Oral Presentation

[1K01-07] Thermal Hydraulics of Sodium-Cooled Fast Reactors

Wed. Sep 7, 2016 10:00 AM - 11:55 AM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Tatsuya Matsumoto (Kyushu Univ.)

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10:00 AM - 10:15 AM

[1K01] Study on the Cooling Process of Decay Heat Removal System for Subassemblies of Sodium-cooled Fast Reactor

*Ayako Ono¹, Takamitsu Onojima¹, Norihiro Doda¹, Yasuhiro Miyake², Hideki Kamide¹ (1.Japan Atomic Energy Agency, 2.NDD corporation)

10:15 AM - 10:30 AM

[1K02] Evaluation of the three-dimensional natural circulation heat removal characteristics in sodium-cooled fast reactor

*Junji Endo¹, Kazuhiro Oyama¹, Osamu Watanabe¹, Norihiro Doda² (1.Mitsubishi FBR Systems, 2.Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[1K03] Study on High Cycle Thermal Fatigue at a Bottom of UIS in a Sodium-cooled Fast Reactor

Influence of Flow Collector of Backup CR Guide Tube

*Jun Kobayashi¹, Toshiki Ezure¹, Masaaki Tanaka¹, Hideki Kamide¹ (1.Japan Atomic Energy Agency)

10:45 AM - 11:00 AM

[1K04] Study on Cavitation Due to Sub-Surface Vortex at Intake of Hot-Leg Pipe in Sodium Cooled Fast Reactor

(9th Report) Development of Cavitation Evaluation Method with Vortex Modeling

*Kei Ito¹, Toshiki Ezure¹, Masaaki Tanaka¹ (1.JAEA)

11:00 AM - 11:15 AM

[1K05] Study on Cavitation Due to Sub-Surface Vortex at Intake of Hot-Leg Pipe in Sodium Cooled Fast Reactor

(10)Application of Sub-Surface Vortex Evaluation Method to Intake of Primary Cold-Leg Pipe

*Hiroyuki Hagiwara¹, Satoshi Hayakawa¹, Toshiki Ezure², Kei Ito², Hiroyuki Ohshima² (1.Mitsubishi FBR Systems, 2.Japan Atomic Energy Agency)

11:15 AM - 11:30 AM

[1K06] Evaluation of Target-wastage for Steam Generator Tubes of Sodium-cooled Fast Reactor

(1)Experimental study on Sodium-water Reaction Simulated the Vertical Tube Bundle in Steam Generator

*Ryota Umeda¹, Kazuhito Shimoyama¹, Akikazu Kurihara¹ (1.Japan Atomic Energy Agency)

11:30 AM - 11:45 AM

[1K07] Evaluation of Target-wastage for Steam Generator Tubes of Sodium-cooled Fast Reactor

(2)Evaluation of Target-wastage Based on the Local Wastage Environment around the Tube

*Akikazu Kurihara¹, Ryota Umeda¹, Kazuhito Shimoyama¹ (1.Japan Atomic Energy Agency)

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

Oral Presentation

[1K08-14] Fuel Assembly Thermal Hydraulics

Wed. Sep 7, 2016 2:45 PM - 4:35 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Yoichi Utanohara (INSS)

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2:45 PM - 3:00 PM

[1K08] Thermal-hydraulic evaluation for fuel assembly design of next generation FBR in Japan

(1)Hydraulic evaluation of large bundle fuel assembly

*Satoshi Hayakawa¹, Kazuhiro Oyama¹, Takayuki Ozawa², Seiichiro Maeda², Hiroyuki Ohshima² (1.MFBR, 2.JAEA)

3:00 PM - 3:15 PM

[1K09] Thermal-hydraulic evaluation for fuel assembly design of next generation FBR in Japan

(2)Local temperature increase evaluation of fuel cladding tubes by a spacer wire

*Hironori Nakamura¹, Kazuhiro Oyama¹, Tomoaki Ogata², Takayuki Ozawa³, Seiichiro Maeda³ (1.MFBR, 2.MHI, 3.JAEA)

3:15 PM - 3:30 PM

[1K10] Thermal-hydrauric evaluation of large bundle fuel assembly design of next generation FBR in Japan

(3)Numerical analysis for entrance nozzle of fuel assembly

*Osamu Watanabe¹, Satoshi Hayakawa¹, Iwao Ikarimoto³, Hiroyuki Ohshima² (1.Mitsubishi FBR Systems, Inc., 2.Japan Atomic Energy Agency, 3.Mitsubishi Heavy Industries, Ltd.)

3:30 PM - 3:45 PM

[1K11] Natural Convection Heat Transfer from Vertical 5x5 Rod Bundles in Liquid Sodium

*Koichi Hata¹, Katsuya FUKUDA¹, Tohru MIZUUCHI² (1.Graduate School of Maritime Sciences, Kobe University , 2.Institute of Advanced Energy, Kyoto University)

3:45 PM - 4:00 PM

[1K12] Experiments on Influences of Injecting Seawater and Boric Acid under Severe Accident Conditions

(6)Void-fraction distribution of salt-water pool-boiling in 5x5 bundle geometry

*Masahiro Furuya¹, Hiroki Takiguchi¹, Takahiro Arai¹, Kensetsu Shirakawa¹ (1.CRIEPI)

4:00 PM - 4:15 PM

[1K13] Thermal hydraulics in reactor core under rod bundle uncovery conditions

(12)Influence of rod-pitch on void fraction distribution in rod bundle under high pressure conditions

*Kenichi Katono¹, Kiyoshi Fujimoto¹, Goro Aoyama¹, Yuma Nagasawa¹, Takuji Nagayoshi¹, Takahiro Arai² (1.Hitachi-GE Nuclear Energy, 2.Central Research Institute of Electric Power Industry)

4:15 PM - 4:30 PM

[1K14] Thermal-hydraulics in reactor core under rod bundle uncovery conditions

(13)Void fraction measurement in 5×5 heated rod bundle at low flow rate and high pressure conditions using High-energy X-ray CT

*Takahiro Arai¹, Masahiro Furuya¹, Kenetsu Shirakawa¹, Yoshihisa Nishi¹ (1.Central Research Institute of Electric Power Industry)

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

Oral Presentation

[1K15-18] Behavior in Containment Vessel

Wed. Sep 7, 2016 4:35 PM - 5:40 PM Room K (Kumume City Plaza - Assembly Room 1)

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

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4:35 PM - 4:50 PM

[1K15] System Response Test with the Horizontal PCCS

(5)System Response Test for the advanced PCCS

*masato yamada¹, mika tahara¹, keiji matsumoto¹, masato uchida², koji nishida³ (1.Toshiba corporation, 2.The japan Atomic power conpany, 3.Hitachi-GE nuclear energy)

4:50 PM - 5:05 PM

[1K16] System Response Test with the Horizontal PCCS

(6)System Response Test Analysis

*Mika Tahara¹, Masato Yamada¹, Keiji Matsumoto¹, Masato Uchita³, Kouji Nishida² (1.TOSHIBA, 2.HITACHI GE, 3.JAPC)

5:05 PM - 5:20 PM

[1K17] CIGMA experiment CC-PL-04 on thermal hydraulics behavior in containment vessel by outer surface cooling

(1)Experimental results and RELAP5 analysis

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

5:20 PM - 5:35 PM

[1K18] CIGMA experiment CC-PL-04 on thermal hydraulics behavior in containment vessel by outer surface cooling

(2)CFD anlysis

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

Time reserved for Chair （5:35 PM - 5:40 PM）

Oral Presentation

[1K19-22] Severe Accident

Wed. Sep 7, 2016 5:40 PM - 6:45 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Masahiro Furuya (CRIEPI)

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5:40 PM - 5:55 PM

[1K19] Development of Numerical Simulation Method for Relocation Behavior of Molten Materials in Nuclear Reactors

(8)Interface Behavior of Simulated Molten Fluid in Slope Part

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

5:55 PM - 6:10 PM

[1K20] Study on Quench Behavior at Core Disruptive Accident for Fast Breeder Reactor

(31)Dominant conditions of surface solidification on a melt jet

*Yuzuru Iwasawa¹, Yutaka Abe¹, Akiko Kaneko¹, Tetsuya Kanagawa¹, Shimpei Saito¹, Hiroshi Sakaba², Kazuya Koyama³, Hideki Nariai¹ (1.Univ. of Tsukuba, 2.MHI, 3.MFBR)

6:10 PM - 6:25 PM

[1K21] Development of Numerical Simulation for Jet Break up Behavior in Complicated Structure of BWR Lower Plenum

(14)Effect of Inlet Velocity on Jet Falling Behavior in Complicated Structures

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

6:25 PM - 6:40 PM

[1K22] Development of Numerical Simulation for Jet Breakup Behavior in Complicated Structure of BWR Lower Plenum

(15)Evaluation of the Molten Falling Behavior in Single-Channel by the High Resolution Analysis

*Takayuki Suzuki¹, Hiroyuki Yoshida¹, Yuki Narushima², Akiko Kaneko², Yutaka Abe² (1.Japan Atomic Energy Agency, 2.University of Tsukuba)

Time reserved for Chair （6:40 PM - 6:45 PM）

Oral Presentation

[2K01-06] Two-Phase Flow and Phase Change 1

Thu. Sep 8, 2016 9:30 AM - 11:10 AM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Michio Murase (INSS)

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9:30 AM - 9:45 AM

[2K01] Characteristics of Heating and Microwave under Microwave Heating

*FUMINORI CHONAN¹, Yutaka Abe¹, Akiko Kanako¹, Tetsuya Kanagawa¹, Shunya Fujita¹, Tomohisa Yuasa¹, Tomoomi Segawa², Yoshikazu Yamada² (1.University of Tsukuba, 2.Japan Atomic Energy Agancy )

9:45 AM - 10:00 AM

[2K02] Droplet generation during liquid jet collision onto solid surface

*Naoki Oya¹, Yi Zhan¹, Koji Enoki¹, Tomio Okawa¹, Mitsuhiro Aoyagi², Shuji Ohno², Takashi Takata² (1.The university of electro-communications, 2.Japan Atomic Energy Agency)

10:00 AM - 10:15 AM

[2K03] Study on Seawater Pool Boiling Heat Transfer

(2)Mechanism of Sea Salt Deposition on Heat Transfer Surface

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

10:15 AM - 10:30 AM

[2K04] Evaluation of jet shape and fluid force generated from ruptured high temperature and high pressure water pipe

*Shiro Takahashi¹, Noriyuki Takamura ², Qiang Xu² (1.Hitachi, 2.Hitachi-GE)

10:30 AM - 10:45 AM

[2K05] Scale effect on the operating criteria of supersonic steam injector

*Masaya Fujishiro¹, Yutaka Abe¹, Akiko Kaneko¹, Tetsuya Kanagawa¹ (1.University of tsukuba)

10:45 AM - 11:00 AM

[2K06] Development of Prediction Technology of Two-Phase Flow Dynamics under Earthquake Acceleration

(32)A rising single bubble behavior under Horizontal Structure Vibration

*Akifumi Miyazaki¹, Tetsuya Kanagawa¹, Akiko Kaneko¹, Hideaki Monji¹, Hiroyuki Yoshida², Yutaka Abe¹ (1.University of Tsukuba, 2.AESJ)

Time reserved for Chair （11:00 AM - 11:10 AM）

Oral Presentation

[2K07-09] Accident Progression Analysis

Thu. Sep 8, 2016 11:10 AM - 12:00 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Tomio Okawa (UEC)

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11:10 AM - 11:25 AM

[2K07] Construction of PWR analysis model in MAAP5.01 code

Part (2)Parameter survey on the pressurizer relief valve operation in the TMLB' sequence

*Yoshihisa Nishi¹, Satoshi Nishimura¹, Shota Soga¹, Toshihiko Miyamoto², Yuusuke Katakami², Hiroyuki Sakamoto³, Kenta Kobayashi³, Tomohiro Kodaira³ (1.CRIEPI, 2.SEPCO, 3.HEPCO)

11:25 AM - 11:40 AM

[2K08] Evaluation about the spent fuel pool accident analysis by MAAP

(1)Spray cooling properties evaluation in loss of coolant accident (LOCA)

*Kenichi Kanda¹, Satoshi Nishimura¹, Masaaki Satake¹, Kazuma Abe¹, Masahiro Furuya¹, Yoshihisa Nishi¹ (1.Central Research Institute of Electric Power Industry)

11:40 AM - 11:55 AM

[2K09] ROSA/LSTF Test on Nitrogen Gas Behavior during Reflux Cooling and RELAP5 Analysis

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

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

Oral Presentation

[2K10-15] Fukushima Daiichi NPP Accident 1

Thu. Sep 8, 2016 2:45 PM - 4:20 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Hiroyuki Yoshida (JAEA)

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2:45 PM - 3:00 PM

[2K10] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(76)Results of Penetration Tube Melt Tests Performed at KAERI

*Masanori Naitoh¹, Hidetoshi Okada¹, Marco Pellegrini¹ (1.IAE)

3:00 PM - 3:15 PM

[2K11] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(77)Validation of Debris Freezing Model in a penetration tube against the KAERI Experiment

*Suzuki Hiroyuki¹, Marco Pellegrini¹, Suzuki Hiroaki¹, Naitoh Masanori¹ (1.Institute of Applied Energy)

3:15 PM - 3:30 PM

[2K12] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

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

*Hiroaki Suzuki¹, Masanori Naitoh¹, Marco Pellegrini¹, Hiroyuki Suzuki¹, Chiaki Kino¹ (1.The Institute of Applied Energy )

3:30 PM - 3:45 PM

[2K13] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

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

*Chiaki Kino¹, Hiroaki Suzuki¹, Hidetoshi Okada¹, Masanori Naito¹ (1.The Institute of Applied Energy )

3:45 PM - 4:00 PM

[2K14] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(80)Analysis of the accident at Fukushima Daiichi unit 3 by the SAMPSON code

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

4:00 PM - 4:15 PM

[2K15] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(81)Ex-vessel phenomena analysis of the accident in the Fukushima Daiichi nuclear power station Unit 1 using DSA-CVPA modules of SAMPSON

*Mirco Di Giuli¹, Hyrouchi Suzuki¹, Marco Pellegrini¹, Masaori Naitoh¹ (1.IAE)

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

Oral Presentation

[2K16-20] Fukushima Daiichi NPP Accident 2

Thu. Sep 8, 2016 4:20 PM - 5:40 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Yoshiro Kudo (NRA)

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4:20 PM - 4:35 PM

[2K16] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(82)Assessment of SAMPSON Severe Accident Code Modeling against MELCOR

*Ayumi Itoh¹, Marco Pellegrini¹, Hidetoshi Okada¹, Masanori Naitoh¹ (1.The Institute of Applied Energy)

4:35 PM - 4:50 PM

[2K17] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(83)Estimation of Accident Progression of unit 3 based on Water Level Indicator Readings

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

4:50 PM - 5:05 PM

[2K18] Development of Evaluation Method for Air Cooling of Fuel Debris

(2)Preliminary analysis of the natural convection cooling performance

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

5:05 PM - 5:20 PM

[2K19] Study on criteria of thermal stratification in suppression chamber

*Daisuke YAMAUCHI¹, Nejdet ERKAN², Byeongnam JO¹, Koji OKAMOTO² (1.Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 2.Nuclear Professional School, Schcool of Engineering, The University of Tokyo)

5:20 PM - 5:35 PM

[2K20] development status of drying simulation code for waste storage

*terada atsuhiko¹, isao yamagishi¹, ryutaro hino¹ (1.Japan Atomic Energy Agency)

Time reserved for Chair （5:35 PM - 5:40 PM）

Oral Presentation

[2K21-23] Thermal Fatigue Evaluation

Thu. Sep 8, 2016 5:40 PM - 6:30 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Hiroyuki Ohshima (JAEA)

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5:40 PM - 5:55 PM

[2K21] Assessments for high-cycle thermal fatigue at a mixing tee pipe

Part 1:Characteristics of thermal stress by wall temperature measurement test

*Koji Miyoshi¹, Yoichi Utanohara¹, Masayuki Kamaya¹ (1.Institute of Nuclear Safety System)

5:55 PM - 6:10 PM

[2K22] Assessments of High-Cycle Thermal Fatigue at a Mixing Tee Pipe

Part 2:Numerical simulation of the temperature fluctuation

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

6:10 PM - 6:25 PM

[2K23] Assessments of high-cycle thermal fatigue at a mixing tee pipe

Part 3:Fatigue damage assessment

*Masayuki Kamaya¹, Koji Miyoshi¹, Youichi Utanohara¹ (1.Institute of Nuclear Safety Sysmte, Inc.)

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

Oral Presentation

[3K01-05] Two-Phase Flow and Phase Change 2

Fri. Sep 9, 2016 9:30 AM - 10:55 AM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Susumu Yamashita(JAEA)

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9:30 AM - 9:45 AM

[3K01] Effect of various parameters on the bubble size distribution in water subcooled flow boiling

*Kazuhiro Kaiho¹, Shintaro Sakamoto¹, Nian gang¹, Koji Enoki¹, Tomio Okawa¹ (1.The University of Electro-Communications)

9:45 AM - 10:00 AM

[3K02] Interfacial Friction Factor for Counter-current Gas-Liquid Flow in Vertical Pipes

*Takayoshi Kusunoki¹, Michio MURASE¹, Yasunori YAMAMOTO¹, Akio TOMIYAMA², Katsuya MORI² (1.INSS, 2.Kobe University)

10:00 AM - 10:15 AM

[3K03] Countercurrent Flow Limitation in the Vertical Pipe of a Pressurizer Surge Line

(1)Effects of Diameters

*Yasunori Yamamoto¹, Michio Murase¹, Katsuya Mori², Akio Tomiyama² (1.INSS, 2.Kobe University)

10:15 AM - 10:30 AM

[3K04] Countercurrent Flow Limitation in the Vertical Pipe of a Pressurizer Surge Line

(2)Effects of Fluid Properties

*Michio Murase¹, Yasunori Yamamoto¹, Katsuya Mori², Akio Tomiyama² (1.INSS, 2.Kobe U.)

10:30 AM - 10:45 AM

[3K05] Measurement of the diameter distribution of the droplets by a portable spray

Koji Ishizaki¹, Hayata Shimmura¹, Yuusuke Kokubo¹, *Chihiro Nishizaki², Yasushi Makino², Hironori Noguchi² (1.KEPCO, 2.MHI)

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

Oral Presentation

[3K06-09] Source Term

Fri. Sep 9, 2016 10:55 AM - 12:00 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Akira Nakamura (INSS)

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10:55 AM - 11:10 AM

[3K06] Dose evaluation in a BWR reactor building with MAAP-DOSE.

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

11:10 AM - 11:25 AM

[3K07] Evaluation of Fission Products Released during the NPP Severe Accident

14.Evaluation of FP behavior in plants based on the Backward Evaluation Method

*Hide Okada¹, Shunsuke Uchida¹, Hidetoshi Karasawa¹, Ayumi Itoh¹, Marco Pellegrini¹, Masanori Naitoh¹ (1.The Institute of Applied Energy)

11:25 AM - 11:40 AM

[3K08] Evaluation of Fission Products Released during the NPP Severe Accident

15.Evaluation of FP behavior in S/P based on dose rate measured with CAMS

*Shunsuke Uchida¹, Hide Okada¹, Hidetoshi Karasawa¹, Ayumi Itoh¹, Marco Pellegrini¹, Masanori Naitoh¹ (1.The Institute of Applied Energy)

11:40 AM - 11:55 AM

[3K09] Evaluation of Fission Products Released during the NPP Severe Accident

16.FP release from S/P under decompression boiling

*Hidetoshi Karasawa¹, Shunsuke Uchida¹, Hidetoshi Okada¹, Ayumi Ito¹, Marco Pellegrini¹, Masanori Naito¹ (1.Institute of Applied Energy)

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

Oral Presentation

[3K10-12] Filtered Vent

Fri. Sep 9, 2016 2:45 PM - 3:35 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Hidetoshi Okada (IAE)

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2:45 PM - 3:00 PM

[3K10] Development of evaluation method for two-phase flow in Venturi scrubber for filtered venting

(3)Measurement of liquid film thickness distribution in flow direction by the laser displacement meter

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

3:00 PM - 3:15 PM

[3K11] Development of evaluation method for two-phase flow in Venturi scrubber for filtered venting

(4)Visualization of droplets generation on film flow in diffuser

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

3:15 PM - 3:30 PM

[3K12] Gas phase jet behavior during pool scrubbing

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

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

Sessions

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

[1K01-07] Thermal Hydraulics of Sodium-Cooled Fast Reactors

Influence of Flow Collector of Backup CR Guide Tube

(9th Report) Development of Cavitation Evaluation Method with Vortex Modeling

(10)Application of Sub-Surface Vortex Evaluation Method to Intake of Primary Cold-Leg Pipe

(1)Experimental study on Sodium-water Reaction Simulated the Vertical Tube Bundle in Steam Generator

(2)Evaluation of Target-wastage Based on the Local Wastage Environment around the Tube

[1K08-14] Fuel Assembly Thermal Hydraulics

(1)Hydraulic evaluation of large bundle fuel assembly

(2)Local temperature increase evaluation of fuel cladding tubes by a spacer wire

(3)Numerical analysis for entrance nozzle of fuel assembly

(6)Void-fraction distribution of salt-water pool-boiling in 5x5 bundle geometry

(12)Influence of rod-pitch on void fraction distribution in rod bundle under high pressure conditions

(13)Void fraction measurement in 5×5 heated rod bundle at low flow rate and high pressure conditions using High-energy X-ray CT

[1K15-18] Behavior in Containment Vessel

(5)System Response Test for the advanced PCCS

(6)System Response Test Analysis

(1)Experimental results and RELAP5 analysis

(2)CFD anlysis

[1K19-22] Severe Accident

(8)Interface Behavior of Simulated Molten Fluid in Slope Part

(31)Dominant conditions of surface solidification on a melt jet

(14)Effect of Inlet Velocity on Jet Falling Behavior in Complicated Structures

(15)Evaluation of the Molten Falling Behavior in Single-Channel by the High Resolution Analysis

[2K01-06] Two-Phase Flow and Phase Change 1

(2)Mechanism of Sea Salt Deposition on Heat Transfer Surface

(32)A rising single bubble behavior under Horizontal Structure Vibration

[2K07-09] Accident Progression Analysis

Part (2)Parameter survey on the pressurizer relief valve operation in the TMLB' sequence

(1)Spray cooling properties evaluation in loss of coolant accident (LOCA)

[2K10-15] Fukushima Daiichi NPP Accident 1

(76)Results of Penetration Tube Melt Tests Performed at KAERI

(77)Validation of Debris Freezing Model in a penetration tube against the KAERI Experiment

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

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

(80)Analysis of the accident at Fukushima Daiichi unit 3 by the SAMPSON code

(81)Ex-vessel phenomena analysis of the accident in the Fukushima Daiichi nuclear power station Unit 1 using DSA-CVPA modules of SAMPSON

[2K16-20] Fukushima Daiichi NPP Accident 2

(82)Assessment of SAMPSON Severe Accident Code Modeling against MELCOR

(83)Estimation of Accident Progression of unit 3 based on Water Level Indicator Readings

(2)Preliminary analysis of the natural convection cooling performance

[2K21-23] Thermal Fatigue Evaluation

Part 1:Characteristics of thermal stress by wall temperature measurement test

Part 2:Numerical simulation of the temperature fluctuation

Part 3:Fatigue damage assessment

[3K01-05] Two-Phase Flow and Phase Change 2

(1)Effects of Diameters

(2)Effects of Fluid Properties

[3K06-09] Source Term

14.Evaluation of FP behavior in plants based on the Backward Evaluation Method

15.Evaluation of FP behavior in S/P based on dose rate measured with CAMS

16.FP release from S/P under decompression boiling

[3K10-12] Filtered Vent

(3)Measurement of liquid film thickness distribution in flow direction by the laser displacement meter

(4)Visualization of droplets generation on film flow in diffuser

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