Oral Presentation

[2E01-04] Countermeasures against Severe Accident 1

Thu. Sep 8, 2016 9:30 AM - 10:30 AM Room E (Kumume City Plaza - Kurumeza Theatre)

Chair: Yuichi Shimada (JANSI)

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9:30 AM - 9:45 AM

[2E01] AP1000® safety assessment for beyond design basis events

(1)Assessment based on ENSREG stress test

*Yuta Sano¹, Thomas A. Kindred² (1.Westinghouse Electric Japan Ltd., 2.Westinghouse Electric Company)

9:45 AM - 10:00 AM

[2E02] AP1000® safety assessment for beyond design basis events

(2)Assessment for the safety enhancement

*Yukitaka Yamazaki¹, Thomas A. Kindred² (1.Westinghouse Electric Japan Ltd., 2.Westinghouse Electric Company)

10:00 AM - 10:15 AM

[2E03] Development of Accident Tolerant Control Rod for Light Water Reactor

Reactivity Analysis of Innovative Neutron-Absorbing Materials

*Hirokazu Ohta¹, Takanari Ogata¹, Kinya Nakamura¹ (1.CRIEPI)

10:15 AM - 10:30 AM

[2E04] Development of Dry-well Cooler for a Severe Accident

(3)Thermal-Hydraulics Analysis of Dry-well Cooler

*Naoyuki Ishida¹, Yasunori Nagata¹, Yukiko Kushima¹, Kouji Andou¹ (1.Hitachi GE)

Oral Presentation

[2E05-07] Countermeasures against Severe Accident 2

Thu. Sep 8, 2016 10:30 AM - 11:15 AM Room E (Kumume City Plaza - Kurumeza Theatre)

Chair: Kenichi Katono (Hitachi)

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10:30 AM - 10:45 AM

[2E05] Development of Hydrogen Treatment System in Severe Accident

(6)水素処理速度に対する反応材粒径の影響

*Akira Yamada¹, Ryoma Fujihara¹, Ryoji Katsuki¹, Chikako Iwaki¹, Motoshige Yagyu¹, Masato Okamura¹, Masashi Tanabe¹ (1.Toshiba corporation)

10:45 AM - 11:00 AM

[2E06] Development of Hydrogen Treatment System in Severe Accident

(7)反応材粒子径が反応器水素処理特性に与える影響

*Chikako Iwaki¹, Ryoma Fujihara¹, Ryoji Katsuki¹, Akira Yamada¹, Motoshige Yagyu¹, Masato Okamura¹, Masashi Tanabe¹ (1.Toshiba)

11:00 AM - 11:15 AM

[2E07] Sophistication of the filtered containment venting system operation

(7)Relationship of a liquid property and an iodine decontamination performance

*Taizo Kanai¹, Masahiro Furuya¹, Takahiro Arai¹, Yoshihisa Nishi¹ (1.CRIEPI)

Oral Presentation

[2E08-10] Safety Evaluation on LWR 1

Thu. Sep 8, 2016 11:15 AM - 12:00 PM Room E (Kumume City Plaza - Kurumeza Theatre)

Chair: Tatsuya Itoi (Univ. of Tokyo)

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11:15 AM - 11:30 AM

[2E08] Assessment of Defence in depth Level 4 for Ohma Nuclear Power Plant, based on SRS-46

(1)Measures to Reinforce Safety

*Kozo Miyao¹, Tetsurou Kobayashi¹, Satoshi Ishiguro¹ (1.J-POWER)

11:30 AM - 11:45 AM

[2E09] Assessment of Defence in depth Level 4 for Ohma Nuclear Power Plant, based on SRS-46

(2)Assessment Method

*Masanori Ohtani¹, Motoaki Sakashita¹, Kenji Tominaga¹, Akira Yasuo¹ (1.Japan Nuclear Safety Institute)

11:45 AM - 12:00 PM

[2E10] Assessment of Defence in depth Level 4 for Ohma Nuclear Power Plant, based on SRS-46

(3)Assessment Result

*Motoaki Sakashita¹, Masanori Ohtani¹, Toshihiro Kando¹, Tetsurou Kobayashi², Satoshi Ishiguro² (1.Japan Nuclear Safety Institute, 2.J-POWER)

Oral Presentation

[2E11-14] Safety Evaluation on LWR 2

Thu. Sep 8, 2016 2:45 PM - 3:50 PM Room E (Kumume City Plaza - Kurumeza Theatre)

Chair: Hitoshi Muta (Tokyo City Univ.)

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2:45 PM - 3:00 PM

[2E11] Safety analysis and countermeasures for Kashiwazaki Kariwa Nuclear Power Plants.

(1)Volcanic effect asessment for the Kashiwazaki Kariwa Nuclear Power Plants.

*MATSUDA KOSUKE¹, Shuhei Matsunaka², Takashi Ando¹, Manabu Watanabe¹, Tsutomu Itoh¹, Yoshihiro Ooyama¹ (1.Tokyo Electric Power Company Holdings, Inc., 2.Tepco Systems Corporation)

3:00 PM - 3:15 PM

[2E12] Safety analysis and countermeasures for Kashiwazaki Kariwa Nuclear Power Plants.

(2)Tornado effect assessment for the Kashiwazaki Kariwa Nuclear Power Plants.

*takashi ando¹, Shuhei Matsunaka², manabu watanabe¹, Tsutomu Itoh¹, Yoshihiro Ooyama¹ (1.Tokyo Electric Power Company Holings,Inc., 2.Tepco Systems Corporation)

3:15 PM - 3:30 PM

[2E13] Safety analysis and countermeasures for Kashiwazaki Kariwa Nuclear Power Plants.

(3)the combination of external hazards

*Manabu Watanabe¹, Shuhei Matsunaka², Kousuke Matsuda¹, Takashi Ando¹, Tsutomu Itoh¹, Yoshihiro Ooyama¹ (1.TEPCO Holdings, Inc., 2.Tepco Sysmstems Corporation)

3:30 PM - 3:45 PM

[2E14] Safety analysis and countermeasures for Kashiwazaki Kariwa Nuclear Power Plants.

(4)Internal Flood analysis for Kashiwazaki Kariwa Nuclear Power Plants.

*Naoki TAKAHASHI¹, Yoshihiro OYAMA¹ (1.Nuclear Reactor Safety Engineering Group, Nuclear Asset Management Department, TEPCO)

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

Oral Presentation

[2E15-18] LWR performance duirng an accident 2

Thu. Sep 8, 2016 3:50 PM - 4:55 PM Room E (Kumume City Plaza - Kurumeza Theatre)

Chair: Mamoru Konomura (Univ. of Fukui)

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3:50 PM - 4:05 PM

[2E15] Study on molten core coolability under precautionary water injection into containment vessel

(1)Total Plan

*Akitoshi Hotta¹, Miyuki Akiba¹, Akinobu Morita¹ (1.Regulatory Standard and Research DepartmentSecretariat of Nuclear Regulation Authority (S/NRA/R))

4:05 PM - 4:20 PM

[2E16] Study on molten core coolability under precautionary water injection into containment vessel

(2)Experiment on underwater liquid melt spreading

*Miyuki Akiba¹, Akinobu Morita¹, Akitoshi Hotta¹ (1.Regulatory Standard and Research DepartmentSecretariat of Nuclear Regulation Authority (S/NRA/R))

4:20 PM - 4:35 PM

[2E17] Study on molten core coolability under precautionary water injection into containment vessel

(3)Improvement of melt spread model in the JASMINE code

Ryuhei Kawabe¹, Toshinori Matsumoto¹, Tomoyuki Sugiyama¹, *Yu Maruyama¹ (1.Japan Atomic Energy Agency)

4:35 PM - 4:50 PM

[2E18] Study on molten core coolability under precautionary water injection into containment vessel

(4)Improvement of Jet Breakup Model in the JASMINE code

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

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

Oral Presentation

[2E19-24] Improvement of Safety on Spent Fuel Pool

Thu. Sep 8, 2016 4:55 PM - 6:30 PM Room E (Kumume City Plaza - Kurumeza Theatre)

Chair: Kenichi Kanda (CRIEPI)

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4:55 PM - 5:10 PM

[2E19] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(7)Investigation for a modeling of cladding air oxidation

*Yoshiyuki Nemoto¹, Yoshiyuki Kaji¹, Chihiro Ogawa¹, Kazuo Nakashima², Masayuki Tojo² (1.JAEA, 2.GNF-J)

5:10 PM - 5:25 PM

[2E20] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(8)Preliminary Experiment for Evaluation of CCFL Behavior at Upper Tie Plate

*Taku Nagatake¹, Wei Liu¹, Shinichiro Uesawa¹, Yasuo Koizumi¹, Mitsuhiko Shibata¹, Hiroyuki Yoshida¹, Yoshiyuki Nemoto¹, Yoshiyuki Kaji¹ (1.Japan Atomic Energy Agency)

5:25 PM - 5:40 PM

[2E21] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(9)Temperature evaluations of BWR fuels by steady-state heat transfer analyses using 3 dimensional analysis method

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

5:40 PM - 5:55 PM

[2E22] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(10)Effects on criticality due to the differences of water level between in and out of channel box of BWR fuel

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

5:55 PM - 6:10 PM

[2E23] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(11)Evaluation of Cooling Characteristics of SFP Spray and Alternative Water Injection with MAAP Code

*Satoshi Nishimura¹, Masaaki Satake¹, Shota Soga¹, Yoshihisa Nishi¹, Yoshiyuki Kaji², Yoshiyuki Nemoto² (1.CRIEPI, 2.JAEA)

6:10 PM - 6:25 PM

[2E24] Study on Improvement of Safety for Accident Conditions in Spent Fuel Pool

(12)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)

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

Oral Presentation

[1F01-04] Exernal Hazard

Wed. Sep 7, 2016 10:00 AM - 11:00 AM Room F (Kumume City Plaza - Creative Box)

Chair: Koji Morita (Kyushu Univ.)

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10:00 AM - 10:15 AM

[1F01] Research and Development of Margin Assessment Methodology of Decay Heat Removal Function against External Hazards

(15)Progress in JFY2015 and Event Sequence Assessment Methodology against a Combination Hazard of Strong Wind and Rainfall

*Hidemasa Yamano¹, Hiroyuki Nishino¹, Kenichi Kurisaka¹, Yasushi Okano¹, Takashi Takata¹, Takaaki Sakai¹, Takahiro Yamamoto², Yoshihiro Ishizuka², Ryuta Furukawa², Nobuo Geshi² (1.JAEA, 2.AIST)

10:15 AM - 10:30 AM

[1F02] Research and Development of Margin Assessment Methodology of Decay Heat Removal Function against External Hazards

(16)Selection of Combination Hazard Events for Safety Assessment and Event Sequence Assessment Methodology against a Combination Hazard of Snow and Low Temperature

*Hiroyuki Nishino¹, Hidemasa Yamano¹, Kenichi Kurisaka¹ (1.JAEA)

10:30 AM - 10:45 AM

[1F03] Research and Development of Margin Assessment Methodology of Decay Heat Removal Function against External Hazards

(17)Combination Hazard Curve Evaluation of Forest Fire and Thunder

*Yasushi OKANO¹, Hidemasa YAMANO¹ (1.Japan Atomic Energy Agency)

10:45 AM - 11:00 AM

[1F04] Research and Development of Margin Assessment Methodology of Decay Heat Removal Function against External Hazards

(18)Numerical Quantification of Plant State based on CMMC Method under Strong Rainfall Hazard

*Takashi Takata¹ (1.Japan Atomic Energy Agency)

Oral Presentation

[1F05-08] Probabilistic Risk Assessment 1

Wed. Sep 7, 2016 11:00 AM - 12:00 PM Room F (Kumume City Plaza - Creative Box)

Chair: Takashi Takata (JAEA)

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11:00 AM - 11:15 AM

[1F05] Method of multiple failure initiating events for seismic PRA

(3)Analysis of Model Plant and issue of Evaluation Method

*Hiromichi Miura¹, Ryou Inomata¹, Tsuyoshi Uchida¹, Katsunori Ogura¹, Yuki Kameko², Ken Muramatsu², Hitoshi Muta² (1.Central Research Institute of Electric Power Industry, 2.Tokyo City Univ.)

11:15 AM - 11:30 AM

[1F06] Method of multiple failure initiating events for seismic PRA

(4)Analysis of Core Damage Probability

*Yuki Kameko¹, Ken Muramatsu¹, Hitoshi Muta¹, Hiromichi Miura², Ryou Inomata², Tsuyoshi Uchida², Katsunori Ogura² (1.Graduate School Tokyo City University , 2.Central Research Institute of Electric Power Industry)

11:30 AM - 11:45 AM

[1F07] A methodology for establishing margin to facilities and equipment used during core damage accidents

*Yuki Iita¹, Tatsuya Itoi¹, Naoto Sekimura¹ (1.The University of Tokyo)

11:45 AM - 12:00 PM

[1F08] Study on Development of Level 2 PRA Methodology Considering Seismic Impact

*MOTOHISA MIYASHITA¹, HITOSHI MUTA¹, KEN MURAMATSU¹ (1.TOKYO CITY UNIVERSITY GRADUATE DIVISION)

Oral Presentation

[1F09-13] Probabilistic Risk Assessment 2

Wed. Sep 7, 2016 2:45 PM - 4:05 PM Room F (Kumume City Plaza - Creative Box)

Chair: Yoshiyuki Narumiya (KEPCO)

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2:45 PM - 3:00 PM

[1F09] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(1)Review of Requirements on Scenario Identification and Reliability Data Development

*Ken MURAMATSU Muramatsu¹, Hitoshi Muta¹, Kosuke Matsuda¹, Hiroyuki Sato², Hirohumi Ohashi², Akemi Nishida², Tatsuya Itoi³, Masayuki Tanabe⁴ (1.Tokyo City University, 2.Japan Atomic Energy Agency, 3.The University of Tokyo, 4.JGC Corporation)

3:00 PM - 3:15 PM

[1F10] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(2)Development of Source Term Evaluation Method

*Yuki Honda¹, Hiroyuki Sato¹, Hirofumi Ohashi¹, Akemi Nishida¹, Hitoshi Muta², Ken Muramatsu², Tatsuya Itoi³, Masayuki Tanabe⁴ (1.JAEA, 2.Tokyo City University, 3.The University of Tokyo, 4.JGC Corporation)

3:15 PM - 3:30 PM

[1F11] Development of Dynamic Probabilistic Risk Assessment Model for PWR using Simplified Plant Simulation

*Shohei Otsuki¹, Tomohiro Endo¹, Akio Yamamoto¹ (1.Nagoya University Graduate School of Engineering)

3:30 PM - 3:45 PM

[1F12] Conditional Monte Carlo method for large scale event tree analysis

*Shota Soga¹ (1.Central Research Institute of Electric Power Industry)

3:45 PM - 4:00 PM

[1F13] Dynamic Risk Assessment of Combined Event of Earthquake and Seismic-induced Internal Flooding in Nuclear Power Plant

*SUNGHYON JANG¹, TAKAHIRO SUZUKI², AKIRA YAMAGUCHI³ (1.Department of Nuclear Engineering and Management, The University of Tokyo, 2.Department of Engineering, The University of Tokyo, 3.Nuclear Professional School, The University of Tokyo)

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

Oral Presentation

[1F14-19] Fukushima Nuclear Power Plant Accident

Wed. Sep 7, 2016 4:05 PM - 5:40 PM Room F (Kumume City Plaza - Creative Box)

Chair: Hiroshi Kawai (TEPSYS)

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4:05 PM - 4:20 PM

[1F14] Study on ascertaining and analyzing reactor core status by MAAP code

(13)Current status of the MAAP enhancement project

*Yoshiji Karino¹, Yoshihiro Kojima¹, Rui Chihara¹, Koji Nishida² (1.IRID(Toshiba), 2.IRID(Hitachi-GE))

4:20 PM - 4:35 PM

[1F15] Study on ascertaining and analyzing reactor core status by MAAP code

(14)Unit-1 accident progression analysis by the improved MAAP code

*TAKESHI SAKAI^2,1, Tadashi Fujii^2,1, Kojo Nishida^2,1 (1.Hitachi-GE, 2.IRID)

4:35 PM - 4:50 PM

[1F16] Study on ascertaining and analyzing reactor core status by MAAP code

(15)Unit-2 accident progression analysis by the improved MAAP code

Rui Chihara¹, *Yoshihiro Kojima¹, Yoshiji Karino¹ (1.IRID(Toshiba))

4:50 PM - 5:05 PM

[1F17] Study on ascertaining and analyzing reactor core status by MAAP code

(16)Unit-3 accident progression analysis by the improved MAAP code

*Yoshihiro Kojima¹, Yoshiji Karino¹, Rui Chihara¹ (1.IRID(Toshiba))

5:05 PM - 5:20 PM

[1F18] Exploration for buried object in concrete using phased array method

*akio sumita¹, kenji osaki¹, katsumi masaki¹ (1.TOSHIBA)

5:20 PM - 5:35 PM

[1F19] Operation Side Ideas of the Searching of the Nuclear Reactor Conditions at SBO

(5)Understanding of the Operation of IC by New Modeling Analysis and Incidental Manual

*Kazuo Watanabe¹ (1.Watanabe Lab. for WNR Cx)

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

Oral Presentation

[1F20-23] LWR performance duirng an accident 1

Wed. Sep 7, 2016 5:40 PM - 6:45 PM Room F (Kumume City Plaza - Creative Box)

Chair: Koichi Nakamura (CRIEPI)

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5:40 PM - 5:55 PM

[1F20] Study on Enhancement of Containment Behavior Analysis for LWR

*Tazai Ayuko¹, Hitoshi Muta¹, Ken Muramatsu¹ (1.Graduate school of Tokyo City University)

5:55 PM - 6:10 PM

[1F21] Thermal-hydraulic Analysis of BWR Containment Response to Accidents using the GOTHIC Thermal Hydraulic Analysis Package

(1)Hydrogen Concentration Analysis

*Hiroshi Kawai¹, Kouta Tominaga¹, Daisuke Fujiwara¹ (1.TEPCO SYSTEMS CORPORATION)

6:10 PM - 6:25 PM

[1F22] Structural Integrity Sensitivity Analysis of Reactor Pressure Vessel Based on Probabilistic Fracture Mechanics During Thermal Transient Condition

*Ryuta Okayama¹, Suzuki Masahide¹, Yinsheng Li², Jinya katsuyama² (1.Nagaoka university of technology, 2.Japan Atomic Energy Agency)

6:25 PM - 6:40 PM

[1F23] Performance evaluation of EPDM at elevated temperature

*ken suzuki¹, Shinichi Matsuda², Naoya Kani², Takuya Sugimura², Yusuke Tsutsumi¹ (1.NIPPON VALQUA INDUSTRIES, 2.Chubu Electric Power)

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

Oral Presentation

[2G10-13] Evaluation of Source Term and Radiation Dose 1

Thu. Sep 8, 2016 2:45 PM - 3:50 PM Room G (Kumume City Plaza - Studio 2)

Chair: Takao Kojima (OPU)

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2:45 PM - 3:00 PM

[2G10] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(5)A study of the quantification method of the Source-Term-Event-Tree

*Hiroshi Endo¹, Koichi Nakamura¹, Atsushi Ui¹, Hiromichi Miura¹, Keigo Murata¹, Yoko Yamane¹ (1.CRIEPI)

3:00 PM - 3:15 PM

[2G11] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(6)Study on the PRD method of Cesium release behavior used in the Source-Term-Event-Tree

*Koichi Nakamura¹, Keigo Murata¹, Yoko Yamane¹, Atsushi Ui¹, Hiroshi Endo¹ (1.CRIEPI, Nuclear Technology Research Laboratory, Reactor Systems Safety)

3:15 PM - 3:30 PM

[2G12] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(7)A study of cesium release behaviors dependent on plant design conditions after the containment failure

*KEIGO MURATA¹, KOICHI NAKAMURA¹, ATSUSHI UI¹, YOKO YAMANE¹, HIROSHI ENDO¹ (1.Central Research Institute of Electric Power Industry)

3:30 PM - 3:45 PM

[2G13] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(8)A Study on Unceartainty Analysis for Cesium Release considering Uncertainty of Accident Management Measures

*Atsushi Ui¹, Hiromichi Miura¹, Koichi Nakamura¹, Keigo Murata¹, Yoko Yamane¹, Hiroshi Endo¹ (1.CRIEPI)

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

Oral Presentation

[2G14-17] Evaluation of Source Term and Radiation Dose 2

Thu. Sep 8, 2016 3:50 PM - 4:55 PM Room G (Kumume City Plaza - Studio 2)

Chair: Hiroshi Endo (CRIEPI)

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3:50 PM - 4:05 PM

[2G14] Evaluation of FP chemistry for improvement of source term estimation method

(1)Experimental evaluation of B effects on revaporization behavior of Cs and I

*Shuhei Miwa¹, Masanori Shinada¹, Masahiko Osaka¹, Tomoyuki Sugiyama¹, Yu Maruyama¹ (1.JAEA)

4:05 PM - 4:20 PM

[2G15] Evaluation of FP chemistry for improvement of source term estimation method

(2)Analytical study for B effects on revaporization behavior of Cs and I

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

4:20 PM - 4:35 PM

[2G16] Fundamental study on emergency response on Co-60 underwater irradiator

(1)Assessment of dose rate in the irradiation building with decrease in the pool water level

*Takao KOJIMA¹, Hiroyuki Miyamaru¹, Ryoichi Taniguchi¹ (1.Radiat. Res. Ctr., Osaka Pref. Univ.)

4:35 PM - 4:50 PM

[2G17] Adsorption characteristics of methyl iodine on AgX in low temperature region

*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

[2G18-22] Risk Evaluation on Reprocessing Plant 1

Thu. Sep 8, 2016 4:55 PM - 6:15 PM Room G (Kumume City Plaza - Studio 2)

Chair: Hidemasa Yamano (JAEA)

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4:55 PM - 5:10 PM

[2G18] Study on Risk Assessment for Fuel Fabrication and Fuel Reprocessing Facilities

(1)An Example of Risk Assessment Procedures

*Mitsuhiro Takanashi¹, Muneyuki Yokotsuka¹, Kenji Mori¹, Kazuki Yamate¹ (1.Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority (S/NRA/R))

5:10 PM - 5:25 PM

[2G19] Study on Risk Assessment for Fuel Fabrication and Fuel Reprocessing Facilities

(2)Concurrent Occurrences of Severe Accidents

*Muneyuki Yokotsuka¹, Mitsuhiro Takanashi¹, Noriaki Sasaki¹, Kazuki Yamate¹ (1.Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority(S/NRA/R))

5:25 PM - 5:40 PM

[2G20] Study on Risk Assessment for Fuel Fabrication and Fuel Reprocessing Facilities

(3)Issues in Simplified Hybrid Method

*Kenji MORI¹, Takashi YAMADA¹, Kazuki YAMATE¹ (1.Seretariat of NRA Division of Research for Nuclear Fuel Cycle & Radioactive Waste)

5:40 PM - 5:55 PM

[2G21] Examination of construction procedure of MLD at Reprocessing Plant

*Masahiro Yamamoto¹, Yoshikazu Tamauchi¹, Hiroshi Kinuhata¹, Naoki Takahashi¹ (1.JNFL)

5:55 PM - 6:10 PM

[2G22] Evaluation of hydrogen gas production at transient criticality in Uranyl nitrate solution

*Ryoichiro Yoshida¹, Yuichi Yamane¹, Hitoshi Abe¹ (1.JAEA )

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

Oral Presentation

[3G01-04] Safety Evaluation on LWR 3

Fri. Sep 9, 2016 9:30 AM - 10:35 AM Room G (Kumume City Plaza - Studio 2)

Chair: Yoshihiro Kojima (TOSHIBA CORPORATION)

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9:30 AM - 9:45 AM

[3G01] Development of Tool for Containment Vent Timing using MAAP Database

(1)Development of Tool

*Hidetaka Imai¹, Takashi Takiguchi¹, Ryousuke Katayose¹, Daisuke Fujiwara², Hiroshi Kawai² (1.TEPCO HOLDINGS, 2.TepcoSystems)

9:45 AM - 10:00 AM

[3G02] Development of Tool for Containment Vent Timing Prediction using MAAP Database

(2)Verification & Valication of Tool

*Daisuke Fujiwara¹, Hidetaka Imai², Takashi Takiguchi², Ryosuke Katayose², Hiroshi Kawai¹ (1.TEPCO SYSTEMS, 2.TEPCO Holdings)

10:00 AM - 10:15 AM

[3G03] Development and use of core damage pre-determination tool in case of low-pressure water injection during accident

*ryosuke katayose¹, Hidetaka Imai¹, Yasuo Ishizaki¹ (1.Tokyo Electric Power Company Holdings, Inc.)

10:15 AM - 10:30 AM

[3G04] Development of the guideline of Japan version Safety Assessment Report (JSAR)

*Yuichi Shimada¹, Satoshi Kurata¹, Katsuyuki Kumasaka¹, Masayuki Tabata¹, Koichi Mizuno¹, Yukio Furutani¹, Kenichi Yasuda⁴, Mitsuhiro Kano³, Kazutoshi Eto⁵, Hirohide Oikawa² (1.Japan Nuclear Safety Institute , 2.Toshiba, 3.MHI, 4.Hitachi-GE, 5.Kyushu Electric Power Company)

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

Oral Presentation

[3G05-09] Earthquake Resistant Technology 1

Fri. Sep 9, 2016 10:35 AM - 12:00 PM Room G (Kumume City Plaza - Studio 2)

Chair: Takenori Hida (Univ. of Tokyo)

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10:35 AM - 10:50 AM

[3G05] Improvement of fragility evaluation method on seismic PRA

(1)Overview

*Katsumi Ebisawa¹, Hiroyuki Yamada¹, Ryusuke Haraguchi², Kazuhiko Kikuchi³ (1.CRIEPI, 2.MHI, 3.YONDEN)

10:50 AM - 11:05 AM

[3G06] Improvement of fragility evaluation method on seismic PRA

(2)Improvement of input seismic motion response factor and building response factor

*Hiroyuki Yamada¹, Katsumi Ebisawa¹, Takeshi Ugata², Ryusuke Haraguchi³, Kazuhiko Kikuchi⁴, Kohei Tanaka⁵, Tsuyoshi takada⁶ (1.CRIEPI, 2.TAISEI, 3.MHI, 4.YONDEN, 5.RTRI, 6.The Univ. of Tokyo)

11:05 AM - 11:20 AM

[3G07] Improvement of fragility evaluation method on seismic PRA

Confirmation of feasibility of systematization on component fragility evaluation

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

11:20 AM - 11:35 AM

[3G08] Advancement of Seismic Evaluation Method Considering three Dimensional Fuel Assembly Displacement in FBR Core

(1)Considering Influence on the Horizontal Support Condition Caused by a Big Earthquake

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

11:35 AM - 11:50 AM

[3G09] Advancement of Seismic Evaluation Method Considering three Dimensional Fuel Assembly Displacement in FBR Core

(2)Considering Deformation due to Irradiation and Heat

Akihisa Iwasaki¹, Masatsugu Monde¹, *Shinichiro MATSUBARA¹, Iwao Ikarimoto¹ (1.MHI)

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

Oral Presentation

[3G10-13] Earthquake Resistant Technology 2

Fri. Sep 9, 2016 2:45 PM - 3:50 PM Room G (Kumume City Plaza - Studio 2)

Chair: Katsumi Ebisawa (CRIEPI)

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2:45 PM - 3:00 PM

[3G10] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 3: Analytical model of seismic isolated structure

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

3:00 PM - 3:15 PM

[3G11] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 4: Cliff Edge Assessment Model of Systems and Components for Nuclear Power Plant

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

3:15 PM - 3:30 PM

[3G12] Development of seismic counter measures against cliff edges for enhancement of comprehensive safety of nuclear power plants

Part 5: Investigation of seismic behavior of human

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

3:30 PM - 3:45 PM

[3G13] Application concept of margin analysis utilizing accident sequences for fault displacement

*Masanobu Kmiya¹, Syuuji Kanaida¹, Kouichi Kamiya¹, Tsutomu Ogawa¹ (1.The Japan Atomic Power Company)

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

Oral Presentation

[3G14-16] Earthquake Resistant Technology 3

Fri. Sep 9, 2016 3:50 PM - 4:40 PM Room G (Kumume City Plaza - Studio 2)

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

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3:50 PM - 4:05 PM

[3G14] Development of Seismic Isolation Technology for Nuclear Power Plant

(1)A Fragility Evaluation for Seismic Isolation System Applied to NPPs

*Takahide Akimoto¹, Shin-ich Yoshida¹, Yoshitaka Takeuchi¹, Yasuo Okochi², Shinji Kosugi³, Kunihiko Sato⁴, Hideo Hirai⁵ (1.Obayashi Corporation., 2.Chubu Electric Power Co., Inc., 3.Hitachi-GE Nuclear Energy, Ltd., 4.Mitsubishi Heavy Industries, Ltd., 5.Toshiba Corporation)

4:05 PM - 4:20 PM

[3G15] Development of Seismic Isolation Technology for Nuclear Power Plant

(2)A Fragility Evaluation for Crossover Piping System

*SHUNSUKE FUKUSHIMA¹, Masakazu JIMBO¹, Akihito OTANI², Tetsuo IMAOKA⁴, Kunihiko SATO³, Ryusuke HARAGUCHI³, Shigenobu ONISHI⁵, Yutaka Suzuki⁶ (1.Toshiba Corporation, 2.IHI Corporation, 3.Mitsubishi Heavy Industries, Ltd, 4.Hitachi-GE Nuclear Energy, Ltd, 5.Chubu Electric Power Co., Inc., 6.MHI Nuclear Systems And Solution Engineering Co., Ltd)

4:20 PM - 4:35 PM

[3G16] Development of Seismic Isolation Technology for Nuclear Power Plant

(3)Seismic PRA for the Seismic Isolated Nuclear Power Plants

*Ryusuke Haraguchi¹, Shigenobu Onishi², Masakazu Jimbo³, Tetsuo Imaoka⁴ (1.Mitsubishi Heavy Industries, LTD., 2.Chubu Electric Power Co. Inc., 3.Toshiba Corporation, 4.Hitachi-GE Nuclear Energy, Ltd.)

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

Oral Presentation

[3H01-05] Risk Evaluation on Reprocessing Plant 2

Fri. Sep 9, 2016 9:30 AM - 10:50 AM Room H (Kumume City Plaza - Studio 3)

Chair: Mitsuhiro Takanashi (NRA)

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9:30 AM - 9:45 AM

[3H01] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(4)Hydrogen explosion experiment of simulated small annular vessel

*Takashi Kobayashi¹, Takeshi Mikami¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yosikazu Tamauchi², Masanao Nakano², Naoya Sakagami², Kouhei Ootake², Tatsuya Kudou², Nobuyuki Arai² (1.Mitsubishi Materials Corporation, 2.Japan Nuclear Fuel Limited)

9:45 AM - 10:00 AM

[3H02] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(5)Combustion analysis and structural analysis of simulated small annular vessel

*Wenbin Dai¹, Yoshinori Hirashima¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Masanao Nakano², Naoya Sakagami², Kouhei Ootake², Tatsuya Kudou², Nobuyuki Arai² (1.Mitsubishi Materials Corporation, 2.Japan Nuclear Fuel Limited)

10:00 AM - 10:15 AM

[3H03] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(6)Hydrogen explosion experiment of simulated small plate vessel

*Takeshi Mikami¹, Takashi Kobayashi¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Masanao Nakano², Naoya Sakagami², Kouhei Ootake², Tatsuya Kudou², Nobuyuki Arai² (1.Mitsubishi Materials Corporation, 2.Japan Nuclear Fuel Limited Corporation)

10:15 AM - 10:30 AM

[3H04] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(7)Combustion analysis and structural analysis of simulated small plate vessel

*Yoshinori Hirashima¹, Wenbin Dai¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Masanao Nakano², Naoya Sakagami², Kouhei Ootake², Tatsuya kudou², Nobuyuki Arai² (1.Mitsubishi Materials Corporation, 2.Japan Nuclear Fuel Limited)

10:30 AM - 10:45 AM

[3H05] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(8)Comparison with numerical analysis and experiment of small scale vessels

*Yoshikazu Tamauchi¹, Masanao Nakano¹, Naoya Sakagami¹, Kouhei Ootake¹, Tatsuya Kudou¹, Nobuyuki Arai¹, Wenbin Dai², Motohiro Sakaihara², Osamu Kanehira² (1.Japan Nuclear Fuel Limited, 2.Mitsubishi Material Corporation)

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

Oral Presentation

[3H06-09] Development of Test Facility and Technology

Fri. Sep 9, 2016 10:50 AM - 12:00 PM Room H (Kumume City Plaza - Studio 3)

Chair: Kenji Kamiyama (JAEA)

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10:50 AM - 11:05 AM

[3H06] Development of plasma heating technology for simulation of LWR severe accident behavior

(1)Objectives and JFY2014 Outcomes

*Ikken Sato¹, Yuta Abe¹, Toshio Nakagiri¹, Yuji Nagae¹, Akihiro Ishimi¹ (1.Japan Atomic Energy Agency)

11:05 AM - 11:20 AM

[3H07] Development of plasma heating technology for simulation of LWR severe accident behavior

(2)JFY2015 Outcomes and summary

*Yuta Abe¹, Ikken Sato¹, Toshio Nakagiri¹, Yuji Nagae¹, Akihiro Ishimi¹ (1.JAEA)

11:20 AM - 11:35 AM

[3H08] Development of evaluation system for viscosity coefficient and surface tension with laser-induced capillary wave

Toward analyzing fluid properties of molten fuel

*Masanari Kuroiwa¹, Kazuya Idemitsu¹, Yaohiro Inagaki¹, Tatsumi Arima¹ (1.Kyushu University Faculty of Engineering)

11:35 AM - 11:50 AM

[3H09] Development of fuel degradation and relocation test equipment under severe accident

(2)Degradation behavior of test bundle in steam environments at high temperature

*Kinya Nakamura¹, Takanari Ogata¹, Shigeru Kurematsu², Toshiya Kido², Masaki Kurata³ (1.CRIEPI, 2.NDC, 3.JAEA)

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

Oral Presentation

[3H10-13] Safety Evaluation on Fast Rector 1

Fri. Sep 9, 2016 2:45 PM - 3:50 PM Room H (Kumume City Plaza - Studio 3)

Chair: Yoshitaka Fukano (JAEA)

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2:45 PM - 3:00 PM

[3H10] Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors

(1)Overall plan

*Kenji Kamiyama¹, Ken-ichi Matsuba¹, Mikio Isozaki¹, Yuya Imaizumi¹, Tohru Suzuki¹, Yuki Emura¹ (1.Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[3H11] Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors

(2)Experimental study on molten-metal discharge into a shallow water pool

*Yuya Imaizumi¹, Kenji Kamiyama¹, Ken-ichi Matsuba¹, Mikio Isozaki¹, Tohru Suzuki¹, Yuki Emura¹ (1.JAEA)

3:15 PM - 3:30 PM

[3H12] Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors

(3)A simulation of a heavy metal jet with MPS method

*Mamoru Konomura¹, Kenji Kamiyama² (1.University of Fukui, 2.Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[3H13] Development of an evaluation methodology for in-place cooling of degraded core materials in the core disruptive accident of sodium-cooled fast reactors

Study on key phenomena

*Mitsuhiro Aoyagi¹, Kenji Kamiyama¹, Tohru Suzuki¹, Ken-ichi Matsuba¹ (1.JAEA)

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

Oral Presentation

[3H14-17] Safety Evaluation on Fast Rector 2

Fri. Sep 9, 2016 3:50 PM - 4:55 PM Room H (Kumume City Plaza - Studio 3)

Chair: Satoshi Nishimura (CRIEPI)

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3:50 PM - 4:05 PM

[3H14] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(13)Simulation of Na-concrete reaction process

*Munemichi Kawaguchi¹, Shinya Miyahara¹, Masayoshi Uno² (1.JAEA, 2.Fukui Univ.)

4:05 PM - 4:20 PM

[3H15] Quantification of Loss-of-Reactor-Level Accident of Sodium-Cooled Fast Reactor with Continuous Markov Chain and Monte Carlo Method

*Ye YI¹, Sunghyon Jang¹, Akira Yamaguchi¹ (1.University of Tokyo)

4:20 PM - 4:35 PM

[3H16] Evaluation on hypothetical total instantaneous flow blockage at the inlet of fuel subassembly in a sodium-cooled fast reactor

*Yoshitaka Fukano¹ (1.JAEA)

4:35 PM - 4:50 PM

[3H17] Fundamental Study on Sloshing Behavior of Disrupted Core Pool

Effects of Movement Characteristics on the Reactivity Insertion (2)

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

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

Sessions

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

[2E01-04] Countermeasures against Severe Accident 1

(1)Assessment based on ENSREG stress test

(2)Assessment for the safety enhancement

Reactivity Analysis of Innovative Neutron-Absorbing Materials

(3)Thermal-Hydraulics Analysis of Dry-well Cooler

[2E05-07] Countermeasures against Severe Accident 2

(6)水素処理速度に対する反応材粒径の影響

(7)反応材粒子径が反応器水素処理特性に与える影響

(7)Relationship of a liquid property and an iodine decontamination performance

[2E08-10] Safety Evaluation on LWR 1

(1)Measures to Reinforce Safety

(2)Assessment Method

(3)Assessment Result

[2E11-14] Safety Evaluation on LWR 2

(1)Volcanic effect asessment for the Kashiwazaki Kariwa Nuclear Power Plants.

(2)Tornado effect assessment for the Kashiwazaki Kariwa Nuclear Power Plants.

(3)the combination of external hazards

(4)Internal Flood analysis for Kashiwazaki Kariwa Nuclear Power Plants.

[2E15-18] LWR performance duirng an accident 2

(1)Total Plan

(2)Experiment on underwater liquid melt spreading

(3)Improvement of melt spread model in the JASMINE code

(4)Improvement of Jet Breakup Model in the JASMINE code

[2E19-24] Improvement of Safety on Spent Fuel Pool

(7)Investigation for a modeling of cladding air oxidation

(8)Preliminary Experiment for Evaluation of CCFL Behavior at Upper Tie Plate

(9)Temperature evaluations of BWR fuels by steady-state heat transfer analyses using 3 dimensional analysis method

(10)Effects on criticality due to the differences of water level between in and out of channel box of BWR fuel

(11)Evaluation of Cooling Characteristics of SFP Spray and Alternative Water Injection with MAAP Code

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

[1F01-04] Exernal Hazard

(15)Progress in JFY2015 and Event Sequence Assessment Methodology against a Combination Hazard of Strong Wind and Rainfall

(16)Selection of Combination Hazard Events for Safety Assessment and Event Sequence Assessment Methodology against a Combination Hazard of Snow and Low Temperature

(17)Combination Hazard Curve Evaluation of Forest Fire and Thunder

(18)Numerical Quantification of Plant State based on CMMC Method under Strong Rainfall Hazard

[1F05-08] Probabilistic Risk Assessment 1

(3)Analysis of Model Plant and issue of Evaluation Method

(4)Analysis of Core Damage Probability

[1F09-13] Probabilistic Risk Assessment 2

(1)Review of Requirements on Scenario Identification and Reliability Data Development

(2)Development of Source Term Evaluation Method

[1F14-19] Fukushima Nuclear Power Plant Accident

(13)Current status of the MAAP enhancement project

(14)Unit-1 accident progression analysis by the improved MAAP code

(15)Unit-2 accident progression analysis by the improved MAAP code

(16)Unit-3 accident progression analysis by the improved MAAP code

(5)Understanding of the Operation of IC by New Modeling Analysis and Incidental Manual

[1F20-23] LWR performance duirng an accident 1

(1)Hydrogen Concentration Analysis

[2G10-13] Evaluation of Source Term and Radiation Dose 1

(5)A study of the quantification method of the Source-Term-Event-Tree

(6)Study on the PRD method of Cesium release behavior used in the Source-Term-Event-Tree

(7)A study of cesium release behaviors dependent on plant design conditions after the containment failure

(8)A Study on Unceartainty Analysis for Cesium Release considering Uncertainty of Accident Management Measures

[2G14-17] Evaluation of Source Term and Radiation Dose 2

(1)Experimental evaluation of B effects on revaporization behavior of Cs and I

(2)Analytical study for B effects on revaporization behavior of Cs and I

(1)Assessment of dose rate in the irradiation building with decrease in the pool water level

[2G18-22] Risk Evaluation on Reprocessing Plant 1

(1)An Example of Risk Assessment Procedures

(2)Concurrent Occurrences of Severe Accidents

(3)Issues in Simplified Hybrid Method

[3G01-04] Safety Evaluation on LWR 3

(1)Development of Tool

(2)Verification & Valication of Tool

[3G05-09] Earthquake Resistant Technology 1

(1)Overview

(2)Improvement of input seismic motion response factor and building response factor

Confirmation of feasibility of systematization on component fragility evaluation

(1)Considering Influence on the Horizontal Support Condition Caused by a Big Earthquake

(2)Considering Deformation due to Irradiation and Heat

[3G10-13] Earthquake Resistant Technology 2

Part 3: Analytical model of seismic isolated structure

Part 4: Cliff Edge Assessment Model of Systems and Components for Nuclear Power Plant

Part 5: Investigation of seismic behavior of human