Oral presentation

[1B01-08] Safety Improvement for Spent Fuel Storage Pool

Wed. Sep 13, 2017 10:00 AM - 12:00 PM Room B (B12 - B1 Block)

Chair:Tomohiko Ikegawa (HGNE)

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10:00 AM - 10:15 AM

[1B01] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(13)Investigation of cladding oxidation model

Yoshiyuki Nemoto¹, *Yoshiyuki Kaji¹, Chihiro Ogawa¹, Kazuo Nakajima², Toru Kanazawa², Masayuki Tojo² (1. Japan Atomic Energy Agency, 2. Global Nuclear Fuel - Japan)

10:15 AM - 10:30 AM

[1B02] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(14)CCFL characteristic at Upper Tie Plate by using Visualization Test Results

*Taku Nagatake¹, Shinichiro Uesawa¹, Yasuo Koizumi¹, Mitsuhiko Shibata¹, Hiroyuki Yoshida¹, Yoshiyuki Nemoto¹, Yoshiyuki Kaji¹ (1. Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[1B03] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(15)CFD analysis on Loss of Cooling and Loss of Coolant Accidents in SFP

*Kensuke Kobayashi¹, Toru Kanazawa¹, Masayuki Tojo¹, Daisuke Goto¹, Yoshiyuki Nemoto², Yoshiyuki Kaji² (1. GNF-J, 2. JAEA)

10:45 AM - 11:00 AM

[1B04] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(16)Three-dimensional criticality analysis of the damaged fuel system evaluated by MAAP

Tatsuya Iwamoto¹, Kensuke Kobayashi¹, Masayuki Tojo¹, *Daisuke Goto¹, Yoshiyuki Nemoto², Yoshiyuki Kaji² (1. GNF-J, 2. JAEA)

11:00 AM - 11:15 AM

[1B05] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(17)The basic way of thinking for the distributed fuel loading patterns in SFP of BWR

*Masayuki Tojo¹, Daisuke Goto¹, Tatsuya Iwamoto¹, Kensuke Kobayashi¹, Toru Kanazawa¹, Yoshiyuki Nemoto², Yoshiyuki Kaji² (1. Global Nuclear Fuel - Japan, Co., Ltd., 2. JAEA)

11:15 AM - 11:30 AM

[1B06] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(18)Evaluation of the effect of fuel assembly layout on SFP cooling characteristics with MAAP code

*Satoshi Nishimura¹, Masaaki Satake¹, Yoshihisa Nishi¹, Yoshiyuki Kaji², Yoshiyuki Nemoto² (1. CRIEPI, 2. JAEA)

11:30 AM - 11:45 AM

[1B07] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(19)Loss of Coolant Accident Analysis by improved SAMPSON Code

*Yoshihiro Morita¹, Hiroaki Suzuki¹, Masanori Naitoh¹, Yoshiyuki Kaji², Yoshiyuki Nemoto² (1. The Institute of Applied Energy, 2. Japan Atomic Energy Agency)

11:45 AM - 12:00 PM

[1B08] Experimental Study on Spray Cooling Effect for Accident Conditions in Spent Fuel Pool

(1)Project Plan and Overview of Single Bundle Spray Heat Transfer Test

Yoshitaka Mizutani¹, Tomomi Kawano¹, Shota Okui¹, Tatsuya Sasakawa¹, Masao Owaki¹, *Yuichiro Kubo¹ (1. NFI)

Oral presentation

[1B09-12] Risk Assessment for Fuel Reprocessing Plants

Wed. Sep 13, 2017 2:45 PM - 3:50 PM Room B (B12 - B1 Block)

Chair:Hidetoshi Karasawa (IAE)

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2:45 PM - 3:00 PM

[1B09] Study on the combustion behaivior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(12)Hydrogen explosion experiment of simulated horizontal connected two large cylindrical vessels

*Takeshi Mikami¹, Takashi Kobayashi¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Tatsuya Kudo², Masanao Nakano², Naoya Sakagami², Kouhei Ootake², Nobuyuki Arai² (1. Mitsubishi Materials, 2. Japan Nuclear Fuel Limited)

3:00 PM - 3:15 PM

[1B10] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(13)Combustion analysis and structural analysis of simulated horizontal connected two large cylindrical vessels

*Wenbin Dai¹, Yoshinori Hirashima¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Tatsuya Kudo², Masanao Nakano², Naoya Sakagami², Kouhei Ootake², Nobuyuki Arai² (1. Mitsubishi Materials Corporation, 2. Japan Nuclear Fuel Limited)

3:15 PM - 3:30 PM

[1B11] Experiment on airborne release fraction in hydrogen explosion accident at Reprocessing plant

(6)Review of the previous results and setting up new test plan

*Takahiro ISHIO¹, Takashi KODAMA¹, Takashi KOBAYASHI², Takahiro CHIKAZAWA² (1. Japan Nuclear Fuel Limited, 2. Mitsubishi Materials Corporation)

3:30 PM - 3:45 PM

[1B12] Experiment on airborne release fraction in hydrogen explosion accident at Reprocessing plant

(7)small scale test part3

*Takashi KOBAYASHI¹, Takahiro CHIKAZAWA¹, Takahiro ISHIO², Takashi KODAMA² (1. Mitsubishi Materials Corporation, 2. Japan Nuclear Fuel Limited)

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

Oral presentation

[1B13-16] Evaluation of Source Terms and Radiation Doses 1

Wed. Sep 13, 2017 3:50 PM - 4:55 PM Room B (B12 - B1 Block)

Chair:Masahiko Osaka (JAEA)

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3:50 PM - 4:05 PM

[1B13] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(1)Development of source term PRD method focused on high important phenomena during a severe accident

*Koichi Nakamura¹, Yoko Yamane², Keigo Murata², Taizo Kanai¹, Hiroshi Endo¹ (1. Central Research Institute of Electric Power Industry, 2. AdvanceSoft Corporation)

4:05 PM - 4:20 PM

[1B14] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(2)Development of Source term PRD method by applying the model evaluated fission product aerosol diameter distribution

*Yoko Yamane¹, Koichi Nakamura², Kanai Taizo², Keigo Murata¹, Hiroshi Endo² (1. Advancesoft Corporation, 2. Central Research Institute of Electric Power Industry)

4:20 PM - 4:35 PM

[1B15] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(3)Analysis of fission product released to environment behavior based on the source term uncertainty analysis

*KEIGO MURATA¹, Koichi Nakamura², Yoko Yamane¹, Taizo Kanai², Hiroshi Endo² (1. AdVanceSoft Corporation, 2. Central Research Institute of Electric Power Industry)

4:35 PM - 4:50 PM

[1B16] Development of the evaluation method for the advanced level 2 probabilistic risk assessment

(4)Development of filtered containment venting system performance evaluation tool

*Taizo Kanai¹, Masahiro Furuya¹, Koichi Nakamura¹, Hiroshi Endo¹, Yoshihisa Nishi¹ (1. CRIEPI)

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

Oral presentation

[1B17-20] Evaluation of Source Terms and Radiation Doses 2

Wed. Sep 13, 2017 4:55 PM - 6:00 PM Room B (B12 - B1 Block)

Chair:Koichi Nakamura (CRIEPI)

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4:55 PM - 5:10 PM

[1B17] Analytical technique for cesium and iodine chemical behavior under severe accident

*Hiroyuki Shiotsu¹, Jun Ishikawa¹, Hiroto Ito¹, Tomoyuki Sugiyama¹, Yu Maruyama¹ (1. JAEA)

5:10 PM - 5:25 PM

[1B18] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(7)Source term evaluation for accident scenario considering graphite component failure

*Hiroyuki Sato¹, Yuki Honda¹, Hirofumi Ohashi¹ (1. Japan Atomic Energy Agency)

5:25 PM - 5:40 PM

[1B19] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(8)Identification of influencing factors for uncertainty in source term evaluation during unprotected depressurized loss-of-forced circulation accident

*Yuki Honda¹, Hiroyuki Sato¹, Hirofumi Ohashi¹ (1. Japan Atomic Energy Agency)

5:40 PM - 5:55 PM

[1B20] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors(HTGRs)

(9)Consideration on applicability of SECOM 2-DQFM-U code in case of pipe breach accident by seismic

*Kosuke Matsuda¹, Hitoshi Muta¹, Ken Muramatsu¹, Hiroyuki Sato², Akemi Nishida², Tatsuya Itoi³, Yasuki Ohtori¹ (1. Tokyo City University, 2. Japan Atomic Energy Agency, 3. The University of Tokyo)

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

Oral presentation

[2B01-05] Light Water Reactor Behavior Under Accident Conditions 2

Thu. Sep 14, 2017 9:30 AM - 10:50 AM Room B (B12 - B1 Block)

Chair:Kenji Kamiyama (JAEA)

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9:30 AM - 9:45 AM

[2B01] Analysis of MCCI phenomena by MELCOR and SAMPSON codes

(1)Study on Debris Behaviors focused on Flow and Radiation immediately after Falling onto Cavity Floor

*Masashi Himi¹, Koetsu Ito¹, Yoshihiro Ide¹, Hidetoshi Morita¹, Koichi Nakamura² (1. Advancesoft co., 2. CRIEPI)

9:45 AM - 10:00 AM

[2B02] Analysis of MCCI phenomena by MELCOR and SAMPSON codes

(2)Simulation of the phenomena by use of MELCOR and SAMPSON codes

*Koetsu Ito¹, Masashi Himi¹, Yoshihiro Ide¹, Hidetoshi Morita¹, Kohichi Nakamura² (1. Advancesoft Corp., 2. CRIEPI)

10:00 AM - 10:15 AM

[2B03] Fundamental experiment on the U-Zr-Gd-O molten corium solidification behavior

*ayako sudo¹, Igor Poznyak², Yuji Nagae¹, Toshio Nakagiri¹, Masaki Kurata¹ (1. Japan Atomic Energy Agency, 2. Reserch Center Rez)

10:15 AM - 10:30 AM

[2B04] Study on Molten Core Coolability under Precautionary Water Injection into Containment Vessel

(1)Development of Breakup Particle Agglomeration Model in JASMINE

Toshinori Matsumoto¹, Ryuhei Kawabe¹, Kohei Ajima¹, *Tomoyuki Sugiyama¹, Yu Maruyama¹ (1. JAEA)

10:30 AM - 10:45 AM

[2B05] Study on Molten Core Coolability under Precautionary Water Injection into Containment Vessel

(2)Analysis by Improved Melt Spreading Model in JASMINE

Ryuhei Kawabe¹, Toshinori Matsumoto¹, Kohei Ajima¹, Tomoyuki Sugiyama¹, *Yu Maruyama¹ (1. JAEA)

Time reserved for Chair （10:45 AM - 10:50 AM）

Oral presentation

[2B06-09] Safety Assessment for Fast Reactors 1

Thu. Sep 14, 2017 10:50 AM - 11:55 AM Room B (B12 - B1 Block)

Chair:Tomoyuki Sugiyama (JAEA)

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10:50 AM - 11:05 AM

[2B06] Experimental Study on Self-leveling Behavior of Debris Bed

Development of empirical correlation for bed high of mixed particles

*Ryo Miura¹, Humiya Matsuoka¹, Ngo Phi Manh¹, Phan Le Hoang Sang¹, Tatsuya Matsumoto¹, Wei Liu¹, Koji Morita¹ (1. Kyushu University)

11:05 AM - 11:20 AM

[2B07] Applicability assessment of empirical correlations to the prediction of the distance for fragmentation of molten core materials in sodium

*Kenichi Matsuba¹, Mikio Isozaki¹, Junichi Toyooka¹, Kenji Kamiyama¹, Vladimir Zuev², Alexander Kolodeshnikov² (1. Japan Atomic Energy Agency, 2. NNC/RK)

11:20 AM - 11:35 AM

[2B08] Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors

(4)Effects of test conditions on dispersion and sedimentation of molten-metal in a shallow water pool

*Yuki Emura¹, Kenji Kamiyama¹, Ken-ichi Matsuba¹, Mikio Isozaki¹, Yuya Imaizumi¹ (1. JAEA)

11:35 AM - 11:50 AM

[2B09] Studies on Relocation Behavior of Molten Core Materials in the Core Disruptive Accident of Sodium-cooled Fast Reactors

(5)A Behavior of a Heavy Metal Jet with Free Surface Conditon of MPS Method

*Mamoru Konomura¹, Kenji Kamiyama² (1. Univ. of Fukui, 2. JAEA)

Time reserved for Chair （11:50 AM - 11:55 AM）

Oral presentation

[2B10-13] Safety Assessment for Fast Reactors 2

Thu. Sep 14, 2017 2:45 PM - 3:45 PM Room B (B12 - B1 Block)

Chair:Mamoru Konomura (Univ. of Fukui)

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2:45 PM - 3:00 PM

[2B10] Study on In-Vessel Retention (IVR) of Unprotected Accident for Fast Reactor

(9)Uncertainty in Assessments of Initiating Phase in ULOF

*Kenichi Kawada¹, Shinya Ishida¹ (1. JAEA)

3:00 PM - 3:15 PM

[2B11] Study on In-Vessel retention (IVR) of Unprotected Accident for Fast Reactor

(10)Evaluation of discharge amount of core fuel for Transition Phase in ULOF

*Hirotaka Tagami¹, Yoshiharu Tobita¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[2B12] Study on In-Vessel Retention (IVR) of Unprotected Accident for Fast Reactor

(11)Best Estimate and Uncertainty Assessment of PAMR/PAHR Phase in ULOF

*Joji Sogabe¹, Yusaku Wada¹, Tohru Suzuki^1,2, Yoshiharu Tobita¹ (1. JAEA, 2. Tokyo City Univ.)

3:30 PM - 3:45 PM

[2B13] Study on In-Vessel Retention (IVR) of Unprotected Accident for Fast Reactor

(12)Criticality Assessment of PAMR Phase in ULOF

*Shinya Ishida¹, Yoshiharu Tobita¹ (1. JAEA)

Oral presentation

[2B14-16] Safety Measures for Sodium Facilities

Thu. Sep 14, 2017 3:45 PM - 4:30 PM Room B (B12 - B1 Block)

Chair:Kenichi Matsuba (JAEA)

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3:45 PM - 4:00 PM

[2B14] Dismantling technology for large-scale sodium components used for a long time

(1)Behavior of impurity adhesion to sodium equipment

*Kazuhito SHIMOYAMA¹, Masato HAYAKAWA¹, Shigeaki SUZUKI², Hiroyuki MIYAKOSHI¹, Kuniaki ARA¹ (1. JAEA, 2. Ascend)

4:00 PM - 4:15 PM

[2B15] Dismantling technology for large-scale sodium components used for a long time

(2)Adhesion behavior of sodium vapor in cover gas region

*Shigeaki SUZUKI¹, Masato HAYAKAWA², Kazuhito SHIMOYAMA², Ryota UMEDA², Eiichi YOSHIDA², Hiroyuki MIYAKOSHI² (1. Ascend, 2. JAEA)

4:15 PM - 4:30 PM

[2B16] Dismantling technology for large-scale sodium components used for a long time

(3)Burning control for component with sodium deposits during air plasma cutting

*Masato HAYAKAWA¹, Shigeaki SUZUKI², Kazuhito SHIMOYAMA¹, Ryota UMEDA¹, Eiichi YOSHIDA¹, Hiroyuki MIYAKOSHI¹ (1. JAEA, 2. Ascend)

Oral presentation

[1C01-04] Mitigation Measures Against Severe Accidents

Wed. Sep 13, 2017 10:00 AM - 11:05 AM Room C (Open Hall - B1 Block)

Chair:Daisuke Yamauchi (TEPCO HD)

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10:00 AM - 10:15 AM

[1C01] Development of hydrogen treatment system in severe accident

(8)Evaluation of Obstructive facter for hydrogen treatment rate

*Akira Yamada¹, chikako Iwaki¹, Motoshige Yagyu¹, Yoshiko Haruguchi¹, Masashi Tanabe² (1. Toshiba Corporation Power and Industrial Systems Research and Development Center, 2. Toshiba Corporation Isogo Engineering Center)

10:15 AM - 10:30 AM

[1C02] Development of Hydrogen Treatment System in Severe Accident

(9)Evaluation of Steam Influence on Hydrogen Processing Characteristics of Reactor Unit

*Chikako Iwaki¹, Tsukasa Sugita¹, Akira Yamada¹, Motoshige Yagyu¹, Yoshiko Haruguchi¹, Masashi Tanabe¹ (1. Toshiba corporation)

10:30 AM - 10:45 AM

[1C03] Development of a method for Mitigating Thermal Stratification in Pressure Suppression Pool

*Akira Tanaka¹, Akiyoshi Obonai¹, Marco Pellegrini² (1. TOHOKU ELECTRIC POWER CO.,INC., 2. The Institute of Applied Energy)

10:45 AM - 11:00 AM

[1C04] Adsorption characteristics of methyl iodine on AgX in low temperature region-Part.3

*Toshiki Kobayashi¹, Jifeng Wang¹, Yoshihiro Ishikawa¹, Yuichiro Uzuyama¹, Koji Endo¹ (1. Rasa Industries, LTD)

Time reserved for Chair （11:00 AM - 11:05 AM）

Oral presentation

[1C05-07] Safety Assessment for Light Water Reactors 1

Wed. Sep 13, 2017 11:05 AM - 11:55 AM Room C (Open Hall - B1 Block)

Chair:Masahiro Ishigaki (JAEA)

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11:05 AM - 11:20 AM

[1C05] Development of Desktop Plant Simulator to Treat Simultaneous Accident Progress in Reactor and SFP

(2)Specification and functions of desktop plant simulator in reactor shutdown condition

*Yoshitaka Sugiura¹, Ryunosuke Yamaguchi¹, Toru Sakamoto¹, Daisuke Fujiwara¹, Osamu Kubota¹ (1. TEPCO SYSTEMS CORPORATION)

11:20 AM - 11:35 AM

[1C06] Development of Desktop Plant Simulator to Treat Simultaneous Accident Progress in Reactor and SFP

(3)Two-way coupling calculation between RPV and SFP

*Toru Sakamoto¹, Yoshitaka Sugiura¹, Ryunosuke Yamaguchi¹, Daisuke Fujiwara¹, Osamu Kubota¹ (1. Tepsys)

11:35 AM - 11:50 AM

[1C07] Plant incident progress scenario analysis for nuclear emergency exercise of Kansai Electric Power Co., Inc. 2016

*ikuo kawasaki¹, akira nakamura¹, shunsuke takahashi², yasuhiro tateda², yasunori yamamoto¹ (1. Institute of Nuclear Safety System, 2. Kansai Electric Power)

Time reserved for Chair （11:50 AM - 11:55 AM）

Oral presentation

[1C08-12] Safety Assessment for Light Water Reactors 2

Wed. Sep 13, 2017 2:45 PM - 4:05 PM Room C (Open Hall - B1 Block)

Chair:Isobe Yoshihiro (NFI)

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2:45 PM - 3:00 PM

[1C08] Research on Aggregate Test Flow for ASR Potential Evaluation

*Eto Junji¹, Takamasa Ochiai², Shoichi Ogawa³, Kazutoshi Shibuya³, Ippei Maruyama⁴, Kazuo Yamada⁵, Masayuki Takizawa¹ (1. MRI, 2. MRA, 3. THC, 4. Nagoya Univ., 5. NIES)

3:00 PM - 3:15 PM

[1C09] Development of the fuel behavior analysis code for mechanical fuel failure during PWR reactivity insertion accident

*Yuma Higashi¹, Eisaku Tatsumi¹, Tadakatsu Yodo¹, Yugen Shiratsuchi¹, Teruhisa Yamamoto², Nozomu Murakami² (1. MHI, 2. MNF)

3:15 PM - 3:30 PM

[1C10] Performance evaluation of EPDM at elevated temperature (2)

*ken Suzuki¹, Shinichi Matsuda², Takuya Sugimura², Tsutsumi Yusuke¹ (1. NIPPON VALQUA INDUSTRIES, 2. Chubu Electric Power )

3:30 PM - 3:45 PM

[1C11] Probabilistic integrity evaluation assuming embedded flaw of reactor pressure vessel

*Takashi Suzuki¹, Ryuta Okayama², Kenta Murakami¹, Masahide Suzuki¹, Jinya Katsuyama³, Yinsheng Li³ (1. Nagaoka University of Technology, 2. Tokyo Electric Power Company Holdings, Inc., 3. Japan Atomic Energy Agency)

3:45 PM - 4:00 PM

[1C12] Uncertainty evaluation for fracture boundary of non-irradiated Zircaloy-4 cladding tube under LOCA conditions

*Takafumi Narukawa^1,2, Akira Yamaguchi¹, Sunghyon Jang¹, Masaki Amaya² (1. UTokyo, 2. JAEA)

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

Oral presentation

[1C13-18] Light Water Reactor Behavior Under Accident Conditions 1

Wed. Sep 13, 2017 4:05 PM - 5:45 PM Room C (Open Hall - B1 Block)

Chair:Yuzuru Eguchi (CRIEPI)

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4:05 PM - 4:20 PM

[1C13] Analysis of BWR Containment Behavior under Severe Accidents using GOTHIC

(3)Analysis of Aerosol Behavior

*Hiroshi Kawai¹, Tatsuya Hayasaki¹, Daisuke Fujiwara¹ (1. TEPCO SYSTEMS CORPORATION)

4:20 PM - 4:35 PM

[1C14] Thermal-hydraulic Analysis of BWR Containment Response to Accidents with GOTHIC

(4)Analysis of SFPAir Coolability

*Keisuke Okawa¹, Daisuke Fujiwara¹, Yun Gao¹, Achihiro Hamano¹ (1. TEPSYS)

4:35 PM - 4:50 PM

[1C15] A Study on The Boiling Transition in RIAs (Cold RIA)

(1)Overall Plan

*Yuichi Sago¹, Kenichi Harada¹, Masahiro Furuya², Hirohisa Kaneko³, Takamasa Miyaji⁴ (1. Chubu Electric Power, 2. CRIEPI, 3. GNF-J, 4. NFI)

4:50 PM - 5:05 PM

[1C16] A Study on The Boiling Transition in RIAs (Cold RIA)

(2)Transient critical heat flux with 3 x 3 bundle heated rapidly under atmospheric pressure

*Takahiro Arai¹, Masahiro Furuya¹, Kenetsu Shirakawa¹, Shun Watanabe¹, Hiroki Takiguchi¹, Yuichi Sago², Kenichi Harada² (1. CRIEPI, 2. Chubu Electric Power)

5:05 PM - 5:20 PM

[1C17] A Study on The Boiling Transition in RIAs (Cold RIA)

(3)Development and Verification of A CHF Correlation for Cold RIA

*Toru Kanazawa¹, Tsugumi Tsuchida¹, Tetsuhiro Ozaki², Takamasa Miyaji², Yuichi Sago³, Kenichi Harada³ (1. GNF-J, 2. NFI, 3. Chubu Electric Power)

5:20 PM - 5:35 PM

[1C18] A Study on The Boiling Transition in RIAs (Cold RIA)

(4)BWR RIA Analysis at Cold Condition

*Tsugumi Tsuchida¹, Hirohisa Kaneko¹, Ryosuke Nakamura², Takamasa Miyaji², Yuichi Sago³, Kenichi Harada³ (1. GNF-J, 2. NFI, 3. Chubu Electric Power)

Time reserved for Chair （5:35 PM - 5:45 PM）

Oral presentation

[2C01-06] PRA 1

Thu. Sep 14, 2017 9:30 AM - 11:05 AM Room C (Open Hall - B1 Block)

Chair:Akio Gofuku (Okayama Univ.)

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9:30 AM - 9:45 AM

[2C01] The Progress of PRA for Tokai No.2 Power Station

(1)HRA evaluation results of Tokai No.2 Power Station during Power Operation (Level1)

*Haruka Inoue², Masaru Yamanaka¹, Atsuo Ikeda², Takayuki Negishi² (1. The Japan Atomic Power Company, 2. Nuclear Enginnering And Service Company)

9:45 AM - 10:00 AM

[2C02] Study for upgrading of Human Reliability Analysis

(1)Development of HRA Guide adopting concept of "Narrative" for Qualitative Analysis

*Yukihiro Kirimoto¹, Hiromichi Miura¹, Akihiko Nagasaka¹, Kenichi Kanda¹, Kazuma Abe² (1. CRIEPI, 2. Tohoku-EPCO)

10:00 AM - 10:15 AM

[2C03] Study for upgrading of Human Reliability Analysis

(2)A Concept of Human Failure Events Database

*Akihiko Nagasaka¹, Yuuko Hirotsu¹, Hisao Shibue¹, Hiromichi Miura¹, Yukihiro Kirimoto¹ (1. CRIEPI)

10:15 AM - 10:30 AM

[2C04] Examination about utilization of multi agent system for probabilistic risk assessment

*Kenichi Kanda¹, Kazuma Abe¹, Hiromichi Miura¹, Tomoaki Yoshida¹ (1. Central Research Institute of Electric Power Industry)

10:30 AM - 10:45 AM

[2C05] Study on Method of Dynamic Multi-Unit Probabilistic Risk Assessment Considering Influences in Multiple Units

*Yuki Nakano¹, Satoshi Takeda¹, Takanori Kitada¹ (1. Graduate School of Engineering Osaka Univ.)

10:45 AM - 11:00 AM

[2C06] Quantitative Analysis on Off-site Emergency Management on Multi-unit Site Under Severe Accident Condition

*SUNGHYON JANG¹, Akira Yamaguchi¹ (1. The University of Tokyo)

Time reserved for Chair （11:00 AM - 11:05 AM）

Oral presentation

[2C07-10] PRA 2

Thu. Sep 14, 2017 11:05 AM - 12:10 PM Room C (Open Hall - B1 Block)

Chair:Tatsuya Itoi (Univ. of Tokyo)

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11:05 AM - 11:20 AM

[2C07] Study on PRA Methodology for Seismic Induced Tsunami Event

(1)Evaluation of Seismic Induced Tsunami Event Using DQFM Method

*HIROHISA YAMAKAWA¹, Hitoshi Muta¹, Ken Matsumoto¹, Yuki Kameko¹, Takayuki Negishi², Atsuo Ikeda², Hidekazu Suwa², Hiroto Matsumoto² (1. Tokyo City Univ., 2. Nuclear Engineering and Services Co.)

11:20 AM - 11:35 AM

[2C08] Study on PRA Methodology for Seismic Induced Tsunami Event

(2)The Comparison of MCS Methodology and DQFM Methodology

*Hidekazu Suwa¹, Takayuki Negishi¹, Atsuo Ikeda¹, Hiroto Matsumoto¹, Hitoshi Muta², Ken Muramatsu², Hirohisa Yamakawa² (1. Nuclear Engineering and Services Co., 2. Tokyo City Univ.)

11:35 AM - 11:50 AM

[2C09] Development of a fragility evaluation methodology for the Tsunami PRA

*Takanori Togashi¹, Takeshi Kunimasa¹, Keigo Maehara¹, Ryusuke Haraguchi² (1. THE KANSAI ELECTRIC POWER CO.,INC., 2. Mitsubishi Heavy Industries, Ltd.)

11:50 AM - 12:05 PM

[2C10] Evaluation of Annual Probability of Tornado Missile Strike on Arbitrary Horizontal and Vertical Plates

*Yuzuru Eguchi¹, Takahiro Murakami¹, Soichiro Sugimoto¹, Yasuo Hattori¹, Hiromaru Hirakuchi¹ (1. CRIEPI)

Time reserved for Chair （12:05 PM - 12:10 PM）

Oral presentation

[2C11-16] PRA 3

Thu. Sep 14, 2017 2:45 PM - 4:25 PM Room C (Open Hall - B1 Block)

Chair:Sunghyon Jang (Univ. of Tokyo)

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2:45 PM - 3:00 PM

[2C11] Development of Internal Flood Level 1 PRA Model for Light Water Reactor

*Tamio Koriyama¹, Kotaro Sakata¹, Yoshikane Hamaguchi¹, Tomomichi Itoh¹ (1. S/NRA/R)

3:00 PM - 3:15 PM

[2C12] The Progress of PRA for SHIKA NPS unit2

(2)PRA evaluation results of SHIKA NPS unit2 during shutdown state(Level1)

*Shinichi Hamatani^1,2, Mutsuhiro Nakada¹, Toshihiro Aida¹, Daisuke Suimon¹, Keigo Morita¹, Takayuki Negishi², Atsuo Ikeda², Junya Masuko² (1. Hokuriku Electric Power Co., 2. Nuclear Engineering and Services Co.)

3:15 PM - 3:30 PM

[2C13] KK-6,7 project Internal Event Operating Level 1 PRA Model Sophistication Progress Report

(1)Project summary

*ryota tomiyasu¹, chikahiro sato¹, hiroshi abe¹, masanori takeuchi², toshinobu kita², yoshihiro ooyama² (1. TEPCO SYSTEMS CORPORATION, 2. Tokyo Electric Power Company Holdings,Inc.)

3:30 PM - 3:45 PM

[2C14] KK-6,7 project Internal Event Operating Level 1 PRA Model Sophistication Progress Report

(2)Identification Initiating Event and Estimation of Frequency

*Keisuke Maeda¹, Ryouta Tomiyasu¹, Natsuki Shiraishi¹, Chikahiro Sato¹, Hiroshi Abe¹, Masanori Takeuchi², Toshinobu Kita², Yoshihiro Ooyama² (1. TEPSYS, 2. TEPCO HD)

3:45 PM - 4:00 PM

[2C15] KK-6,7 project Internal Event Operating Level 1 PRA Model Sophistication Progress Report

(3)Analysis of Accident Sequence

*Shohei Yamagishi¹, Shunsuke Tanno¹, Teruyoshi Sato¹, Chikahiro Sato¹, Hiroshi Abe¹, Masanori Takeuchi², Toshinobu Kita², Yoshihiro Ooyama² (1. TEPSYS, 2. TEPCO)

4:00 PM - 4:15 PM

[2C16] KK-6,7 project Internal Event Operating Level 1 PRA Model Sophistication Progress Report

(4)Evaluation of Interinfluence between Adjacent Units

*Shuhei Matsunaka¹, Hiroshi Abe¹, Manabu Watanabe², Yoshihiro Oyama² (1. TEPCO SYSTEMS, 2. TEPCO)

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

Oral presentation

[2C17-23] Fukushima Nuclear Accident

Thu. Sep 14, 2017 4:25 PM - 6:20 PM Room C (Open Hall - B1 Block)

Chair:Shunsuke Uchida (IAE)

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4:25 PM - 4:40 PM

[2C17] Our lesson based on the information on background and process of Tsunami height evaluation at before the Fukushima Daiich nuclear accident.

*Yoshitaka Yoshida¹, Takeshi Matsuoka¹, Takashi Sawada¹, Genki Yagawa¹, Naoto Sekimura¹, Ayao Tsuge¹, Hideki Nariai¹, Masaki Shiratori¹, Hiroshi Miyano¹, Hiroyuki Kameda¹ (1. Working Group on Fukushima Nuclear Accident, Science Council of Japan)

4:40 PM - 4:55 PM

[2C18] Analysis of Plant Data Measured at Fukushima-Daiichi NPP Unit 3

Estimated Mechanism of PCV Pressure Variation during the expected MCCI phase

*IKKEN SATO¹ (1. Japan Atomic Energy Agency)

4:55 PM - 5:10 PM

[2C19] Study on ascertaining and analyzing reactor core status by MAAP code

(17)In-depth analysis for Unit-2 accident progression using MAAP code

*Yuki Nakamura¹, Yoshihiro Kojima¹, Naoki Shinji¹ (1. IRID/Toshiba)

5:10 PM - 5:25 PM

[2C20] Study on ascertaining and analyzing reactor core status by MAAP code

(18)In-depth analysis for Unit-3 accident progression using MAAP code

*Yoshihiro Kojima¹, Yuki Nakamura¹, Naoki Shinji¹ (1. Toshiba)

5:25 PM - 5:40 PM

[2C21] Evaluation method using material analysis of specimen in plasma heating experiment

(1)Outline of evaluation method using material analysis of specimen in plasma heating experiment

*Yuta Abe¹, Toshio Nakagiri¹, Ikken Sato¹, Natsuko Nakano², Hidenobu Yamaguchi³, Shinichiro Maruyama⁴ (1. Japan Atomic Energy Agency (JAEA), 2. Kaken, 3. Nissan ARC, 4. SUMITOMO MITSUI CONSTRUCTION)

5:40 PM - 5:55 PM

[2C22] Evaluation method using material analysis of specimen in plasma heating experiment

(2)Application possibility of materials analysis and LIBS using the plasma basics heating experiment

*Tomohiko Kawakami¹, Abe Yuta², Fabio Spaziani¹, Nakano Natsuko¹, Toshio Nakagiri² (1. Kaken, 2. Japan Atomic Energy Agency)

5:55 PM - 6:10 PM

[2C23] Evaluation method using material anaiysis of specimen in plasma heating experiment

(3)Cutting of Simulated Fuel Assembly Heating Examination by AWJ

*Shinichiro Maruyama¹, Yuta Abe², Toshio Nakagiri², Satoshi Watatani¹, Yuji Takashima³ (1. SUMITOMO MITSUI CONSTRUCTION, 2. Japan Atomic Energy Agency(JAEA), 3. NISSIN KIKO)

Time reserved for Chair （6:10 PM - 6:20 PM）

Oral presentation

[3C01-06] Quake-resistant and Seismic Isolation Technologies

Fri. Sep 15, 2017 9:30 AM - 11:10 AM Room C (Open Hall - B1 Block)

Chair:Hiroyuki Yamada (CRIEPI)

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9:30 AM - 9:45 AM

[3C01] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part6: Definition and representation of cliff edge

*Tsuyoshi Takada¹, Tatsuya Itoi¹, Takenori Hida¹, Ken Muramatsu², Hitoshi Muta², Satoshi Fujita³, Osamu Furuya³, Keisuke Minagawa⁴, Hidemasa Yamano⁵, Akemi Nishida⁵ (1. The University of Tokyo, 2. Tokyo City University, 3. Tokyo Denki University, 4. Saitama Institute of Technology, 5. Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[3C02] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part7: Cliff edges relevant to NPP building response

*Akemi Nishida¹, Byunghyun Choi¹, Hidemasa Yamano¹, Tsuyoshi Takada² (1. JAEA, 2. The Univ. of Tokyo)

10:00 AM - 10:15 AM

[3C03] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part8: Relaxation of cliff edges by seismic isolation

*Keisuke Minagawa¹, Satoshi Fujita², Osamu Furuya², Tsuyoshi Takada³ (1. Saitama Institute of Tech., 2. Tokyo Denki Univ., 3. The University of Tokyo)

10:15 AM - 10:30 AM

[3C04] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part9: Required Performance and Cliff-edge of Overall Nuclear Power Plant System to Seismic Event

*Hitoshi Muta¹, Ken Muramatsu¹, Yasuki Ohtori¹, Tsuyoshi Takada², Tatsuya Itoi² (1. Tokyo City University, 2. The University of Tokyo)

10:30 AM - 10:45 AM

[3C05] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part10: Evaluation of cliff edges of human

*Takenori Hida¹, Tatsuya Itoi¹, Tsuyoshi Takada¹ (1. The University of Tokyo)

10:45 AM - 11:00 AM

[3C06] The analysis evaluation of equipment and piping system for fault displacement

(3)An elasto-plastic analysis of crossover piping combined with the earthquake

*kunihiko sato¹, yutaka suzuki¹, satoshi shinma², ryusuke haraguchi², masanobu kamiya³, tsutomu ogawa³, kouichi kamiya³ (1. MHI NSE, 2. MHI, 3. JAPC)

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

Oral presentation

[3C07-09] Seismic PRA 1

Fri. Sep 15, 2017 11:10 AM - 12:00 PM Room C (Open Hall - B1 Block)

Chair:Keisuke Minagawa (Saitama Inst. of Tech.)

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11:10 AM - 11:25 AM

[3C07] Improvement of fragility evaluation method on seismic PRA

(4)Study of evaluation method on input seismic motion response factor at model plant

*Hiroyuki Yamada¹, Katsumi Ebisawa¹, Kazuhiko Kikuchi², Takeshi Ugata³, Shigehiro Sakamoto³, Sayaka Igarashi³, Yoshinori Mihara⁴, kohei Tanaka⁵ (1. CRIEPI, 2. YONDEN, 3. TAISEI CORPORATION, 4. Kajima Corp., 5. RTRI)

11:25 AM - 11:40 AM

[3C08] Improvement of fragility evaluation method on seismic PRA

(5)Study on building fragility evaluation considering nonlinear dynamic analysis

*Akira Ota¹, Takeshi Ugata¹, Masatoshi Okada², Hiroyuki Yamada³, Katsumi Ebisawa³ (1. TAISEI, 2. YONDEN, 3. CRIEPI)

11:40 AM - 11:55 AM

[3C09] Improvement of fragility evaluation method on seismic PRA

(6)Investigation of the component fragility evaluation considering dynamic nonlinear characteristics of building

*Tetsuhiro Gou¹, Ryusuke Haraguchi¹, Kazuhiko Kikuchi², Hiroyuki Yamada³, Katsumi Ebisawa³ (1. MHI, 2. YONDEN, 3. CRIEPI)

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

Oral presentation

[3C10-12] Seismic PRA 2

Fri. Sep 15, 2017 2:45 PM - 3:35 PM Room C (Open Hall - B1 Block)

Chair:Katsumi Ebisawa (CRIEPI)

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2:45 PM - 3:00 PM

[3C10] Rsearch on Seismic Correlation for PRA

Part 1: Calculation Method of Seismic Correlation

*Yasuki Ohtori¹, Masato Nakajima², Hitoshi Muta¹ (1. Tokyo City University, 2. Central Research Institute of Electric Power Industry)

3:00 PM - 3:15 PM

[3C11] Investigation and Consideration about Risk Evaluation by Fault Displacements for Nuclear Facilities

Structure Damage on Surface Faulting of 2016 Kumamoto Earthquake

*Masanobu Kamiya¹, Masataka Sawada², Yasuhira Aoyagi² (1. JAPC, 2. CRIEPI)

3:15 PM - 3:30 PM

[3C12] Fragility Evaluation considering Aleatory and Epistemic Uncertainty of Fault Displacement for Reactor Buildings

*Kenshiro Ishiki¹, Hirokazu Tsuji², Minoru Kanechika¹, Yoshinori Mihara¹ (1. Kajima Corp., 2. Japan Nuclear Safety Inst.)

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

Oral presentation

[3C13-17] Seismic PRA 3

Fri. Sep 15, 2017 3:35 PM - 4:55 PM Room C (Open Hall - B1 Block)

Chair:Masanobu Kamiya (JAPC)

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3:35 PM - 3:50 PM

[3C13] Development of fault displacement PRA methodology

(1)Outline

*Katsumi Ebisawa¹, Hideaki Tsutsumi¹, Yoshinori Mihara³, Futoshi Tanaka², Daisuke Ochi², Manabu Miyata², Ryusuke Haraguchi², Tetsuhiro Gou², Kunihiko Sato², Hidenori Miwa² (1. CRIEPI, 2. MHI, 3. Kajima)

3:50 PM - 4:05 PM

[3C14] Development of fault displacement PRA methodology

(2)Identification of accident scenario based on view point of soil and building failure against fault displacement

*Yoshinori Mihara¹, Katsumi Ebisawa², Hideaki Tsutsumi² (1. Kajima Corporation, 2. Central Research Institute of Electric Power Industry)

4:05 PM - 4:20 PM

[3C15] Development of fault displacement PRA methodology

(3)Identification of accident scenario based on view point of structure, system and component failure against fault displacement

*Futoshi Tanaka¹, Daisuke Ochi¹, Manabu Miyata¹ (1. MHI)

4:20 PM - 4:35 PM

[3C16] Development of fault displacement PRA methodology

(4)Development of fragility evaluation method of structure and component against fault displacement

*Ryusuke Haraguchi¹, Tetsuhiro Gou¹, Kunihiko Sato² (1. Mitsubishi Heavy Industries, LTD., 2. MHI Nuclear Systems And Solution Engineering Co., Ltd.)

4:35 PM - 4:50 PM

[3C17] Development of fault displacement PRA methodology

(5)Development of accident sequence evaluation against fault displacement

*Hideki Miwa¹, Daisuke Ochi¹, Manabu Miyata¹, Futoshi Tanaka¹ (1. MHI)

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

Sessions

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

[1B01-08] Safety Improvement for Spent Fuel Storage Pool

(13)Investigation of cladding oxidation model

(14)CCFL characteristic at Upper Tie Plate by using Visualization Test Results

(15)CFD analysis on Loss of Cooling and Loss of Coolant Accidents in SFP

(16)Three-dimensional criticality analysis of the damaged fuel system evaluated by MAAP

(17)The basic way of thinking for the distributed fuel loading patterns in SFP of BWR

(18)Evaluation of the effect of fuel assembly layout on SFP cooling characteristics with MAAP code

(19)Loss of Coolant Accident Analysis by improved SAMPSON Code

(1)Project Plan and Overview of Single Bundle Spray Heat Transfer Test

[1B09-12] Risk Assessment for Fuel Reprocessing Plants

(12)Hydrogen explosion experiment of simulated horizontal connected two large cylindrical vessels

(13)Combustion analysis and structural analysis of simulated horizontal connected two large cylindrical vessels

(6)Review of the previous results and setting up new test plan

(7)small scale test part3

[1B13-16] Evaluation of Source Terms and Radiation Doses 1

(1)Development of source term PRD method focused on high important phenomena during a severe accident

(2)Development of Source term PRD method by applying the model evaluated fission product aerosol diameter distribution

(3)Analysis of fission product released to environment behavior based on the source term uncertainty analysis

(4)Development of filtered containment venting system performance evaluation tool

[1B17-20] Evaluation of Source Terms and Radiation Doses 2

(7)Source term evaluation for accident scenario considering graphite component failure

(8)Identification of influencing factors for uncertainty in source term evaluation during unprotected depressurized loss-of-forced circulation accident

(9)Consideration on applicability of SECOM 2-DQFM-U code in case of pipe breach accident by seismic

[2B01-05] Light Water Reactor Behavior Under Accident Conditions 2

(1)Study on Debris Behaviors focused on Flow and Radiation immediately after Falling onto Cavity Floor

(2)Simulation of the phenomena by use of MELCOR and SAMPSON codes

(1)Development of Breakup Particle Agglomeration Model in JASMINE

(2)Analysis by Improved Melt Spreading Model in JASMINE

[2B06-09] Safety Assessment for Fast Reactors 1

Development of empirical correlation for bed high of mixed particles

(4)Effects of test conditions on dispersion and sedimentation of molten-metal in a shallow water pool

(5)A Behavior of a Heavy Metal Jet with Free Surface Conditon of MPS Method

[2B10-13] Safety Assessment for Fast Reactors 2

(9)Uncertainty in Assessments of Initiating Phase in ULOF

(10)Evaluation of discharge amount of core fuel for Transition Phase in ULOF

(11)Best Estimate and Uncertainty Assessment of PAMR/PAHR Phase in ULOF

(12)Criticality Assessment of PAMR Phase in ULOF

[2B14-16] Safety Measures for Sodium Facilities

(1)Behavior of impurity adhesion to sodium equipment

(2)Adhesion behavior of sodium vapor in cover gas region

(3)Burning control for component with sodium deposits during air plasma cutting

[1C01-04] Mitigation Measures Against Severe Accidents

(8)Evaluation of Obstructive facter for hydrogen treatment rate

(9)Evaluation of Steam Influence on Hydrogen Processing Characteristics of Reactor Unit

[1C05-07] Safety Assessment for Light Water Reactors 1

(2)Specification and functions of desktop plant simulator in reactor shutdown condition

(3)Two-way coupling calculation between RPV and SFP

[1C08-12] Safety Assessment for Light Water Reactors 2

[1C13-18] Light Water Reactor Behavior Under Accident Conditions 1

(3)Analysis of Aerosol Behavior

(4)Analysis of SFPAir Coolability

(1)Overall Plan

(2)Transient critical heat flux with 3 x 3 bundle heated rapidly under atmospheric pressure

(3)Development and Verification of A CHF Correlation for Cold RIA

(4)BWR RIA Analysis at Cold Condition

[2C01-06] PRA 1

(1)HRA evaluation results of Tokai No.2 Power Station during Power Operation (Level1)

(1)Development of HRA Guide adopting concept of "Narrative" for Qualitative Analysis

(2)A Concept of Human Failure Events Database

[2C07-10] PRA 2

(1)Evaluation of Seismic Induced Tsunami Event Using DQFM Method

(2)The Comparison of MCS Methodology and DQFM Methodology

[2C11-16] PRA 3

(2)PRA evaluation results of SHIKA NPS unit2 during shutdown state(Level1)

(1)Project summary

(2)Identification Initiating Event and Estimation of Frequency

(3)Analysis of Accident Sequence

(4)Evaluation of Interinfluence between Adjacent Units

[2C17-23] Fukushima Nuclear Accident

Estimated Mechanism of PCV Pressure Variation during the expected MCCI phase

(17)In-depth analysis for Unit-2 accident progression using MAAP code

(18)In-depth analysis for Unit-3 accident progression using MAAP code