 3:50 PM Room B (C1-311 -C1 Building)

Chair: Shinichiro Uesawa (JAEA)

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2:45 PM - 3:00 PM

[2B10] Effect of Inner Flow in a Single Bubble on Decontamination during Pool Scrubbing

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

3:00 PM - 3:15 PM

[2B11] Gas-liquid two-phase flow behavior effected by thermal stratification during pool scrubbing

*Yuki Nakamura¹, Kota Fujiwara¹, Wataru Kikuchi¹, Saito Shimpei¹, Tomohisa Yuasa¹, Akiko Kaneko¹, Yutaka Abe¹ (1. University of Tsukuba)

3:15 PM - 3:30 PM

[2B12] Aerosol Transfer Behavior in Two Phase Flow during Pool Scrubbing

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

3:30 PM - 3:45 PM

[2B13] Pool scrubbing experiment

(1)Results of test in 0.3m submergence

*HAOMIN SUN¹, Shinichi Machida², Yoshiyasu Hirose³, Yasuteru Sibamoto¹, Yuria Okagaki¹, Taisuke Yonomoto¹ (1. Japan atomic energy agency, 2. Persol Tempstaff, 3. Advanced Algorithm & Systems)

Time reserved for Chair （3:45 PM - 3:50 PM）

Oral presentation

[2B14-17] CCFL and Liquid Film Behavior

Tue. Mar 27, 2018 3:50 PM - 4:55 PM Room B (C1-311 -C1 Building)

Chair: Hide Okada (IAE)

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3:50 PM - 4:05 PM

[2B14] Experimental Study of an Effect of Water Flow Rate on CCFL Behavior at Upper Tie Plate

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

4:05 PM - 4:20 PM

[2B15] Effect of Diameters on Countercurrent Flow Limitation at Sharp-Edged Upper End of Vertical Pipes

*Michio Murase¹, Koji Nishida¹, Takayoshi Kusunoki¹, Akio Tomiyama² (1. Institute of Nuclear Safety System, Inc., 2. Kobe University)

4:20 PM - 4:35 PM

[2B16] Effect of the Wettability on the Front Edge Geometry of Liquid Film Flowing Down on an Incline

*Takahiro Ito¹, Tatsuya Tsuneyoshi¹, Yoshiyuki Tsuji¹ (1. Nagoya University)

4:35 PM - 4:50 PM

[2B17] Development of Numerical Simulation Method for Relocation Behavior of Molten Materials in Nuclear Reactors

(12)流下液膜界面挙動の計測

*Yutaro Hihara¹, Hideaki Monji¹, Yutaka Abe¹, Hiroyuki Yoshida², Susumu Yamashita² (1. University of Tsukuba, 2. JAEA)

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

Oral presentation

[2B18-21] Two-phase Flow Experiment

Tue. Mar 27, 2018 4:55 PM - 6:00 PM Room B (C1-311 -C1 Building)

Chair: Tomio Okawa (UEC)

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4:55 PM - 5:10 PM

[2B18] Detailed measurement of thermal hydraulic behavior of steam-air mixture condensation

(1)Summary of test facility and results of shake-down test

*Masahiro Ishigaki¹, Satoshi Abe¹, Yuki Wada¹, Yasuteru Sibamoto¹, Taisuke Yonomoto¹ (1. JAEA)

5:10 PM - 5:25 PM

[2B19] Two-phase flow behavior in diffuser section of a supersonic steam injector

*Yuki Kamata¹, Masaya Fujishiro¹, Akiko Kaneko¹, Yutaka Abe¹ (1. Univ. of Tsukuba)

5:25 PM - 5:40 PM

[2B20] Research and development for understanding two-phase flow behavior inside a fuel bundle

(4)Two-subchannel cross flow test at atmospheric pressure

*kiyoshi Fujimoto¹, Kenichi Katono¹, Hajime Furuichi¹, Hideaki Hosoi¹, Kenichi Yasuda¹, Kazuaki Kito¹ (1. Hitachi-GE Nuclear Energy,Ltd.)

5:40 PM - 5:55 PM

[2B21] Development of simultaneous measurement technique for void fraction and fluid temperature in boiling flow

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

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

Oral presentation

[3J01-04] Melt Material Behavior and Steam Explosion

Wed. Mar 28, 2018 9:30 AM - 10:35 AM Room J (U3-211 -U3 Building)

Chair: Akifumi Yamaji (Waseda Univ.)

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9:30 AM - 9:45 AM

[3J01] Experimental study on liquid melt spreading under precautionary water injection into containment vessel

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

9:45 AM - 10:00 AM

[3J02] Penetration Behavior of Liquid Jet Falling into a Shallow Pool

(2)Simultaneous Measurement of Jet Spreading Behavior and Velocity Field Using LIF/PIV

*Fumihito Kimura¹, Hiroyuki Yoshida², Akiko Kaneko¹, Yutaka Abe¹ (1. University of Tsukuba, 2. Japan Atomic Energy Agency)

10:00 AM - 10:15 AM

[3J03] Penetration Behavior of Liquid Jet Falling into a Shallow Pool

(3)Detailed Numerical Simulation of Jet Spreading Behavior

*Hiroyuki Yoshida¹, Fumihito Kimura², Takayuki Suzuki¹, Akiko Kaneko², Yutaka Abe² (1. Japan Atomic Energy Agency, 2. University of Tsukuba)

10:15 AM - 10:30 AM

[3J04] Availability of Steam Explosion Retardant for High-Temperature Molten Nickel and Tin

*Masahiro Furuya¹, Takahiro Arai¹ (1. CRIEPI)

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

Oral presentation

[3J05-09] Particle Method

Wed. Mar 28, 2018 10:35 AM - 12:00 PM Room J (U3-211 -U3 Building)

Chair: Koji Morita (Kyushu Univ.)

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10:35 AM - 10:50 AM

[3J05] Improved Curvature Calculation of the Continuum Surface Tension Model in Moving Particle Semi-Implicit Method

*Jiazhi Li¹, Sunghyon Jang¹, Akira Yamaguchi¹ (1. The University of Tokyo)

10:50 AM - 11:05 AM

[3J06] Development of the numerical calculation code for relocation analysis of reactor core internal structures with the MPFI method and the MPS method

*Shota Ueda¹, Masahiro Kondo¹, Koji Okamoto¹ (1. The University of Tokyo)

11:05 AM - 11:20 AM

[3J07] Research on numerical simulation of MCCI using MPS method

*Keigo Fujikawa¹, Koji Okamoto¹, Masahiro Kondo¹ (1. The Univ. of Tokyo)

11:20 AM - 11:35 AM

[3J08] Deepening Understanding of Ex-Vessel Corium Behavior by Multi-Physics Modeling

(2)Overview and Progress on Spreading Analysis by MPS Method

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

11:35 AM - 11:50 AM

[3J09] Deepening Understanding of Ex-Vessel Corium Behavior by Multi- Physics Modeling

III. Physical property of liquid oxides measured by aerodynamic levitation

*Toshiki Kondo¹, Yuji Ohishi¹, Hiroaki Muta¹, Ken Kurosaki¹, Shinsuke Yamanaka (1. Kurosaki and Muta laboratory , Department of sustainable energy and environmental engineering, Graduate school of engineering, Osaka university )

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

Oral presentation

[3J10-12] Thermal-hydraulics Numerical Simulation

Wed. Mar 28, 2018 2:45 PM - 3:35 PM Room J (U3-211 -U3 Building)

Chair: Hiroyuki Yoshida (JAEA)

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2:45 PM - 3:00 PM

[3J10] Development of a three-dimensional two-fluid thermal-hydraulic analysis code, “MIDAC-T” for PWR safety analysis

Phase1: Development policy

*Tadakatsu Yodo¹, Atsuyoshi Ikebe², Masaaki Katayama¹, Motoko Kawachi¹, Takayuki Suemura¹ (1. Mitsubishi Heavy Industries, Ltd., 2. MHI Nuclear Systems And Solution Engineering Co., Ltd.)

3:00 PM - 3:15 PM

[3J11] Numerical simulation of wall condensation heat transfer experiment in a circular tube

*Yoichi Utanohara¹, Michio Murase¹ (1. INSS)

3:15 PM - 3:30 PM

[3J12] Development of multi-dimensional melt spreading behavior analysis code MSPREAD

Code structure and validation based on simulant test data

*Akitoshi Hotta¹, Miyuki Akiba¹, Yuki Doi¹ (1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority )

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

Oral presentation

[3J13-15] Density Stratification and Natural Convection

Wed. Mar 28, 2018 3:35 PM - 4:25 PM Room J (U3-211 -U3 Building)

Chair: Yasushi Saito (Kyoto Univ.)

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3:35 PM - 3:50 PM

[3J13] CIGMA experiment and CFD analysis on density strtification breakup in a containment vessel

*Satoshi Abe¹, Masahiro Ishigaki¹, Yasuteru Sibamoto¹, Taisuke yonomoto¹ (1. Japan Atomic Energy Agency)

3:50 PM - 4:05 PM

[3J14] Investigation on heat transfer characteristics of reactor cavity cooling system for high temperature gas-cooled reactor

*Seisuke Hosomi¹, Shuhei Yamaguchi¹, Tomoyasu Akashi¹, Tatsuya Matsumoto¹, Wei Liu¹, Koji Morita¹, Kuniyoshi Takamatsu² (1. Kyushu Univ., 2. JAEA)

4:05 PM - 4:20 PM

[3J15] Study on Air Ingress Phenomena during a Depressurization Accident of VHTR

(3)Influence of pipe rupture position on onset time of natural circulation

*Tetsuaki TAKEDA¹, Tomoya SHIGA¹ (1. University of Yamanashi)

Time reserved for Chair （4:20 PM - 4:25 PM）

Oral presentation

[3K08-13] Nuclear Plant and Equipment

Wed. Mar 28, 2018 2:45 PM - 4:25 PM Room K (U3-311 -U3 Building)

Chair: Akira Nakamura (INSS)

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2:45 PM - 3:00 PM

[3K08] A Study on Analysis Method for Hydrogen Distribution Applying GOTHIC DP model and Scenario Clustering

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

3:00 PM - 3:15 PM

[3K09] TRACE code analysis for PCV thermal-hydraulics at the Fukushima Daiichi Unit 3 accident

*Riichiro Okawa¹, Masahiro Furuya¹ (1. Central Research Institute of Electric Power Industry)

3:15 PM - 3:30 PM

[3K10] Risk Based Strategies for Inspection and Maintenance of Nuclear Power Plants

6. Maintenance Management Based on Reliability Evaluation Method Combining PFM and FMEA

*Masayoshi Kojima¹, Hiroshige Kikura¹, Hideharu Takahashi¹, Shunsuke Uchida², Hidetoshi Okada² (1. Tokyo Institute of Technology, 2. The Institute of Applied Energy)

3:30 PM - 3:45 PM

[3K11] Risk Based Strategies for Inspection and Maintenance of Nuclear Power Plants

7. Improvement of Plant Reliability Based on Fusion of Prediction and Inspection on IGSCC

*Hide Okada¹, Shunsuke Uchida¹, Masanori Naitoh¹, Yasuhiro Chimi², Shigeki Kasahara², Satoshi Hanawa², Masayoshi Kojima³, Hideharu Takahashi³, Hiroshige Kikura³ (1. The Institute of Applied Energy, 2. Japan Atomic Energy Agency, 3. Tokyo Institute of Technology)

3:45 PM - 4:00 PM

[3K12] Study on Thermal-hydraulics characteristics of the flat and high-thermal-conductivity core-catcher

Experiments of heat transfer behavior in the horizontal rectangular finned channel

*Daiki Takeyama¹, Chikako Iwaki¹, Mika Tahara¹, Onitsuka Yoichi¹ (1. Toshiba Energy Systems & Solutions Corporation)

4:00 PM - 4:15 PM

[3K13] Development of Cross Fin Heat Exchanger for Nuclear Power Plant

*Hisaharu Sakae¹ (1. IHI)

Time reserved for Chair （4:15 PM - 4:25 PM）

Sessions

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

[1B01-07] Thermal-hydraulics of Fast Reactor

(2)Design for a sodium two-phase flow experiment with boiling in a simulated debris

(3)Measurement of air-water two phase pressure drop in a simulated debris bed

(1)Observation of gas entrainment by PIV measurement

(2)Evaluation of gas entrainment by CFD analysis

[1B08-14] Boiling and Condensation

1st: Dryout Heat Flux for Bottom Heated Debris Beds

(2)3 mm inner diameter and 100 mm heated length

(1)Effect of pressure on the behavior of bubbles and process of coalescence

[1B15-19] Fission Product Behavior

(1)Effect of Surface Materials on the Aerosol Deposition Behavior

(2)Observation of Aerosol Behavior near Solid Wall

(3)Basic study on the aerosol deposition effect in the reactor building using a CFD

21. Evaluation of FP deposition behavior in the containment using SAMPSON code

22. Validation of the analytical results on FP behavior by comaring with CAMS data

[2B01-04] Fukushima Accident 1

(1)熱流動解析モジュールの開発

(99)1F accident progression scenario for SAMPSON 3 weeks analysis (Unit-1)

(100)1F accident progression scenario for SAMPSON 3 weeks analysis (Unit-2)

(101)1F accident progression scenario for SAMPSON 3 weeks analysis (Unit-3)

[2B05-09] Fukushima Accident 2

(102)3 weeks analysis using SAMPSON code (Unit-1)

(103)3 weeks analysis using SAMPSON code (Unit-2)

(104)3 weeks analysis using SAMPSON code (Unit-3)

(105)3D-MCCI analysis for 1F Unit-2&3 using SAMPSON code

(106)Improvements of SAMPSON debris to lower head wall heat transfer models

[2B10-13] Scrubbing

(1)Results of test in 0.3m submergence

[2B14-17] CCFL and Liquid Film Behavior

(12)流下液膜界面挙動の計測

[2B18-21] Two-phase Flow Experiment

(1)Summary of test facility and results of shake-down test

(4)Two-subchannel cross flow test at atmospheric pressure

[3J01-04] Melt Material Behavior and Steam Explosion

(2)Simultaneous Measurement of Jet Spreading Behavior and Velocity Field Using LIF/PIV

(3)Detailed Numerical Simulation of Jet Spreading Behavior

[3J05-09] Particle Method

(2)Overview and Progress on Spreading Analysis by MPS Method

III. Physical property of liquid oxides measured by aerodynamic levitation

[3J10-12] Thermal-hydraulics Numerical Simulation

Phase1: Development policy

Code structure and validation based on simulant test data

[3J13-15] Density Stratification and Natural Convection

(3)Influence of pipe rupture position on onset time of natural circulation

[3K08-13] Nuclear Plant and Equipment

6. Maintenance Management Based on Reliability Evaluation Method Combining PFM and FMEA

7. Improvement of Plant Reliability Based on Fusion of Prediction and Inspection on IGSCC

Experiments of heat transfer behavior in the horizontal rectangular finned channel

Authentication