Oral presentation

[1M01-04] Fukushima Daiichi Nuclear Power Plant Accident

Mon. Mar 27, 2017 10:05 AM - 11:10 AM Room M (16-504 Building No.16)

Chair: Chiaki Kino (IAE)

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10:05 AM - 10:20 AM

[1M01] IC was no operation between earthquake and tunami in F1 No.1 Reactor

Observation of operation manual at accident

*kiyoshi yoneyama¹ (1. H.O.Yoneyama)

10:20 AM - 10:35 AM

[1M02] Final Report of Study Group on Tsunami Countermeasures for Fukushima Accident

*Ritsuo Yoshioka¹, Masaaki Fuchigami², Kenji Iino³ (1. Japan Functional Safety Laboratory, 2. Komatsu Ltd., 3. SYDROSE LP)

10:35 AM - 10:50 AM

[1M03] Correction for pressure measurement data of Fukushima Daiichi NPP Unit 3 and hints for understanding on accident progression behavior based on the corrected data

*Ikken Sato¹ (1. Japan Atomic Energy Agency)

10:50 AM - 11:05 AM

[1M04] Investigation of the accident events which occurred in TEPCO Fukushima Daiichi NPS (second report)

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

Time reserved for Chair （11:05 AM - 11:10 AM）

Oral presentation

[1M05-07] Reprocessing Plant

Mon. Mar 27, 2017 11:10 AM - 12:00 PM Room M (16-504 Building No.16)

Chair: Yoshitaka Yoshida (INSS)

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11:10 AM - 11:25 AM

[1M05] Study on the combustion behaivior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(9)Hydrogen explosion experiment of simulated two large cylindrical vessels connected via vessel off gas ventilation system

*Takashi Kobayashi¹, Takeshi Mikami¹, Motohiro Sakaihara¹, Osamu Kanehira¹, Yoshikazu Tamauchi², Tatsuya Kudo², Masanao Nakano², Naoya Sakagami², Kohei Otake², Nobuyuki Arai² (1. Mitsubishi Materials Corporation, 2. Japan Nuclear Fuel limited)

11:25 AM - 11:40 AM

[1M06] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(10)Combustion analysis and structural analysis of simulated two large cylindrical vessels connected via vessel off gas ventilation system

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

11:40 AM - 11:55 AM

[1M07] Study on the combustion behavior of radiolytically generated hydrogen explosion in vessels at the reprocessing plant

(11)Comparison with numerical analysis and experiment of simulated two large cylindrical vessels connected via vessel off gas ventilation system

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

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

Oral presentation

[1M08-11] External Hazard Including Security Issue

Mon. Mar 27, 2017 2:45 PM - 3:50 PM Room M (16-504 Building No.16)

Chair: Hidehiko Kuroda (TOSHIBA)

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2:45 PM - 3:00 PM

[1M08] Research and Development of Probabilistic Risk Assessment Methodology of External Hazard Combinations

Identification of Hazard Combinations in terms of Impacts on SFR Decay Heat Removal System with Final Heat Sink of Ambient Air

*Yasushi OKANO¹, Hidemasa Yamano¹, Takashi Takata¹, Hiroyuki Nishino¹, Kenichi Kurisaka¹ (1. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1M09] Research and Development of Margin Assessment Methodology of Decay Heat Removal Function against External Hazards

(19)Margin Assessment Methodology against a Combination Hazard of Strong Wind and Rainfall

*Hidemasa Yamano¹, Hiroyuki Nishino¹, Kennichi Kurisaka¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[1M10] Interface of Nuclear Safety and Security

(1)Problem extraction for 2S interface

*Kazuyuki Demachi¹, Mitsutoshi Suzuki², Takashi Takata², Yoshiki Kimura², yo Nakamura², Masaaki Suzuki³, Yoshiyuki Narumiya⁴, Hiroshi Miyano⁵ (1. The University of Tokyo, 2. Japan Atomic Energy Agency, 3. Tokyo University of Science, 4. Kansai Electric Power Co., Inc., 5. Hosei University)

3:30 PM - 3:45 PM

[1M11] Interface of Nuclear Safety and Security

(2)Vital Area Identification (VAI) and response to severe accident initiated by security incident

*Mitsutoshi Suzuki¹, Kazuyuki Demachi² (1. Japan Atomic Energy Agency, 2. The University of Tokyo)

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

Oral presentation

[1M12-18] Evaluation of Source Term and Radiation Dose

Mon. Mar 27, 2017 3:50 PM - 5:45 PM Room M (16-504 Building No.16)

Chair: Shogo Higaki (Univ. of Tokyo)

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3:50 PM - 4:05 PM

[1M12] Adsorption characteristics of methyl iodine on AgX in low temperature region-Part 2

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

4:05 PM - 4:20 PM

[1M13] Analysis of iodine behavior experiments under the severe accident condition using MAAP5 code

*Toru Sakamoto¹, Daisuke Fujiwara¹ (1. TEPSYS)

4:20 PM - 4:35 PM

[1M14] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(9)Research on the applicability of PRD method to Containment functional failure frequency due to the severe accident

*Koichi Nakamura¹, Yoko Yamane², Keigo Murata³, Atsushi Ui¹, Hiroshi Endo¹ (1. Central Research Institute of Electric Power Industry, 2. Advancesoft Corporation, 3. Trust Tech)

4:35 PM - 4:50 PM

[1M15] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

(10)Research on the applicability of PRD method to cesium release behavior due to the severe accident

*Yoko Yamane¹, Koichi Nakamura², Keigo Murata³, Atsushi Ui², Hiroshi Endo² (1. Advancesoft Corporation, 2. Central Research Institute of Electric Power Industry, 3. Trust Tech)

4:50 PM - 5:05 PM

[1M16] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

Research on the effectivity of measures for prevention containment vessel failure due to the sever accident

*Keigo Murata¹, Koichi Nakamura³, Yoko Yamane², Atsushi Ui³, Hiroshi Endo³ (1. TRUSTTECH Corporation, 2. AdvanceSoft Corporation, 3. Central Research Institute of Electric Power Industry)

5:05 PM - 5:20 PM

[1M17] Development of the evaluation method of cesium release in level 2 probabilistic risk assessment

Investigation of source term risk assessment using Artificial Intelligence (AI)

*Taizo Kanai¹, Hiroshi Endo¹ (1. CRIEPI)

5:20 PM - 5:35 PM

[1M18] Development of the evaluation method of cesiumu release in lebvel 2 probabilistic risk assessment

(13)Quantification method of the source term event tree (STET)

*Hiroshi Endo¹, Yoko Yamane², Koichi Nakamura¹, Atsushi Ui¹, Taizo Kanai¹, Keigo Murata³ (1. CRIEPI , 2. AdvanceSoft Corp., 3. Trust Tech Corp.)

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

Oral presentation

[2M01-06] LWR performance duirng an accident

Tue. Mar 28, 2017 9:35 AM - 11:10 AM Room M (16-504 Building No.16)

Chair: Hidemasa Yamano (JAEA)

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9:35 AM - 9:50 AM

[2M01] Severe accidents analyses of LWR plant behavior with simulator of RELAP/SCDAPSIM code and graphical interface.

(3)Analysis of BWR plant at BOC/EOC of equilibrium core.

*Daiki Nunokawa¹, Mituyo Tuji¹, Takanori Kameyama² (1. Graduate School of TOKAI Univ., 2. TOKAI Univ.)

9:50 AM - 10:05 AM

[2M02] Severe accidents analyses of LWR plant behavior with simulator of RELAP/SCDAPSIM code and graphical interface.

(4)Analysis of PWR plant at BOC/EOC of equilibrium core

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

10:05 AM - 10:20 AM

[2M03] Thermal-dydraulic Analysis of BWR Containment Response to Accidents Using the GOTHIC Therrmal Hydraulic Analysis Package

(2)Loss of pressure suppression capability in S/P

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

10:20 AM - 10:35 AM

[2M04] Loss of Cooling System and Loss of Coolant Accident Progression Analysis for Spent Fuel Pools

Experimental Analysis for Oxidation of Spent Fuel Assemblies using Mockup Fuel Bundles

*Retsu Kojo¹, Akitoshi Hotta¹ (1. Nuclear Regulation Authority)

10:35 AM - 10:50 AM

[2M05] Development of Desktop Plant Simulator to Treat Simultaneous Accident Progress in Reactor and SFP

(1)Overall Scope of the Project

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

10:50 AM - 11:05 AM

[2M06] Study on the plant behavior and success criteria for typical PWR during multiple pipe rupture

*Tatsuya Patrick Kunishi¹, Hitoshi Muta¹, Ken Muramatu¹ (1. Tokyo City university graduate school of engineering cooperative major in nuclear energy)

Time reserved for Chair （11:05 AM - 11:10 AM）

Oral presentation

[2M07-09] Safety Evaluation on LWR

Tue. Mar 28, 2017 11:10 AM - 12:00 PM Room M (16-504 Building No.16)

Chair: Koichi Nakamura (CRIEPI)

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11:10 AM - 11:25 AM

[2M07] 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, Hirohide Oikawa², Kazutoshi Eto⁵ (1. Japan Nuclear Safety Institute , 2. Toshiba, 3. MHI, 4. Hitachi-GE, 5. Kyushu Electric Power Company)

11:25 AM - 11:40 AM

[2M08] Development of Refractory Material Erosion Model for Debris Cooling Equipment

Erosion Evaluation of Refractory Material Based on a Thermo-Chemical Reaction Model

*Shinji Matsushita¹, Masafumi Nojima¹, Masataka Hidaka¹, Tadashi Fujii², Takeshi Sakai² (1. Hitachi, 2. Hitachi-GE)

11:40 AM - 11:55 AM

[2M09] Study on Material Properties of Concrete Exposed to Extremely High Temperature and Its Non-Destructive Evaluation

*Yuma Sato¹, Dung Thi-Mai Do¹, Masahide Suzuki¹, Tomonori Yamada² (1. Nagaoka University of Technology, 2. Japan Atomic Energy Agency)

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

Oral presentation

[2M10-14] Safety Evaluation on Fast Reactor 1

Tue. Mar 28, 2017 2:45 PM - 4:05 PM Room M (16-504 Building No.16)

Chair: Yoshitaka Fukano (JAEA)

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2:45 PM - 3:00 PM

[2M10] Fundamental Study on Sloshing Behavior of Disrupted Core Pool

Effects of Movement Characteristics on the Reactivity Insertion (3)

*Masayuki Fukuda¹, Sho Fuchita¹, Tatsuya Matsumoto¹, Koji Morita¹, Isao Tatewaki¹ (1. Kyushu Univ.)

3:00 PM - 3:15 PM

[2M11] Study on Safety Improvement of the Fast Reactor Focusing on Sodium Chemistry

(1)Outline and Test Results of Combustion/Corrosion Inhibition (Part 1)

*Tomohiro Furukawa¹, Toshihide Takai¹, Yasushi Hirakawa¹, Akikazu Kurihara¹, Junichi Saito¹ (1. JAEA)

3:15 PM - 3:30 PM

[2M12] Study on Safety Improvement of the Fast Reactor Focusing on Sodium Chemistry

(2)Test Results of Combustion/Corrosion Inhibition (Part 2)

*Toshihide Takai¹, Yasushi Hirakawa¹, Akikazu Kurihara¹, Junichi Saito¹, Tomohiro Furukawa¹ (1. JAEA)

3:30 PM - 3:45 PM

[2M13] Analysis on the initiating phase of ATWS events for Gen-IV loop-type SFR with SAS4A

*Ryuzaburo Kubota¹, Kazuya Koyama², Hiroyuki Moriwaki², Yumi Yamada², Yoshio Shimakawa², Tohru Suzuki¹, Kenichi Kawada¹, Shigenobu Kubo¹, Hidemasa Yamano¹ (1. JAEA, 2. MFBR)

3:45 PM - 4:00 PM

[2M14] Analysis of CABRI-1 AH3 Experiment using by Integrated Core Disruptive Accident Analysis Code, ASTERIA-FBR

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

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

Oral presentation

[2M15-18] Safety Evaluation on Fast Reactor 2

Tue. Mar 28, 2017 4:05 PM - 5:10 PM Room M (16-504 Building No.16)

Chair: Hiroshi Endo (CRIEPI)

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4:05 PM - 4:20 PM

[2M15] Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor

(14)Self-terminating behavior of sodium-concrete reaction

*Munemichi Kawaguchi^1,2, Shinya Miyahara^1,2, Masayoshi Uno² (1. JAEA, 2. Fukui Univ.)

4:20 PM - 4:35 PM

[2M16] Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor

(15)Multi-dimensional sodium fire analysis of an upward spray experiment

*Mitsuhiro Aoyagi¹, Takashi Takata¹, Shuji Ohno¹, Masayoshi Uno² (1. JAEA, 2. University of Fukui)

4:35 PM - 4:50 PM

[2M17] Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor

(16)Ignition study on various gas concentration of hydrogen jet containing sodium vapor/mist

*Daisuke Doi^1,2, Kei Ito¹, Hiroshi Seino¹, Shinya Miyahara², Masayoshi Uno² (1. JAEA, 2. Fukui Univ.)

4:50 PM - 5:05 PM

[2M18] Availability evaluation of passive reactor shut-down system in partial load operating conditions of the next generation sodium-cooled fast reactor

*HIROYUKI SAITO¹, YUMI YAMADA¹, KAZUHIRO OYAMA¹, SHOKO MATSUNAGA¹, SHIGENOBU KUBO², HIDEMASA YAMANO² (1. MFBR, 2. JAEA)

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

Oral presentation

[2M19-23] Safety Evaluation on Fast Reactor 3

Tue. Mar 28, 2017 5:10 PM - 6:30 PM Room M (16-504 Building No.16)

Chair: Koji Morita (Kyushu Univ.)

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5:10 PM - 5:25 PM

[2M19] Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor

(1)Prevention criteria proposal of significant core damage and their approach

*Masahiro Nishimura¹, Yoshitaka Fukano¹, Yuichi Onoda¹, Fumiaki Yamada¹ (1. JAEA)

5:25 PM - 5:40 PM

[2M20] Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor

(2)Bases of criteria on fuel

*Yoshitaka Fukano¹, Masahiro Nishimura¹, Yuichi Onoda¹, Fumiaki Yamada¹ (1. JAEA)

5:40 PM - 5:55 PM

[2M21] Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor

(3)Proposal of an assumed leak size in piping under the LORL event

*Hiroki Yada¹, Masanori Ando¹, Takashi Wakai¹ (1. JAEA)

5:55 PM - 6:10 PM

[2M22] Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor

(4)Calculation program on RV sodium level for LORL event

*Fumiaki YAMADA¹, Mitsuhiro ARIKAWA² (1. JAEA, 2. NESI)

6:10 PM - 6:25 PM

[2M23] Study on Effectiveness Evaluations of Countermeasures against Severe Accidents in Fast Reactor

(5)Validation of Reactor Analytical Model for PLOHS events

*Takero Mori¹, Hiroaki Ohira¹, Masutake Sotsu¹, Yoshitaka Fukano¹ (1. JAEA)

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

Oral presentation

[3M01-05] Fault Displacement

Wed. Mar 29, 2017 9:30 AM - 10:45 AM Room M (16-504 Building No.16)

Chair: Akemi Nishida (JAEA)

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9:30 AM - 9:45 AM

[3M01] The Basic Approach of Nuclear Safety for Fault Displacement

*Masanobu Kamiya¹ (1. JAPC)

9:45 AM - 10:00 AM

[3M02] The analysis evaluation of equipment and piping system for fault displacement

(1)The analysis evaluation of equipment

*kunihiko sato¹, ryusuke haraguchi², masanobu kamiya³, tsutomu ogawa³, kouichi kamiya³ (1. MHI NUCLEAR SYSTEMS AND SOLUTION ENGINEERING CO.,LTD., 2. Mitsubishi Heavy Industries, 3. The Japan Atomic Power Company)

10:00 AM - 10:15 AM

[3M03] The analysis evaluation of equipment and piping system for fault displacement

(2)The analysis evaluation of piping system

*satoshi shinma¹, takahiro umemoto¹, masanobu kamiya², tsutomu ogawa², kouichi kamiya² (1. Mitsubishi Heavy Industries, LTD., 2. The Japan Atomic Power Conpany)

10:15 AM - 10:30 AM

[3M04] Utilization of fragility evaluation method on fault displacement PRA

(1)Concept

*katsumi ebisawa¹, hideaki tsutsumi¹, Yoshinori Mihara² (1. central research institute of electric power industry, 2. Kajima Corporation)

10:30 AM - 10:45 AM

[3M05] Utilization of fragility evaluation method on fault displacement PRA

(2)Evaluation Example regarding Influence of Fault Displacement on Sea Water Channel

*hideaki tsutsumi¹, katsumi ebisawa¹, Tomoyasu Hamada², Yoshinori Mihara² (1. central research institute of electric power industry, 2. Kajima Corporation)

Oral presentation

[3M06-10] Statistical Safety Evaluation

Wed. Mar 29, 2017 10:45 AM - 12:00 PM Room M (16-504 Building No.16)

Chair: Takanori Kitada (Osaka Univ.)

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10:45 AM - 11:00 AM

[3M06] Analysis of In-Vessel Retention for AP1000^TM using Risk-Oriented Accident Analysis Methodology

*Satoshi Tsuda¹, Hisaki Sato¹, Yoshio Kawano¹, Yukitaka Yamazaki², Yasunobu Fujiki¹ (1. TOSHIBA, 2. Westinghouse Electric Japan)

11:00 AM - 11:15 AM

[3M07] Study on uncertainty propagation due to nuclear analysis codes on statistical safety evaluation method

(1)Overall Plan

*Kenichi Harada¹, Hirohisa Kaneko², Takamasa Miyaji³, Taichi Takii⁴, Akira Mototani⁵ (1. Chubu Electric Power Co., 2. GNF-J, 3. NFI, 4. HGNE, 5. Toshiba)

11:15 AM - 11:30 AM

[3M08] Study on uncertainty propagation due to nuclear analysis codes on statistical safety evaluation method

(2)Influence of nuclear data covariance to static analysis

*Teppei Yamana¹, Tadashi Ikehara¹, Hirohisa Kaneko¹, Masayuki Tojo¹, Kenichi Harada² (1. GNF-J, 2. Chubu Electric Power Co.)

11:30 AM - 11:45 AM

[3M09] Study on uncertainty propagation due to nuclear analysis codes on statistical safety evaluation method

(3)Influence of nuclear data covariance to transient analysis

*Yu Jinguji¹, Takeshi Yamada¹, Kenjiro Yamamoto², Teppei Yamana², Kenichi Harada³ (1. Hitachi-GE, 2. GNF-J, 3. Chubu Electric Power Co.)

11:45 AM - 12:00 PM

[3M10] Study on uncertainty propagation due to nuclear analysis codes on statistical safety evaluation method

(4)Influence of manufacturing tolerance to static and transient analyses

*Takamasa Miyaji¹, Ryosuke Nakamura¹, Mikio Tokashiki¹, Kenichi Harada² (1. NFI, 2. cepco)

Oral presentation

[3M11-16] Probabilistic Risk Assessment

Wed. Mar 29, 2017 2:45 PM - 4:20 PM Room M (16-504 Building No.16)

Chair: Yasushi Okano (JAEA)

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2:45 PM - 3:00 PM

[3M11] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(3)Project Overview and Progress

*Hiroyuki Sato¹, Akemi Nishida¹, Ken Muramatsu², Hitoshi Muta², 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)

3:00 PM - 3:15 PM

[3M12] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(4)Development of Event Tree Construction and Quantification Method for Accident Sequences Involving Multiple Piping Ruptures in Seismic PRA

*Kosuke Matsuda¹, Ken Muramatsu¹, Hitoshi Muta¹, Hiroyuki Sato², Akemi Nishida², Tatsuya Itoi³ (1. Tokyo City Uiversity Graduate Division, 2. JAEA, 3. Tokyo University)

3:15 PM - 3:30 PM

[3M13] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(5)Development of Seismic Fragility Analysis Method

*Tatsuya Itoi¹, Tsuyoshi Takada¹, Akemi Nishida², Ryohei Tanaka¹, Takenori Hida¹ (1. The University of Tokyo, 2. Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[3M14] Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors

(6)Development of Source Term Evaluation Method

*Yuki Honda¹, Hiroyuki Sato¹, Yosuke Shimazaki¹, Shigeaki Nakagawa¹, Hirofumi Ohashi¹ (1. Japan Atomic Anergy Agency)

3:45 PM - 4:00 PM

[3M15] Study on Evaluation Method of Internal Flooding Scenario Considering Time Uncertainty

*Shohei Nakai¹, Satoshi Takeda¹, Takanori Kitada¹ (1. Osaka University )

4:00 PM - 4:15 PM

[3M16] The Progress of PRA for SHIKA NPS unit2

(1)PRA evaluation results of SHIKA NPS unit2 during Power Operation(Level1)

*Kazuhiro Sugihara², Mutsuhiro Nakata¹, Toshihiro Aida¹, Daisuke Suimon¹, Shinichi Hamatani¹, Hiroto Matsumoto², Takuma Takahashi², Takayuki Negishi² (1. Hokuriku Electric Power Co., 2. Nuclear Engineering and Services Co.)

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

Sessions

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

[1M01-04] Fukushima Daiichi Nuclear Power Plant Accident

Observation of operation manual at accident

[1M05-07] Reprocessing Plant

(9)Hydrogen explosion experiment of simulated two large cylindrical vessels connected via vessel off gas ventilation system

(10)Combustion analysis and structural analysis of simulated two large cylindrical vessels connected via vessel off gas ventilation system

(11)Comparison with numerical analysis and experiment of simulated two large cylindrical vessels connected via vessel off gas ventilation system

[1M08-11] External Hazard Including Security Issue

Identification of Hazard Combinations in terms of Impacts on SFR Decay Heat Removal System with Final Heat Sink of Ambient Air

(19)Margin Assessment Methodology against a Combination Hazard of Strong Wind and Rainfall

(1)Problem extraction for 2S interface

(2)Vital Area Identification (VAI) and response to severe accident initiated by security incident

[1M12-18] Evaluation of Source Term and Radiation Dose

(9)Research on the applicability of PRD method to Containment functional failure frequency due to the severe accident

(10)Research on the applicability of PRD method to cesium release behavior due to the severe accident

Research on the effectivity of measures for prevention containment vessel failure due to the sever accident

Investigation of source term risk assessment using Artificial Intelligence (AI)

(13)Quantification method of the source term event tree (STET)

[2M01-06] LWR performance duirng an accident

(3)Analysis of BWR plant at BOC/EOC of equilibrium core.

(4)Analysis of PWR plant at BOC/EOC of equilibrium core

(2)Loss of pressure suppression capability in S/P

Experimental Analysis for Oxidation of Spent Fuel Assemblies using Mockup Fuel Bundles

(1)Overall Scope of the Project

[2M07-09] Safety Evaluation on LWR

Erosion Evaluation of Refractory Material Based on a Thermo-Chemical Reaction Model

[2M10-14] Safety Evaluation on Fast Reactor 1

Effects of Movement Characteristics on the Reactivity Insertion (3)

(1)Outline and Test Results of Combustion/Corrosion Inhibition (Part 1)

(2)Test Results of Combustion/Corrosion Inhibition (Part 2)

[2M15-18] Safety Evaluation on Fast Reactor 2

(14)Self-terminating behavior of sodium-concrete reaction

(15)Multi-dimensional sodium fire analysis of an upward spray experiment

(16)Ignition study on various gas concentration of hydrogen jet containing sodium vapor/mist

[2M19-23] Safety Evaluation on Fast Reactor 3

(1)Prevention criteria proposal of significant core damage and their approach

(2)Bases of criteria on fuel

(3)Proposal of an assumed leak size in piping under the LORL event

(4)Calculation program on RV sodium level for LORL event

(5)Validation of Reactor Analytical Model for PLOHS events

[3M01-05] Fault Displacement

(1)The analysis evaluation of equipment

(2)The analysis evaluation of piping system

(1)Concept

(2)Evaluation Example regarding Influence of Fault Displacement on Sea Water Channel

[3M06-10] Statistical Safety Evaluation

(1)Overall Plan

(2)Influence of nuclear data covariance to static analysis

(3)Influence of nuclear data covariance to transient analysis

(4)Influence of manufacturing tolerance to static and transient analyses

[3M11-16] Probabilistic Risk Assessment

(3)Project Overview and Progress

(4)Development of Event Tree Construction and Quantification Method for Accident Sequences Involving Multiple Piping Ruptures in Seismic PRA

(5)Development of Seismic Fragility Analysis Method

(6)Development of Source Term Evaluation Method

(1)PRA evaluation results of SHIKA NPS unit2 during Power Operation(Level1)

Authentication