Oral presentation

[1E01-07] Thermal-Hydraulics in Fuels

Wed. Sep 13, 2017 10:05 AM - 12:00 PM Room E (B32 - B3 Block)

Chair:Takeshi Takeda (JAEA)

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10:05 AM - 10:20 AM

[1E01] Research and development for understanding two-phase flow behavior inside a fuel bundle

(1)Outline of research plan

*Kazuaki Kito¹, Kenichi Katono¹, Atsushi Ui², Masahiro Furuya² (1. Hitachi-GE, 2. CRIEPI)

10:20 AM - 10:35 AM

[1E02] Research and development for understanding two-phase flow behavior inside a fuel bundle

(2)Test plan for measurement of cross-flow behavior in two-subchannel under rated condition of BWRs

*Hideaki Hosoi¹, Kenichi Katono¹, Kiyoshi Fujimoto¹, Naohisa Watahiki¹, Yuma Nagasawa¹, Kenichi Yasuda¹, Kazuaki Kito¹ (1. Hitachi-GE)

10:35 AM - 10:50 AM

[1E03] Research and development for understanding two-phase flow behavior inside a fuel bundle

(3)Experiments of subcooled boiling flow through a vertical double wall channel under atmospheric condition

*Atsushi Ui¹, Masahiro Furuya¹, Hiroki Takiguchi¹, Kenetsu Shirakawa¹, Takahiro Arai¹ (1. Central Research Institute of Electric Power Industry)

10:50 AM - 11:05 AM

[1E04] Thermal hydraulics in reactor core under rod bundle uncovery conditions

(15)Influence of Rod-Pitch on Void Fraction Distribution in an Unheated 5 x 5 Rod Bundle

*Kenichi Katono¹, Kiyoshi Fujimoto¹, Goro Aoyama², Yuma Nagasawa², Takuji Nagayoshi¹, Takahiro Arai³ (1. Hitachi, 2. Hitachi-GE Nuclear Energy, 3. Central Research Institute of Electric Power Industry)

11:05 AM - 11:20 AM

[1E05] Research on a flow inside the fuel assembly by a portable spray

*Koji Yamada¹, Koji Ishizaki¹, Hayata shimmura¹, Junichi Takeuchi², Chihiro Nishizaki², Yoshiyuki Kondoh², Yoshiteru Komuro², Atsushi Kodama² (1. KEPCO, 2. MHI)

11:20 AM - 11:35 AM

[1E06] Measurement of Void Fraction Distribution in Two-Phase Flow in a 4×4 Bundle

(2)Measurement of steam-water two-phase flow under high temperature and pressure conditions

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

11:35 AM - 11:50 AM

[1E07] Study on the DNB heat flux improvement by mixing vanes

*Keito Kamei¹, Shinichi Morooka¹ (1. Waseda Univ.)

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

Oral presentation

[1E08-12] Severe Accident of Fukushima Daiichi 1

Wed. Sep 13, 2017 2:45 PM - 4:05 PM Room E (B32 - B3 Block)

Chair:Tadashi Narabayashi (Hokkaido Univ.)

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2:45 PM - 3:00 PM

[1E08] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(90)Sensitivity analysis of Fukushima Daiichi unit 1 ex-vessel scenario by the SAMPSON code

*Davide Concu¹, Marco Pellegrini¹, Masao Chaki¹, Masanori Naitoh¹ (1. IAE)

3:00 PM - 3:15 PM

[1E09] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(91)Evaluation of Debris Spreading Conditions by Plant Sensitivity Analyses

*Masataka Hidaka^1,2, Tadashi Fujii^1,2, Takeshi Sakai^1,2 (1. International Research Institute for Nuclear Decommissioning, 2. Hitachi-GE Nuclear Energy, Ltd.)

3:15 PM - 3:30 PM

[1E10] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(92)Fukushima Daiichi Unit 2 plant analysis using SAMPSON/POOL3D

*Antonio Buccio¹, Marco Pellegrini¹, Masao Chaki¹, Masanori Naitoh¹ (1. The Institute of Applied Energy)

3:30 PM - 3:45 PM

[1E11] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(93)Comprehensive evaluation for debris distribution in Unit-2 by SAMPSON Severe Accident Code

*Chiaki Kino¹, Itsuo Yoshioka¹, Masao Chaki¹, Masanori Naitoh¹ (1. IAE)

3:45 PM - 4:00 PM

[1E12] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(94)Long term sensitivity analysis of Fukushima Daiichi Unit 3 by the SAMPSON code

*Marco Pellegrini¹, Francesca Longhi¹, Masao Chaki¹, Masanori Naitoh¹ (1. The Institute of Applied Energy)

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

Oral presentation

[1E13-17] Severe Accident of Fukushima Daiichi 2

Wed. Sep 13, 2017 4:05 PM - 5:25 PM Room E (B32 - B3 Block)

Chair:Tadashi Fujii (HGNE)

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4:05 PM - 4:20 PM

[1E13] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(95)Evaluation of Inflow of Venting Gas of Unit 3 into Unit 4 using GOTHIC

*Kenichiro Nozaki¹, Takeshi Honda¹, Daisuke Yamauchi¹, Masato Mizokami¹, Shinya Mizokami¹ (1. Tokyo Electric Power Company Holdings, Inc.)

4:20 PM - 4:35 PM

[1E14] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(96)CRD housing failure experiment at the KAERI VESTA facility

*Hiroyuki Suzuki¹, Marco Pellegrini¹, Masanori Naitoh¹ (1. IAE)

4:35 PM - 4:50 PM

[1E15] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(97)Assessment of "SAMPSON/DCA" Heat Transfer Models between relocated molten core and RPV lower head wall

*Alexandre Ezzidi¹, Masanori Naitoh¹, Hide Okada¹, Chiaki Kino¹ (1. IAE)

4:50 PM - 5:05 PM

[1E16] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(98)Discussion in the accident progression behavior in the early stage of the Unit 1 accident based on dose rate data

*Daisuke YAMAUCHI¹, Hiroshi SHIRAI², Tami MUKOUHARA², Masaki SAKAMOTO², Yuki KIMURA², Takeshi HONDA¹, Kenichiro NOZAKI¹, Masato MIZOKAMI¹, Shinya MIZOKAMI¹ (1. Tokyo Electric Power Company Holdings, Inc., 2. TEPCO Systems Corporation)

5:05 PM - 5:20 PM

[1E17] Fukushima Daiichi NPP Unit-2 Suppression Chamber Bottom Earthquake Break and Its Consequence

*Fumiya Tanabe¹ (1. Sociotechnical Systems Safety Research Institute)

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

Oral presentation

[1E18-20] CCFL

Wed. Sep 13, 2017 5:25 PM - 6:15 PM Room E (B32 - B3 Block)

Chair:Kenichiro Nozaki (TEPCO HD)

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5:25 PM - 5:40 PM

[1E18] Countercurrent Flow Limitation at Lower End of Vertical Pipes

(1)Correlation of Interfacial Friction for one-region computation

*KOJI NISHIDA¹, TAKAYOSHI KUSUNOKI¹, MICHIO MURASE¹ (1. Institute of Nuclear Safety System, Incorporated)

5:40 PM - 5:55 PM

[1E19] Counter-current flow limitation at lower ends in vertical pipes

(2)Measurement of interfacial friction factor

*Raito Goda¹, Katsuya Mori¹, Kosuke Hayashi¹, Shigeo Hosokawa¹, Akio Tomiyama¹ (1. Kobe University)

5:55 PM - 6:10 PM

[1E20] Counter current flow limiting in inclined pipe simulating PWR hot-leg

*Akira Satou¹, Yasuteru Shibamoto¹, Taisuke Yonomoto¹ (1. Japan Atomic Energy Agency)

Time reserved for Chair （6:10 PM - 6:15 PM）

Oral presentation

[2E01-04] Phase Change

Thu. Sep 14, 2017 9:30 AM - 10:35 AM Room E (B32 - B3 Block)

Chair:Ayako Ono (JAEA)

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9:30 AM - 9:45 AM

[2E01] On Improvement of Pool Boiling Heat Transfer coefficient by Honeycomb Porous plate

*Shoji Mori¹, Ryuta Yanagisawa¹, Kunito Okuyama¹ (1. Yokohama National university)

9:45 AM - 10:00 AM

[2E02] Mechanism of the flashing phenomena induced by microwave heating

*Shunya Fujita¹, Yutaka Abe¹, Akiko Kaneko¹, Tomohisa Yuasa¹, Tomoomi Segawa², Yoshikazu Yamada² (1. University of tsukuba, 2. Japan Atomic Energy Agency)

10:00 AM - 10:15 AM

[2E03] Study on Cooling Process of High-Temperature Body Using Nanofluids

*Yutaro Umehara¹, Tomio Okawa¹, Koji Enoki¹, Wei Liu² (1. UEC, 2. KYUSHU Univ.)

10:15 AM - 10:30 AM

[2E04] The impacts of scale effect on heat transfer and momentum transport on steam-water interface of a supersonic steam injector.

*Masaya Fujishiro¹, Yutaka Abe¹, Akiko Kaneko¹ (1. University of tsukuba)

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

Oral presentation

[2E05-09] Thermal Hydraulics Simulation 1

Thu. Sep 14, 2017 10:35 AM - 12:00 PM Room E (B32 - B3 Block)

Chair:Tatsuya Hazuku (Tokyo Univ. of Marine Sci. and Tech.)

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10:35 AM - 10:50 AM

[2E05] Development of evaluation method on thermal stratification by cavity flow in a vertical branch pipe with elbow and horizontal section

Measurement and understanding of thermal hydraulics phenomena about thermal stratification

*Yoshiteru Komuro¹, Atsushi Kodama¹, Keiichi Hori ¹, Hironori Noguchi¹, Yoshiyuki Kondo¹, Koichi Tanimoto¹ (1. MHI)

10:50 AM - 11:05 AM

[2E06] Development of evaluation method on thermal stratification by cavity flow in a vertical branch pipe with elbow and horizontal section

Development of evaluation method for cavity flow penetration depth

*Atsushi Kodama¹, Yoshiteru Komuro¹, Keiichi Hori¹, Hironori Noguchi¹, Yoshiyuki Kondo¹, Koichi Tanimoto¹ (1. MHI)

11:05 AM - 11:20 AM

[2E07] Numerical analysis of the bubble condensation on subcooled flow boiling

*Shintaro Sakamoto¹, Hiroki Ohori¹, Koji Enoki¹, Tomio Okawa¹ (1. UEC)

11:20 AM - 11:35 AM

[2E08] Numerical simulation for steam-air mixture flow and wall condensation heat transfer in a circular tube

*Yoichi Utanohara¹, Michio Murase¹ (1. INSS)

11:35 AM - 11:50 AM

[2E09] Submergence behavior of liquid jet falling into a shallow pool

Comparison of detailed simulation and results of visualization in a simplified system

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

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

Oral presentation

[2E10-14] Thermal Hydraulics in Fast Reactor 1

Thu. Sep 14, 2017 2:45 PM - 4:05 PM Room E (B32 - B3 Block)

Chair:Yoshihisa Nishi (CRIEPI)

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2:45 PM - 3:00 PM

[2E10] Thermal-hydraulic numerical evaluation for thermal striping of sodium-cooled fast reactor

Study on applicability of temperature fluctuation intensity estimation method to triple parallel jets sodium test

*Masaaki Okano¹, Hiroyuki Sakamoto², Tomoaki Ogata², Hironori Nakamura³, Kazuhiro Oyama³, Osamu Watanabe³, Masaaki Tanaka⁴, Hiroyuki Ohshima⁴ (1. MHI, 2. MHI NSE, 3. MFBR, 4. JAEA)

3:00 PM - 3:15 PM

[2E11] Study on Gas Entrainment in Sodium Cooled Fast Reactors, 11;

Applicability of Vortex Model Based Evaluation on Vortex Type Gas Entrainment

*Toshiki Ezure¹, Kei Ito², Yuri Kameyama³, Masaaki Tanaka¹, Akikazu Kurihara¹, Hiroyuki Ohshima¹ (1. JAEA, 2. Kyoto Univ., 3. NDD Corp.)

3:15 PM - 3:30 PM

[2E12] A Study on Cooling Process of Decay Heat Removal Systems in a Reactor Vessel of Sodium-cooled fast Reactor by Scaled Water Experiments

Flow Visualization Experiments Simulating Operation of Decay Heat Removal Systems under a Severe Accident

*Ayako Ono¹, Akikazu Kurihara¹, Masaaki Tanaka¹, Hiroyuki Ohshima¹, Yasuhiro Miyake², Masami Ito⁴, Shigeru Nakane³ (1. JAEA, 2. NDD, 3. NESI, 4. ASCEND)

3:30 PM - 3:45 PM

[2E13] Study on splashing phenomenon of liquid jet collision

*Yi Zhan¹, Naoki Oya¹, Koji Enoki¹, Tomio Okawa¹, Mitsuhiro Aoyagi², Shuji Ohno², Takashi Takata² (1. UEC Univ., 2. JAEA)

3:45 PM - 4:00 PM

[2E14] Study on coolant behavior in damaged core of sodium-cooled fast reactor

(1)Measurement of gas-liquid two-phase flow in a simulated debris bed

*Daisuke Ito¹, Milka Rivera Nava¹, Kei Ito¹, Yasushi Saito¹, Mitsuhiro Aoyagi², Kenichi Matsuba², Kenji Kamiyama² (1. KURRI, 2. JAEA)

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

Oral presentation

[2E15-18] Thermal Hydraulics in Fast Reactor 2

Thu. Sep 14, 2017 4:05 PM - 5:10 PM Room E (B32 - B3 Block)

Chair:Masaki Morishita (JAEA)

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4:05 PM - 4:20 PM

[2E15] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(1)Overall plan for development of simulations systems

*Hiroyuki Ohshima¹, Takashi Takata¹, Norihiro Doda¹, Shin Kikuchi¹, Nobuyoshi Koga², Yoshihiro Deguchi³ (1. Japan Atomic Energy Agency, 2. Hiroshima University, 3. Tokushima University)

4:20 PM - 4:35 PM

[2E16] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(2)Conceptual design of multi-level simulation system and development plan

*Norihiro Doda¹, Hideo Araseki¹, Kunihiko Nabeshima¹, Takashi Takata¹, Masaaki Tanaka¹, Hiroyuki Ohshima¹ (1. JAEA)

4:35 PM - 4:50 PM

[2E17] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(3)Conceptual design of multi-scenario simulation system and development plan

*Takashi Takata¹, Kei Ito¹, Akhirio Uchibori¹, Mitsuhiro Aoyagi¹, Hiroyuki Ohshima¹ (1. JAEA)

4:50 PM - 5:05 PM

[2E18] Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor

(4)Experimental database construction for code V&V

*Shin Kikuchi¹, Akikazu Kurihara¹, Nobuyoshi Koga², Yoshihiro Deguchi³, Takashi Takata¹, Hiroyuki Ohshima¹ (1. Japan Atomic Energy Agency, 2. Hiroshima University, 3. Tokushima University)

Time reserved for Chair （5:05 PM - 5:10 PM）

Oral presentation

[2E19-23] Equipments for Accidents

Thu. Sep 14, 2017 5:10 PM - 6:30 PM Room E (B32 - B3 Block)

Chair:Hiroyuki Yoshida (JAEA)

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5:10 PM - 5:25 PM

[2E19] Developement of Passive Debris Cooling System

(5)Evalutation of phase diagrama of debris-refractory layer component (UO₂-ZrO₂-Zr)

*Yuya Takahashi¹, Satoru Kuboya¹, Yoshiro Nishioka¹, Isao Sakaki², Tadashi Fujii³, Takafumi Tsuji⁴ (1. Toshiba, 2. Retired Toshiba, 3. Hitachi-GE Nuclear Energy, 4. Chubu Electric Power)

5:25 PM - 5:40 PM

[2E20] Development of Passive Debris Cooling System

(6)Erosion Resistance of Heat Resistant Materials by Molten Debris

*Satoru Kuboya¹, Yuya Takahashi¹, Yoshiro Nishioka¹, Isao Sakaki², Tadashi Fujii³, Takafumi Tsuji⁴ (1. Toshiba, 2. Retired Toshiba , 3. Hitachi-GE Nuclear Energy, 4. CHUBU Electric Power Co.)

5:40 PM - 5:55 PM

[2E21] Developement of Passive Debris Cooling System

(7)Applicability evaluation of Heat Resistant Materials

*YOSHIRO NISHIOKA¹, HIDEKI HORIE¹, SATORU KUBOYA¹, TAKAHASHI TAKAHASHI¹, MIKA TAHARA¹, TAKAHUMI TSUJI², TADASHI FUJII³ (1. TOSHIBA, 2. CHUBU Electric Power, 3. HITACHI-GE Nuclear Energy)

5:55 PM - 6:10 PM

[2E22] Evaluation of cooling capability of isolation condenser under accident conditions

(1)Analyses for Fukushima Daiichi Unit 1

*Yasunori YAMAMOTO¹, Masayoshi MORI¹, Tadashi NARABAYASHI¹, Yuki KURA¹, Go CHIBA¹ (1. Hokkaido University)

6:10 PM - 6:25 PM

[2E23] Evaluation of cooling capability of isolation condenser under accident conditions

(2)Experiments simulating isolation condenser at high pressure and temperature

*Masayoshi MORI¹, Yasunori YAMAMOTO¹, Tadashi NARABAYASHI¹, Yuki KURA¹, Go CHIBA¹ (1. Hokkaido University)

Time reserved for Chair （6:25 PM - 6:30 PM）

Oral presentation

[3E01-05] Filter and Scrubbing 2

Fri. Sep 15, 2017 9:30 AM - 10:55 AM Room E (B32 - B3 Block)

Chair:Takashi Takata (JAEA)

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9:30 AM - 9:45 AM

[3E01] Aerosol Behavior inside a Single Bubble during Pool Scrubbing

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

9:45 AM - 10:00 AM

[3E02] Gas-liquid two-phase flow behavior in pool scrubbing

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

10:00 AM - 10:15 AM

[3E03] Aerosol Behavior in Two-Phase Flow during Pool Scrubbing

*Wataru Kikuchi¹, Kota Fujiwara¹, Yuki Nakamura¹, Shimpei Saito¹, Tomohisa Yuasa¹, Kaneko Akiko¹, Yutaka Abe¹ (1. University of Tsukuba)

10:15 AM - 10:30 AM

[3E04] Development of High Efficiency Filtered Containment Venting System Using Zeolite

(11)Evaluation of Two-Phase Flow Instability by Visualized Test

*Takuya Fujii¹, Naoto Kitahara¹, Tadashi Narabayashi¹, Yasunori Yamamoto¹, Go Chiba¹ (1. Hokkaido Univ.)

10:30 AM - 10:45 AM

[3E05] Development of High Efficiency Filtered Containment Venting System Using Zeolite

(12)Supplession of Two-Phase Flow Instability by Using a Pressurize Orifice

*Naoto Kitahara¹, Takuya Fujii¹, Tadashi Narabayashi², Yasunori Yamamoto², Go Chiba² (1. Hokkaido Univ. Graduate School of Engineering, 2. Hokkaido Univ. Faculty of Engineering)

Time reserved for Chair （10:45 AM - 10:55 AM）

Oral presentation

[3E06-09] Thermal Hydraulics Simulation 2

Fri. Sep 15, 2017 10:55 AM - 12:00 PM Room E (B32 - B3 Block)

Chair:Taku Nagatake (JAEA)

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10:55 AM - 11:10 AM

[3E06] Development of Leak Detector for Canister

(1)Leak Tests by Vertical Small Canister Model

*Hirofumi Takeda¹, Kohei Shimaike² (1. CRIEPI, 2. Siemens)

11:10 AM - 11:25 AM

[3E07] Development of Leak Detector for Canister

(2)Leak Test Analysis by Vertical Small Canister Model

*Kohei Shimaike¹, Hirofumi Takeda² (1. Siemens, 2. CRIEPI)

11:25 AM - 11:40 AM

[3E08] Application of a fire zone model for a single compartment fire under mechanically ventilated condition

Case study of BRI2002

*Koji Tasaka¹, Koji Shirai¹, Toshiko Udagawa² (1. Central Research Institute of Electric Power Industry, 2. WDB Co., Ltd.)

11:40 AM - 11:55 AM

[3E09] Analysis evaluation of the thermal hydraulic phenomenon at lower plenum in the reactor vessel for the improvement in safety of PWR

Application of trasient analysis method to evaluation of the thermal hydraulic phenomenon in the reactor vessel

*Keigo Nishida¹, Junichi Takeuchi¹, Masaaki Okano¹, Daisuke Kanamori² (1. Mitsubishi Heavy Industries,LTD., 2. THE KANSAI ELECTRIC POWER CO.,INC)

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

Oral presentation

[3E10-13] System Analysis

Fri. Sep 15, 2017 2:45 PM - 3:50 PM Room E (B32 - B3 Block)

Chair:Kazuyuki Takase (Nagaoka Univ. of Tech.)

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2:45 PM - 3:00 PM

[3E10] Development of a System Analysis Code for NPP

(2)Development of a Basic Analysis Function

*Junichi Kaneko¹, Naofumi Tsukamoto¹ (1. NRA)

3:00 PM - 3:15 PM

[3E11] Sensitivity Analysis with RELAP5 Code Using ROSA/LSTF Test Data on Steam Generator Tube Rupture

*Takeshi TAKEDA¹, Iwao OHTSU¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[3E12] Verification of RELAP5 Interfacial Friction Model in Downcomer

(2)Investigation of Distribution Parameter Using Bubble Layer Thickness Model

*Ikuo Kinoshita¹, Shuichiro Miwa², Takashi Hibiki³ (1. INSS, 2. Hokkaido University, 3. Purdue University)

3:30 PM - 3:45 PM

[3E13] TRACE code analysis with modified boiling heat-transfer model for LOCA experiments

*Riichiro Okawa¹, Masahiro Furuya¹ (1. CRIEPI)

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

Oral presentation

[3E14-17] Measurement Techinique

Fri. Sep 15, 2017 3:50 PM - 5:00 PM Room E (B32 - B3 Block)

Chair:Satoshi Nishimura (CRIEPI)

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3:50 PM - 4:05 PM

[3E14] Fundamental development of time-resolved measurement technique for discovery of influence of melt convection on eutectic melting progress

*Shota Ueda¹, Masahiro Kondo¹, Kenta Inagaki², Koji Okamoto¹ (1. The University of Tokyo, 2. Central Research Institute of Electric Power Industry)

4:05 PM - 4:20 PM

[3E15] Thin liquid film thickness measurement by ultrasound

*Yuki Wada¹, Jun Sagawa², Yoshiyasu Hirose³, Akira Satou¹, Yasuteru Sibamoto¹, Taisuke Yonomoto¹ (1. JAEA, 2. Mito Electronic Solution, 3. Advanced Algorithm & Systems)

4:20 PM - 4:35 PM

[3E16] Study on maintaining performance of water level gauge under the severe accident

*Yuki KURA¹, Tadashi NARABAYASHI¹, Yasunori YAMAMOTO¹, Go CHIBA¹ (1. Hokkaido University)

4:35 PM - 4:50 PM

[3E17] Measurement Improvement of Flow Rate of Liquid Metal Using Ultrasonic Pulse Doppler Method Based on Velocity Profiles

*Kohei Tsutsumi¹, Shuichiro Miwa¹, Hiroto Sakashita¹, Michitsugu Mori¹ (1. Hokkaido Univ.)

Time reserved for Chair （4:50 PM - 5:00 PM）

Oral presentation

[2F10-16] Thermal Hydraulics at Accidents

Thu. Sep 14, 2017 2:45 PM - 4:40 PM Room F (C214 - C Block)

Chair:Yasuo Koizumi (JAEA)

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2:45 PM - 3:00 PM

[2F10] Experiments on Influences of Injecting Seawater and Boric Acid under Severe Accident Conditions

(7)Boiling concentration of sea water and blockage with precipitated salt in 5x5 bundle geometry

*Masahiro Furuya¹ (1. CRIEPI)

3:00 PM - 3:15 PM

[2F11] Experiments on influences of injecting seawater and boric acid under severe accident conditions

(8)Characterization of salt deposit layer growth and cladding temperature of heated rod bundles

*miyuki akiba¹, akitoshi hotta¹, retsu kojo¹ (1. NRA)

3:15 PM - 3:30 PM

[2F12] Evaluation of Fission Product Release during the NPP Severe Accident

(19)Improvement of Molybdenum Release Model in the SAMPSON Code

Ayumi Itoh¹, *Hidetoshi Karasawa¹, Marco Pellegrini¹, Masanori Naitoh¹ (1. Institute of Applied Energy)

3:30 PM - 3:45 PM

[2F13] Evaluation of Fission Product Released during the NPP Sevier Acccident

(20)Evaluation of Cs Deposition Distribution in the Primary Circuit by Phebus FPT1 Test Analysis

*Hidetoshi Karasawa¹, Ayumi Itoh¹, Marco Pellegrini¹, Masanori Naitoh¹ (1. The Institute of Applied Energy)

3:45 PM - 4:00 PM

[2F14] Study on the influence of internal structures of reactor containment vessel on density stratified layer erosion during a severe accident

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

4:00 PM - 4:15 PM

[2F15] The CIGMA facility experiment on containment vessel outer surface cooling

Effect of initial gas composition (2)

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

4:15 PM - 4:30 PM

[2F16] Study on Air Ingress Phenomena during a Depressurization Accident of VHTR

(2)Discussion on Onset Time of Natural Circulation

*Tetsuaki Takeda¹ (1. University of Yamanashi)

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

Oral presentation

[2F17-23] Filter and Scrubbing 1

Thu. Sep 14, 2017 4:40 PM - 6:30 PM Room F (C214 - C Block)

Chair:Hide Okada (IAE)

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4:40 PM - 4:55 PM

[2F17] Development of a high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core

(4)Investigation of Raduation Protection Technology based on the capture test

*Tadashi Narabayashi¹, Akinori Ishii¹, Yuta Watanabe¹, Go Chiba¹, Yasunori Yamamoto¹, Masanobu Sato², Takao Masuda¹ (1. Hokkaido Univ., 2. Tohoku Univ.)

4:55 PM - 5:10 PM

[2F18] Depelopment of a high efficiency muiti-nuclide aerosol filters for radiation protection during a process of cutting core

(5)Improvement of Decontamination Factor by using steam injection

*Yuta Watanabe¹, Tadashi Narabayashi¹, Akinori Ishii¹, Yasunori Yamamoto¹, Go Chiba¹, Takao Masuda¹, Masanobu Sato² (1. Hokkaido University, 2. Tohoku University)

5:10 PM - 5:25 PM

[2F19] Development of a high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core

(6)Measurement of Iodomethane diffusivity within MFI and FAU type Zeolite

*Noriki Hayakawa¹, Yuta Nakasaka², Yuta Ishizu³, Takuya Yoshikawa², Takao Masuda² (1. Hokkaido University Graduate School of Chemical Sciences and Engineering, 2. Hokkaido University Graduate School of Engineering , 3. Hokkaido University Faculty of Engineering )

5:25 PM - 5:40 PM

[2F20] Development of a High Efficiency Multi-nuclide Aerosol Filters for Radiation Protection during a Process of Cutting Core

(7)Evaluation of Sorption Performance of Methyl Iodine by Silver doped Zeolite under Steam Environment

*Daisuke Akiyama¹, Yutaka Masaki¹, Nobuaki Sato¹, Akira Kirishima¹, Tadashi Narabayashi² (1. Tohoku univ., 2. Hokkaido univ.)

5:40 PM - 5:55 PM

[2F21] Development of a high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core

(8)Development of a simple tool to estimate radioactivity trapped by filter element

*Go Chiba¹, Akinori Ishii¹, Tamotsu Kozaki¹, Tadashi Narabayashi¹, Nobuaki Sato² (1. Hokkaido university, 2. Tohoku university)

5:55 PM - 6:10 PM

[2F22] Development of a high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core

(9)Estimation of radioactivity of short half-lived fission product nuclides trapped by filter element

*Akinori Ishii¹, Go Chiba¹, Tamotsu Kozaki¹, Tadashi Narabayashi¹, Yasunori Yamamoto¹ (1. Hokkaido Univ.)

6:10 PM - 6:25 PM

[2F23] Development of Evaluation Method for Decontamination Performance of Venturi Scrubber Based on Mechanistic Two-phase Flow Model

(1)Understanding of Two-phase Flow behavior by Water-air and Water-vapor Visualization Experiments

*Shinichiro Uesawa¹, Naoki Horiguchi¹, Takayuki Suzuki¹, Mitsuhiko Shibata¹, Hiroyuki Yoshida¹ (1. Japan Atomic Energy Agency)

Time reserved for Chair （6:25 PM - 6:30 PM）

Oral presentation

[3F01-04] Corrosion and Risk Evaluation

Fri. Sep 15, 2017 9:30 AM - 10:35 AM Room F (C214 - C Block)

Chair:Hidemasa Yamano (JAEA)

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9:30 AM - 9:45 AM

[3F01] Risk Based Strategies for Inspection and Maintenance of Nuclear Power Plants

3. Maintenance management based on reliability evaluation in consideration of responding capability against failure modes

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

9:45 AM - 10:00 AM

[3F02] Risk Based Strategies for Inspection and Maintenance of Nuclear Power Plants

4. An Example for Risk Based Inspection for the Events Originating FAC Related Causes

*Hide Okada¹, Shunsuke Uchida¹, Masanori Naitoh¹, Masayoshi Kojima², Hiroshige Kikura² (1. The Institute of Applied Energy, 2. Tokyo Institute of Technology)

10:00 AM - 10:15 AM

[3F03] Risk Based Strategies for Inspection and Maintenance of Nuclear Power Plants

5. An Example for Risk Based Inspection for the Events Originating IGSCC Related Causes

*Shunsuke Uchida¹, Hide Okada¹, Masanori Naitoh¹, Satoshi Hanawa³, Masayoshi Kojima², Hiroshige Kikura² (1. The Institute of Applied Energy, 2. Tokyo Institute of Technology, 3. Japan Atomic Energy Agency)

10:15 AM - 10:30 AM

[3F04] Effect of liquid film velocity on flow accerelated corrosion under water-steam two-phase flow

*Masaaki Satake¹, Kimitoshi Yoneda¹, Ryo Morita¹, Kazutoshi Fujiwara¹, Fumio Inada¹ (1. CRIEPI)

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

Oral presentation

[3F05-09] Melting Behavior

Fri. Sep 15, 2017 10:35 AM - 12:00 PM Room F (C214 - C Block)

Chair:Masaaki Satake (CRIEPI)

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10:35 AM - 10:50 AM

[3F05] Deepening Understanding of Ex-Vessel Corium Behavior by Multi-Physics Modeling

(1)Overview of the Research Plan

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

10:50 AM - 11:05 AM

[3F06] Investigation on thermal deterioration of concreate in severe accident

*Takahito Hareyama¹, Tadashi Narabayashi², Yasunori Yamamoto², Go Chiba², Tsukasa Hayashi³, Takahiro Konno⁴ (1. Hokkaido University, Graduate school of enginieering, 2. Hokkaido University, Faculty of engineering, 3. THE CHUGOKU ELECTRIC POWER, 4. Hitachi-GE Nuclear Energy)

11:05 AM - 11:20 AM

[3F07] An Improved MPS Algorithm for Modelling Crust Behavior in Corium Spreading

*Guangtao Duan¹, Akifumi Yamaji¹, Seiichi Koshizuka², Masahiro Furuya³, Yuji Ohishi⁴ (1. Waseda Univ., 2. Univ. Of Tokyo, 3. Central Research Institute of Electric Power Industry, 4. Osaka Univ.)

11:20 AM - 11:35 AM

[3F08] Development of Numerical Simulation Method for Relocation Behavior of Molten Materials in Nuclear Reactors

(10)Measurement of flow down velocity and comparison with the result of numerical analysis

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

11:35 AM - 11:50 AM

[3F09] Development of Numerical Simulation Method for Relocation Behavior of Molten Materials in Nuclear Reactors

(11)Validation of JUPITER for a corium spreading behavior

*Susumu Yamashita¹, Hiroyuki Yoshida¹ (1. JAEA)

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

Sessions

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

[1E01-07] Thermal-Hydraulics in Fuels

(1)Outline of research plan

(2)Test plan for measurement of cross-flow behavior in two-subchannel under rated condition of BWRs

(3)Experiments of subcooled boiling flow through a vertical double wall channel under atmospheric condition

(15)Influence of Rod-Pitch on Void Fraction Distribution in an Unheated 5 x 5 Rod Bundle

(2)Measurement of steam-water two-phase flow under high temperature and pressure conditions

[1E08-12] Severe Accident of Fukushima Daiichi 1

(90)Sensitivity analysis of Fukushima Daiichi unit 1 ex-vessel scenario by the SAMPSON code

(91)Evaluation of Debris Spreading Conditions by Plant Sensitivity Analyses

(92)Fukushima Daiichi Unit 2 plant analysis using SAMPSON/POOL3D

(93)Comprehensive evaluation for debris distribution in Unit-2 by SAMPSON Severe Accident Code

(94)Long term sensitivity analysis of Fukushima Daiichi Unit 3 by the SAMPSON code

[1E13-17] Severe Accident of Fukushima Daiichi 2

(95)Evaluation of Inflow of Venting Gas of Unit 3 into Unit 4 using GOTHIC

(96)CRD housing failure experiment at the KAERI VESTA facility

(97)Assessment of "SAMPSON/DCA" Heat Transfer Models between relocated molten core and RPV lower head wall

(98)Discussion in the accident progression behavior in the early stage of the Unit 1 accident based on dose rate data

[1E18-20] CCFL

(1)Correlation of Interfacial Friction for one-region computation

(2)Measurement of interfacial friction factor

[2E01-04] Phase Change

[2E05-09] Thermal Hydraulics Simulation 1

Measurement and understanding of thermal hydraulics phenomena about thermal stratification

Development of evaluation method for cavity flow penetration depth

Comparison of detailed simulation and results of visualization in a simplified system

[2E10-14] Thermal Hydraulics in Fast Reactor 1

Study on applicability of temperature fluctuation intensity estimation method to triple parallel jets sodium test

Applicability of Vortex Model Based Evaluation on Vortex Type Gas Entrainment

Flow Visualization Experiments Simulating Operation of Decay Heat Removal Systems under a Severe Accident

(1)Measurement of gas-liquid two-phase flow in a simulated debris bed

[2E15-18] Thermal Hydraulics in Fast Reactor 2

(1)Overall plan for development of simulations systems

(2)Conceptual design of multi-level simulation system and development plan

(3)Conceptual design of multi-scenario simulation system and development plan

(4)Experimental database construction for code V&V

[2E19-23] Equipments for Accidents

(5)Evalutation of phase diagrama of debris-refractory layer component (UO2-ZrO2-Zr)

(6)Erosion Resistance of Heat Resistant Materials by Molten Debris

(7)Applicability evaluation of Heat Resistant Materials

(1)Analyses for Fukushima Daiichi Unit 1

(2)Experiments simulating isolation condenser at high pressure and temperature

[3E01-05] Filter and Scrubbing 2

(11)Evaluation of Two-Phase Flow Instability by Visualized Test

(12)Supplession of Two-Phase Flow Instability by Using a Pressurize Orifice

[3E06-09] Thermal Hydraulics Simulation 2

(1)Leak Tests by Vertical Small Canister Model

(2)Leak Test Analysis by Vertical Small Canister Model

Case study of BRI2002

Application of trasient analysis method to evaluation of the thermal hydraulic phenomenon in the reactor vessel

[3E10-13] System Analysis

(2)Development of a Basic Analysis Function

(2)Investigation of Distribution Parameter Using Bubble Layer Thickness Model

[3E14-17] Measurement Techinique

[2F10-16] Thermal Hydraulics at Accidents

(7)Boiling concentration of sea water and blockage with precipitated salt in 5x5 bundle geometry

(8)Characterization of salt deposit layer growth and cladding temperature of heated rod bundles

(19)Improvement of Molybdenum Release Model in the SAMPSON Code

(20)Evaluation of Cs Deposition Distribution in the Primary Circuit by Phebus FPT1 Test Analysis

Effect of initial gas composition (2)

(2)Discussion on Onset Time of Natural Circulation

[2F17-23] Filter and Scrubbing 1

(4)Investigation of Raduation Protection Technology based on the capture test

(5)Improvement of Decontamination Factor by using steam injection

(6)Measurement of Iodomethane diffusivity within MFI and FAU type Zeolite

(7)Evaluation of Sorption Performance of Methyl Iodine by Silver doped Zeolite under Steam Environment

(8)Development of a simple tool to estimate radioactivity trapped by filter element

(9)Estimation of radioactivity of short half-lived fission product nuclides trapped by filter element

(1)Understanding of Two-phase Flow behavior by Water-air and Water-vapor Visualization Experiments

[3F01-04] Corrosion and Risk Evaluation

3. Maintenance management based on reliability evaluation in consideration of responding capability against failure modes

4. An Example for Risk Based Inspection for the Events Originating FAC Related Causes

(5)Evalutation of phase diagrama of debris-refractory layer component (UO₂-ZrO₂-Zr)