＊Ryo Kawata¹, Yohei Ohara¹, Takuya Fujimoto¹, Satoshi Nishida¹, Koji Morita¹, Liancheng Guo², Hirotaka Tagami³, Tohru Suzuki³ (1.Kyushu university, 2.The Karlsruhe Institute of Technology, 3.JAEA)

3:15 PM - 3:30 PM

[1F11] Fundamental Study on Sloshing Behavior of Disrupted Core Pool

Index for reactivity insertion caused by fuel motion

＊Koji Morita¹, Sho Fuchita¹, Yuki Emura¹, Tatsuya Matsumoto¹, Isao Tatewaki¹ (1.Kyushu University)

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

Oral Presentation

[1F12-15] Safety evaluations for a fast reactor 3

Sat. Mar 26, 2016 3:35 PM - 4:40 PM Room F (Lecture Rooms B B201)

Chair: Hitoshi Muta (Tokyo City Univ.)

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3:35 PM - 3:50 PM

[1F12] Study on Prevention of Loss of Heat Removal Function for Fast Reactor

(1)Approach toward Robust Preventive Function against Loss of Heat Removal

＊Kenichi Kurisaka¹, Hiroyuki Nishino¹, Masutake Sotsu¹ (1.JAEA)

3:50 PM - 4:05 PM

[1F13] Study on Prevention of Loss of Heat Removal Function for Fast Reactor

(2)Effectiveness of Natural Circulation Cooling

＊Fumiaki YAMADA¹, Takero MORI¹ (1.JAEA)

4:05 PM - 4:20 PM

[1F14] Study on Prevention of Loss of Heat Removal Function for Fast Reactor

Effectiveness of Countermeasures for Making-up Reactor Sodium Level

＊Kazuaki Matsui¹, Kazuo Yoshimura¹, Kosuke Aizawa¹, Kenta Ichikawa¹, Fumiaki Yamada¹ (1.JAEA)

4:20 PM - 4:35 PM

[1F15] Study on Prevention of Loss of Heat Removal Function for Fast Reactor

(4)Effectiveness of Alternative Decay Heat Removal System

＊Kazuo Yoshimura¹, Kosuke Aizawa¹, Kenta Ichikawa¹, Takero Mori¹, Fumiaki Yamada¹ (1.JAEA)

Time reserved for Chair （4:35 PM - 4:40 PM）

Oral Presentation

[1F16-20] Safety evaluations for a fast reactor 4

Sat. Mar 26, 2016 4:40 PM - 6:00 PM Room F (Lecture Rooms B B201)

Chair: Koji Morita (Kyushu Univ.)

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4:40 PM - 4:55 PM

[1F16] Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors

(1)Summary of SAS4A code and CABRI in-pile experiments

＊Yoshitaka FUKANO¹, Yuya IMAIZUMI¹, Naonori YOSHIOKA², Hisashi AKAHORI² (1.JAEA, 2.NESI Inc.)

4:55 PM - 5:10 PM

[1F17] Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors

(2)Analysis of LTX test

＊Hisashi Akahori¹, Yoshitaka FUKANO² (1.NESI Inc., 2.JAEA)

5:10 PM - 5:25 PM

[1F18] Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors

(3)Analysis of LT4 test

＊Naonori Yoshioka¹, Yoshitaka Fukano² (1.NESI, 2.JAEA)

5:25 PM - 5:40 PM

[1F19] Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors

(4)Analysis of EFM1 test

＊Yuya Imaizumi¹, Yoshitaka Fukano¹ (1.JAEA)

5:40 PM - 5:55 PM

[1F20] Development of Integrated Core Disruptive Accident Analysis Code, ASTERIA-FBR

(9)Analysis of CABRI-BI3 Experiment

＊Hiroki Watanabe¹, Tomoko Ishizu¹ (1.Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority)

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

Oral Presentation

[1I01-04] Fukushima Daiichi Nuclear Power Plant Accident

Sat. Mar 26, 2016 10:00 AM - 11:00 AM Room I (Lecture Rooms B B200)

Chair: Naoyuki Ishida (Hitachi)

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10:00 AM - 10:15 AM

[1I01] Analysis of Recovery Actions in Fukushima Daiichi NPS Accident (3)

＊Fumiya Tanabe¹ (1.SOCTEX)

10:15 AM - 10:30 AM

[1I02] Operation Side Ideas of the Searching of the Nuclear Reactor Conditions at SBO

(2)Behavior of Pressure Record at the Operation of IC in the Fukushima Reports

＊Kazuo Watanabe¹, Kiyoshi Yoneyama² (1.WNR-Cx Watanabe Lab., 2.H.O.Yoneyama)

10:30 AM - 10:45 AM

[1I03] Operation Side Ideas of the Searching of the Nuclear Reactor Conditions at SBO

(3)Behavior of Water Level Record at the Operation of IC in the Fukushima Reports

＊Kiyoshi Yoneyama¹, Kazuo Watanabe² (1.H.O.YONEYAMA, 2.WNR-Cx Watanabe Lab.)

10:45 AM - 11:00 AM

[1I04] Operation Side Ideas of the Searching of the Nuclear Reactor Conditions at SBO

(4)A Suggestion to Understand an IC Operation Story at the Fukushima No.1 Reactor
- That was really performed with SRV and HPCI -

＊Kiyoshi Yoneyama¹, Kazuo Watanabe² (1.H.O.YONEYAMA, 2.WNR-Cx Watanabe Lab.)

Oral Presentation

[1I05-08] Philosophy of the safety

Sat. Mar 26, 2016 11:00 AM - 12:00 PM Room I (Lecture Rooms B B200)

Chair: Koichi Nakamura (CRIEPI)

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11:00 AM - 11:15 AM

[1I05] Development of the guideline of Japan version Safety Assessment Report (JSAR)

＊Yuichi Shimada¹, Satoshi Kurata¹, Katsuyuki Kumasaka¹, Masayuki Tabata¹, Goro Imada¹, Yoshiaki Suzuki¹, Kenichi Yasuda⁴, Mitsuhiro Kano³, Kouichi Kondo², Kazutoshi Eto⁵ (1.Japan Nuclear Safety Institute , 2.Toshiba, 3.MHI, 4.Hitachi-GE, 5.Kyushu Electric Power Company)

11:15 AM - 11:30 AM

[1I06] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 1: Project Plan

＊Tsuyoshi Takada¹, Tatsuya Itoi¹, Takenori Hida¹, Osamu Furuya², Ken Muramatsu², Hitoshi Muta², Satoshi Fujita³, Keisuke Minagawa⁴, Hidekado Yamano⁵, Akemi Nishida⁵ (1.School of Engineering, the University of Tokyo, 2.Tokyo City University, 3.Tokyo Denki University, 4.Saitama Institue of Technology, 5.Japan Atomic Energy Agency)

11:30 AM - 11:45 AM

[1I07] Concept on nuclear risks and mesures

(1)Nuclear safety design and operation

＊Hiroshi Ando¹, Hiroshi Ujita², Ken Muramatsu³, Kenji Tominaga⁴ (1.INSS, 2.CIGS, 3.Tokyo City University, 4.JANSI)

11:45 AM - 12:00 PM

[1I08] Concept on nuclear risks and measures - For a dialog with society

(2)Rational safety consideration based on risk concept

＊Hiroshi Ujita¹, Ken Muramatsu², Kenji Tominaga³, Hiroshi Ando⁴ (1.The Canon Institute for Global Studies, 2.Tokyo City University, 3.Japan Nuclear Safety Institute, 4.Institute of Nuclear Safety System)

Oral Presentation

[1I09-12] Severe Accident 1

Sat. Mar 26, 2016 2:45 PM - 3:50 PM Room I (Lecture Rooms B B200)

Chair: Shuji Ohno (JAEA)

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2:45 PM - 3:00 PM

[1I09] Development of Dry-Well Cooler for severe accident

(1)Overview

＊Ryohei Watanabe¹, Kouji Andou¹, Daiki Sato¹, Naoyuki Ishida², Naohisa Watahiki², Hideaki Hosoi² (1.Hitachi GE,Ltd., 2.Hitachi,Ltd.)

3:00 PM - 3:15 PM

[1I10] Development of Dry-Well Cooler for an severe accident

(2)Elemental Heat Transfer Tests using 3-rows and 5-levels Tube Bundle

＊Naoyuki Ishida¹, Naohisa Watahiki¹, Ryohei Watanabe², Daiki Sato², Kouji Andou², Hideaki Hosoi¹ (1.Hitachi, 2.Hitachi GE)

3:15 PM - 3:30 PM

[1I11] Consideration of error reduction methods for aerosol decontamination factor measurement in pool scrubbing experiment

＊Haomin Sun¹, Yasuteru Sibamoto¹, Yuria Okagaki¹, Taisuke Yonomoto¹ (1.JAEA)

3:30 PM - 3:45 PM

[1I12] Bayesian optimization analysis of containment venting strategies in a severe accident

＊Xiaoyu Zheng¹, Jun Ishikawa¹, Yu Maruyama¹ (1.Japan Atomic Energy Agency)

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

Oral Presentation

[1I13-16] Severe Accident 2

Sat. Mar 26, 2016 3:50 PM - 4:55 PM Room I (Lecture Rooms B B200)

Chair: Hiroshi Ando (INSS)

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3:50 PM - 4:05 PM

[1I13] Development of Hydrogen Treatment System in Severe Accident

(4)Study of Hydrogen Treatment with Metal Oxides

＊Akira Yamada¹, Motoshige Yagyu¹, Masato Okamura¹, Toshihiro Yoshii¹, Chikako Iwaki¹, Daigo Kittaka¹, Masashi Tanabe¹ (1.TOSHIBA CORPORATION)

4:05 PM - 4:20 PM

[1I14] Development of Hydrogen Treatment System in Severe Accident

(5)Study on the Hydrogen Treatment Characteristics of a Processing Unit

＊CHIKAKO IWAKI¹, DAIGO KITTAKA¹, TOSHIHIRO YOSHII¹, MOTOSHIGE YAGYU¹, MASATO OKAMURA¹, MASASHI TANABE¹ (1.Toshiba)

4:20 PM - 4:35 PM

[1I15] Development of Artificial Intelligence Integrated Adsorption Simulation Method for Nuclear-Related Adsorption Process.

＊Masayuki Miyano¹, Yukiko Obara¹, Manami Sato¹, Patrick Bonnaud¹, Ryuji Miura¹, Ai Suzuki¹, Naoto Miyamoto¹, Nozomu Hatakeyama¹, Akira Miyamoto¹ (1.Tohoku University)

4:35 PM - 4:50 PM

[1I16] AgX and AgR radioiodine adsorbents as severe accident countermeasures

＊Toshiki Kobayashi¹, Jifeng WANG¹, Yoshihiro ISHIKAWA¹, Yuichiro UZUYAMA¹, Koji ENDO¹ (1.Rasa Industries LTD. Electronic Materials Div. )

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

Oral Presentation

[1I17-20] Accident in LWR 1

Sat. Mar 26, 2016 4:55 PM - 6:00 PM Room I (Lecture Rooms B B200)

Chair: Nozomu Hatakeyama (Tohoku Univ.)

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4:55 PM - 5:10 PM

[1I17] Severe accidents analyses of LWR plant behavior with simulator of RELAP/SCDAPSIM code and graphical interface.

(1)Analysis of BWR plant.

＊Daiki Nunokawa¹, Mitsuyo Tuji¹, Kameyama Takanori² (1.Graduate School of Tokai Univ., 2.Tokai Univ.)

5:10 PM - 5:25 PM

[1I18] Severe accidents analyses of LWR plant behavior with simulator of RELAP/SCDAPSIM code and graphical interface.

(2)Analysis of PWR plant.

＊Mitsuyo Tsuji¹, Daiki Nunokawa¹, Takanori Kameyama² (1.Graduate school of Tokai Univ., 2.Tokai Univ.)

5:25 PM - 5:40 PM

[1I19] Analysis of boil-off level using RELAP5-3D

＊Takahiro YANO¹, Hiroyasu MOCHIZUKI¹, Tadas Kaliatka² (1.University of Fukui , 2.Lithuanian Energy Institute)

5:40 PM - 5:55 PM

[1I20] Experiments and Simulation of Steam Injector for Passive Core-Injection System

＊XINGYONG ZHNAG¹, Hiroto Endo¹, Shuichiro Miwa¹, Michitsugu Mori¹, Hiroto Sakashita¹ (1.Hokkaido Univ.)

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

Oral Presentation

[2P01-03] Seismic analysis of FBR

Sun. Mar 27, 2016 9:30 AM - 10:20 AM Room P (Lecture Rooms C C200)

Chair: Hidemasa Yamano (JAEA)

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9:30 AM - 9:45 AM

[2P01] Development of Seismic Evaluation Method Considering three Dimensional Fuel Assembly Displacement in FBR Core

(1)Development of the Core Element Vibration Analysis Code in Three Dimension

＊Akihisa Iwasaki¹, Kazuo Hirota¹, Masatsugu Monde¹, Iwao Ikarimoto¹, Shinichiro Matsubara¹ (1.Mitsubishi heavy industries, LTD.)

9:45 AM - 10:00 AM

[2P02] Development of Seismic Evaluation Method Considering Three Dimensional Fuel Assembly Displacement in FBR Core

(2)Development of Seismic Reactivity Analysis Method Considering Three Dimensional Fuel Assembly Displacement

＊Yohei Kamiyama¹, Kazuki Kirimura¹, Kazuya Yamaji¹, Shinya Kosaka¹ (1.Mitsubishi Heavy Industries, Ltd.)

10:00 AM - 10:15 AM

[2P03] Development of Seismic Evaluation Method Considering Three Dimensional Fuel Assembly Displacement in FBR Core

(3)Validation of Seismic Reactivity Analysis Method Considering Three Dimensional Fuel Assembly Displacement

＊Toru Tsuboi¹, yuto homma¹, Yohei Kamiyama¹, Shinichiro Matsubara¹ (1.Mitsubishi Heavy Industries, Ltd.)

Time reserved for Chair （10:15 AM - 10:20 AM）

Oral Presentation

[2P04-09] Accident in LWR 2

Sun. Mar 27, 2016 10:20 AM - 12:00 PM Room P (Lecture Rooms C C200)

Chair: Kennichi Kurisaka (JAEA)

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10:20 AM - 10:35 AM

[2P04] A simple assessment scheme for severe accident consequences using source term parameters

＊Silva Kampanart¹, Koji Okamoto² (1.Thailand Institute of Nuclear Technology, 2.University of Tokyo)

10:35 AM - 10:50 AM

[2P05] Development of Multiscale, Multiphysics Computational Chemistry Methods for the Application to Atomic Energy Technologies

＊Akira Miyamoto¹, Patrick Bonnaud¹, Ryuji Miura¹, Ai Suzuki¹, Naoto Miyamoto¹, Nozomu Hatakeyama¹ (1.Tohoku University)

10:50 AM - 11:05 AM

[2P06] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(1)Development of the evaluation method of a source term risk induced by cesium

＊Hiroshi Endo¹, Koichi Nakamura¹, Keigo Murata ¹, Atsushi Ui¹ (1.CRIEPI )

11:05 AM - 11:20 AM

[2P07] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(2)Evaluations of the cesium release during core damage events due to a large scale LOCA by using severe accident analysis codes

＊KEIGO MURATA¹, Koichi Nakamura¹, Atsushi Ui¹, Hiroshi Endo¹ (1.Central Research Institute of Electric Power Industry)

11:20 AM - 11:35 AM

[2P08] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

Analysis of Characteristics and Issues on Cesium Transportation Models of Severe accident Analysis Codes

＊Koichi Nakamura¹, Keigo Murata¹, Atsushi Ui¹, Hiroshi Endo¹ (1.CRIEPI)

11:35 AM - 11:50 AM

[2P09] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(4)Uncertainty analysis concerning cesium release towards identifying risk profile and safety vulnerabilities

＊Atsushi Ui¹, Kyoko Murakami¹, Keigo Murata¹, Koichi Nakamura¹, Hiroshi Endo¹ (1.CRIEPI)

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

Oral Presentation

[2P10-12] Risk of External Event 1

Sun. Mar 27, 2016 2:45 PM - 3:40 PM Room P (Lecture Rooms C C200)

Chair: Tsuyoshi Takada (Univ. of Tokyo)

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2:45 PM - 3:00 PM

[2P10] Annual Probability of Tornado Missile Strike on Structure using Fujita Model

＊Yuzuru Eguchi¹, Takahiro Murakami¹, Masashi Kuramasu², Hiromaru Hirakuchi¹, Soichiro Sugimoto¹, Yasuo Hattori¹ (1.CRIEPI, 2.The Chugoku Electric Power Co., Inc.)

3:00 PM - 3:15 PM

[2P11] Tornado Effect Assessment of nuclear power plant

＊shinya sato¹ (1.Tohoku Electric Power Co., Inc.)

3:15 PM - 3:30 PM

[2P12] Fragility Evaluation Method for Tsunami Inundation using Monte Carlo Method

Suggestion and Validation Study using Virtual Plant of Fragility Evaluation Method

＊Masaki Ikeda¹, Yuki Naito¹, Akihiro Ootsuki¹, Yukihiro Kirimoto², Masafumi Matsuyama², Yasuki Ootori², Tomoaki Yoshida² (1.Hitachi-GE Nuclear Energy, Ltd., 2.Central Research Institute of Electric Power Industry)

Time reserved for Chair （3:30 PM - 3:40 PM）

Oral Presentation

[2P13-16] Risk of External Event 2

Sun. Mar 27, 2016 3:40 PM - 4:50 PM Room P (Lecture Rooms C C200)

Chair: Tatsuya Itoi (Univ. of Tokyo)

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3:40 PM - 3:55 PM

[2P13] Method of multiple failure initiating events for seismic PRA

(1)Study on Evaluation Method

＊Hiromichi Miura¹, Katsunori Ogura¹, Tsuyoshi Uchida¹, Yuuki Kameko², Ken Muramatsu ², Hitoshi Muta² (1.CRIEPI, 2.TCU)

3:55 PM - 4:10 PM

[2P14] Method of multiple failure initiating events for seismic PRA

(2)Analysis of Model Plant

＊Yuki Kameko¹, KEN Muramatsu¹, Hitoshi Muta¹, Hiromichi Miura², Katsunori Ogura², Tsuyoshi Uchida² (1.Tokyo City University, 2.CRIEPI)

4:10 PM - 4:25 PM

[2P15] Study on reliability of parallel systems subjected to earthquakes

Yasuki Ohtori¹, ＊Ichiro Tamura² (1.CRIEPI, 2.Chugoku Electric Power Company)

4:25 PM - 4:40 PM

[2P16] Improvement of the component fragility evaluation method considering dynamic non-linear building response

＊Hiroyuki Yamada¹, Hiromichi Miura¹, Katsumi Ebisawa¹, Tomoaki Yoshida¹ (1.CRIEPI)

Time reserved for Chair （4:40 PM - 4:50 PM）

Oral Presentation

[2P17-20] PRA

Sun. Mar 27, 2016 4:50 PM - 6:00 PM Room P (Lecture Rooms C C200)

Chair: Yoshiyuki Narumiya (The Kansai Electric Power Co., INC.)

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4:50 PM - 5:05 PM

[2P17] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

＊Hiroyuki Sato¹, Akemi Nishida¹, Osamu Furuya², Ken Muramatsu², Tatsuya Itoi³, Tsuyoshi Takada³, Masayuki Tanabe⁴, Tsuyoshi Yamamoto⁴ (1.Japan Atomic Energy Agency, 2.Tokyo City University, 3.The University of Tokyo, 4.JGC Corporation)

5:05 PM - 5:20 PM

[2P18] Trial calculation of Tsunami PRA including the effect of drawback.

＊hiroaki sonoyama¹, hiroshi abe¹, yoshihiro ooyama², takashi uemura², syuhei matsunaka² (1.TEPCO SYSTEMS CORPORATION, 2.TOKYO ELECTRIC POWER COMPANY)

5:20 PM - 5:35 PM

[2P19] Tsunami PRA of ONAGAWA NPS unit 2

＊Shinsaku Fujita¹, Akira TANAKA¹, Daisuke SATO¹, Masanobu ABE¹, Fumito KUBO², Shota NINOMIYA³ (1.TOHOKU ELECTRIC POWER CO., INC., 2.Tohoku Information Systems Company, Incorporated , 3.TOSHIBA CORPORATION)

5:35 PM - 5:50 PM

[2P20] Development of realistic model related to direct core damage scenarios on Seismic PRA

shinji katou¹, ＊keisuke maeda¹, hiroshi abe¹, yoshihiro ooyama², takashi uemura², syuhei matsunaka² (1.TEPCO SYSTEMS CORPORATION, 2.TOKYO ELECTRIC POWER COMPANY)

Time reserved for Chair （5:50 PM - 6:00 PM）

Oral Presentation

[3P01-06] Safety design for fast reactors

Mon. Mar 28, 2016 9:30 AM - 11:00 AM Room P (Lecture Rooms C C200)

Chair: Tadashi Narabayashi (Hokkaido Univ.)

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9:30 AM - 9:45 AM

[3P01] Studies on the Safety Design Guidelines of Generation-IV Sodium-cooled Fast Reactors

(6)Focal Points of Safety Design Guideline for Structures, Systems and Components

＊Yasushi OKANO¹, Shigenobu KUBO¹, Ryodai NAKAI¹ (1.Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[3P02] Studies on the Safety Design Guidelines of Generation-IV Sodium-cooled Fast Reactors

(7)Focal Points of Safety Design Guideline for Reactor Core

＊Akihiro Tani¹, Taro Kan¹, Yasushi Okano² (1.MITSUBISHI FBR SYSTEMS, 2.JAPAN ATOMIC ENERGY AGENCY)

10:00 AM - 10:15 AM

[3P03] Studies on the Safety Design Guidelines of Generation-IV Sodium-cooled Fast Reactors

(8)Focal Points of Safety Design Guideline for Reactor Coolant System

＊DAISUKE SATO¹, SHUHEI NAKATA¹, SHIGENOBU KUBO² (1.MITSUBISI FBR SYSTEMS, INC., 2.Japan Atomic Energy Agency)

10:15 AM - 10:30 AM

[3P04] Studies on the Safety Design Guidelines of Generation-Ⅳ Sodium-cooled Fast Reactors

(9)Focal Points of Safety Design Guideline for Containment System

＊koichi higurashi¹, you akiyama¹, hidemasa yamano² (1.MITSUBISHI FBR SYSTEMS, INC., 2.Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[3P05] Studies on the Safety Design Guidelines of Generation-IV Sodium-cooled Fast Reactors

(10)Focal Points of Safety Design Guideline for Gen-IV SFR Designs

＊Shigenobu Kubo¹, Yasushi Okano¹ (1.JAEA)

10:45 AM - 11:00 AM

[3P06] Study on External Hazard Conditions Applied to Conceptual Design of a Next-Generation Sodium-Cooled Fast Reactor

＊Hidemasa Yamano¹, Nobuchika Kawasaki¹, Shigenobu Kubo¹ (1.Japan Atomic Energy Agency)

Oral Presentation

[3P07-10] Safety evaluations for a fast reactor 5

Mon. Mar 28, 2016 11:00 AM - 12:00 PM Room P (Lecture Rooms C C200)

Chair: Yasushi Okano (JAEA)

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11:00 AM - 11:15 AM

[3P07] Evaluation of Sodium Pool Fire and Thermal Consequence in Two-cell Configuration

＊Shuji Ohno¹, Takashi Takata¹, Yuji Tajima² (1.JAEA, 2.ENO Suri Kaiseki Research)

11:15 AM - 11:30 AM

[3P08] Containment Responses and Fission Product Behaviour in Loss-of-Reactor-Level Accident of Sodium-Cooled Fast Reactor

＊YE YI¹, Sunghyon Jang¹, Akira Yamaguchi¹ (1.Department of Nuclear Engineering and Management, School of Engineering, University of Tokyo)

11:30 AM - 11:45 AM

[3P09] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(11)Development of Heat Transport Model in Multi-Dimensional Sodium Combustion Analysis Code

＊Mitsuhiro Aoyagi¹, Shuji Ohno¹, Masayoshi Uno² (1.JAEA, 2.University of Fukui)

11:45 AM - 12:00 PM

[3P10] Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor

(12)Test and Finite Element Analysis of Bellows and Head Plate Structures for CV Structural Integrity Assessment

＊Kazuyuki Tsukimori¹, Masanori Ando¹, Hiroki Yada¹, Yoshinari Anoda², Masakazu Ichimiya², Masayoshi Uno² (1.JAEA, 2.University of Fukui)

Oral Presentation

[3P11-16] Reprocessing Plant

Mon. Mar 28, 2016 2:45 PM - 4:25 PM Room P (Lecture Rooms C C200)

Chair: Yasuhisa Ikeda (Tokyo Tech)

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2:45 PM - 3:00 PM

[3P11] Evaluation of RuO₄ absorption to the water

＊Yuki Shibata¹, Takashi Kodama¹, Kazushi Ogaki¹, Kazunori Suzuki², Mikio Kumagai² (1.JNFL, 2.UI Sciences Inc.)

3:00 PM - 3:15 PM

[3P12] Experiment on airborne release fraction in hydrogen explosion accident at Reprocessing plant

(4)Small scale test Part2

＊Takahiro ISHIO¹, Takashi KODAMA¹, Takahiro CHIKAZAWA², Takashi KOBAYASHI², Tadashi ISOKAWA² (1.JNFL, 2.MMC)

3:15 PM - 3:30 PM

[3P13] Experiment on airborne release fraction in hydrogen explosion accident at Reprocessing plant

(5)Experiment on using dummy annular vessel Part2

＊Takashi Kobayashi¹, Takahiro Chikazawa¹, Harumi Sato¹, Takashi Kodama², Takahiro Ishio² (1.Mitsubishi Materials Cooperation, 2.Japan Nuclear Fuel Limited)

3:30 PM - 3:45 PM

[3P14] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(1)Overview

＊Yoshikazu Tamauchi¹, Tatsuya Kudo¹, Masanao Nakano¹, Naoya Sakagami¹, Kouhei Otake¹, Nobuyuki Arai¹, Takahiro Shibahara², Wenbin Dai², Osamu Kanehira² (1.Japan Nuclear Fuel Limited, 2.Mitsubishi Materials Corporation)

3:45 PM - 4:00 PM

[3P15] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(2)Hydrogen explosion experiment of simulated annular vessels

＊Takahiro Shibahara¹, Hirofumi Takenouchi¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Tatsuya Kudou², Masanao Nakano², Naoya Sakagami², Kouhei Ootake², Nobuyuki Arai² (1.Mitsubishi Materials Corporation, 2.Japan Nuclear Fuel Limited)

4:00 PM - 4:15 PM

[3P16] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(3)Combustion analysis and structural analysis of simulated annular vessels

＊Wenbin DAI¹, Yoshinori HIRASHIMA¹, Takahiro SHIBAHARA¹, Osamu KANEHIRA¹, Yoshikazu TAMAUCHI², Tatsuya KUDOU², Masanao NAKANO², Naoya SAKAGAMI², Kouhei OOTAKE², Nobuyuki ARAI² (1.Mitsubishi Materials Corporation, 2.Japan Nuclear Fuel Limited)

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

Sessions

III. Fission Energy Engineering » 306-1. Nuclear Safety Engineering, Nuclear Installation Safety, PSA

[1F01-08] Safety evaluations for a fast reactor 1

(1)Overview of IVR Evaluation in Anticipated Transient without Scram (ATWS)

(2)Assessment of Initiating Phase in ULOF

(3)Confirmation of Analysis Code for Initiating Phase in ULOF

(4)Assessment of Transition Phase in ULOF

(5)Confirmation of Analysis Code for Transition Phase in ULOF

(6)Assessment of PAMR/PAHR Phase in ULOF

(7)Confirmation of Structural Integrity Evaluation Methodology for PAMR/PAHR phase in ULOF

(8)Assessment of Post-Disassembly Expansion and Structural Response in ULOF

[1F09-11] Safety evaluations for a fast reactor 2

Bed leveling characteristics of spherical and non-spherical particle mixture

Index for reactivity insertion caused by fuel motion

[1F12-15] Safety evaluations for a fast reactor 3

(1)Approach toward Robust Preventive Function against Loss of Heat Removal

(2)Effectiveness of Natural Circulation Cooling

Effectiveness of Countermeasures for Making-up Reactor Sodium Level

(4)Effectiveness of Alternative Decay Heat Removal System

[1F16-20] Safety evaluations for a fast reactor 4

(1)Summary of SAS4A code and CABRI in-pile experiments

(2)Analysis of LTX test

(3)Analysis of LT4 test

(4)Analysis of EFM1 test

(9)Analysis of CABRI-BI3 Experiment

[1I01-04] Fukushima Daiichi Nuclear Power Plant Accident

(2)Behavior of Pressure Record at the Operation of IC in the Fukushima Reports

(3)Behavior of Water Level Record at the Operation of IC in the Fukushima Reports

(4)A Suggestion to Understand an IC Operation Story at the Fukushima No.1 Reactor- That was really performed with SRV and HPCI -

[1I05-08] Philosophy of the safety

Part 1: Project Plan

(1)Nuclear safety design and operation

(2)Rational safety consideration based on risk concept

[1I09-12] Severe Accident 1

(1)Overview

(2)Elemental Heat Transfer Tests using 3-rows and 5-levels Tube Bundle

[1I13-16] Severe Accident 2

(4)Study of Hydrogen Treatment with Metal Oxides

(5)Study on the Hydrogen Treatment Characteristics of a Processing Unit

[1I17-20] Accident in LWR 1

(1)Analysis of BWR plant.

(2)Analysis of PWR plant.

[2P01-03] Seismic analysis of FBR

(1)Development of the Core Element Vibration Analysis Code in Three Dimension

(2)Development of Seismic Reactivity Analysis Method Considering Three Dimensional Fuel Assembly Displacement

(3)Validation of Seismic Reactivity Analysis Method Considering Three Dimensional Fuel Assembly Displacement

[2P04-09] Accident in LWR 2

(1)Development of the evaluation method of a source term risk induced by cesium

(2)Evaluations of the cesium release during core damage events due to a large scale LOCA by using severe accident analysis codes

Analysis of Characteristics and Issues on Cesium Transportation Models of Severe accident Analysis Codes

(4)Uncertainty analysis concerning cesium release towards identifying risk profile and safety vulnerabilities

[2P10-12] Risk of External Event 1

Suggestion and Validation Study using Virtual Plant of Fragility Evaluation Method

[2P13-16] Risk of External Event 2

(1)Study on Evaluation Method

(2)Analysis of Model Plant

[2P17-20] PRA

[3P01-06] Safety design for fast reactors

(6)Focal Points of Safety Design Guideline for Structures, Systems and Components

(7)Focal Points of Safety Design Guideline for Reactor Core

(8)Focal Points of Safety Design Guideline for Reactor Coolant System

(9)Focal Points of Safety Design Guideline for Containment System

(10)Focal Points of Safety Design Guideline for Gen-IV SFR Designs

[3P07-10] Safety evaluations for a fast reactor 5

(11)Development of Heat Transport Model in Multi-Dimensional Sodium Combustion Analysis Code

(12)Test and Finite Element Analysis of Bellows and Head Plate Structures for CV Structural Integrity Assessment

[3P11-16] Reprocessing Plant

(4)Small scale test Part2

(5)Experiment on using dummy annular vessel Part2

(1)Overview

(2)Hydrogen explosion experiment of simulated annular vessels

(3)Combustion analysis and structural analysis of simulated annular vessels

Authentication

(4)A Suggestion to Understand an IC Operation Story at the Fukushima No.1 Reactor
- That was really performed with SRV and HPCI -