Oral presentation

[1D01-07] PRA Method 1

Tue. Mar 26, 2024 10:00 AM - 11:55 AM Room D (21Bildg.3F 21-312)

Chair:Takuro Toubou(TOSHIBA ESS)

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10:00 AM - 10:15 AM

[1D01] Development of Probabilistic Risk Assessment Methodology Using Artificial Intelligence Technology

(2) Application of Automatic Tools to Component Level Fault Tree Creation

*Satoshi FUTAGAMI¹, Kenichi KURISAKA¹, Hidemasa YAMANO¹, Hiroshi UJITA² (1. JAEA, 2. AdvanceSoft Corporation)

10:15 AM - 10:30 AM

[1D02] Development of Probabilistic Risk Assessment Methodology Using Artificial Intelligence Technology

(3) Application of Automatic Failure Detection Methodology to Preliminary Analysis for Reliability Database Construction

*Hiroshi UJITA¹, Tatsuya Morimoto¹, Satoshi FUTAGAMI², Hidemasa YAMANO², Kenichi KURISAKA² (1. AdvanceSoft Corporation, 2. Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[1D03] Risk assessment of hydrogen venting scenarios considering the emergency action level transmission timing

*Nobuhito Shiomura¹, Fumie Sebe¹, Nobuhisa Takezawa¹, Hideki Horie¹, Kaoru Matsushita¹, Mika Tahara¹ (1. TOSHIBA ESS)

10:45 AM - 11:00 AM

[1D04] Development of evaluation methods for simplified evaluation of emergency response

(3)Comprehensive study of metrics use in simplified exposure assessment method

*Kodai Wadayama¹, Retsu Kojo¹ (1. NRA)

11:00 AM - 11:15 AM

[1D05] Development of evaluation methods for simplified evaluation of emergency response

(4)Analysis of Core Release Fractions

*Retsu KOJO¹, Kodai WADAYAMA¹ (1. Nuclear Regulation Authority)

11:15 AM - 11:30 AM

[1D06] Application of dynamic PRA to nuclear power plant operation support

(1) Evaluation of plant operation support using a simple plant model

*Nami Yamamoto¹, Mami Kagimoto¹, Mitsunobu Yoshinaga¹, Yohei Ueno¹, Takafumi Narukawa², Takashi Takata² (1. Mitsubishi Electric, 2. UTokyo)

11:30 AM - 11:45 AM

[1D07] On "societal risks" and safety goals

*Shin-etsu Sugawara¹ (1. Kansai Univ.)

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

Oral presentation

[1D08-12] External Event PRA 1

Tue. Mar 26, 2024 2:45 PM - 4:10 PM Room D (21Bildg.3F 21-312)

Chair:Hitoshi Muta(TCU)

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2:45 PM - 3:00 PM

[1D08] Probabilistic Risk Assessment of Sodium-cooled Fast Reactors by CMMC Method Considering the Recognition Probability on External Hazards

*Akari Koike¹, Takaaki Sakai¹, Norihiro Doda², Masaaki Tanaka² (1. Tokai Univ., 2. JAEA)

3:00 PM - 3:15 PM

[1D09] Study on the improved fragility evaluation method of electrical raceways

(2) Capacity test and improved fragility evaluation method

*Tomokazu Higuchi¹, Tatsuya Oku¹, Kazuya Masuda¹, Naotomo Maruyama², Shinji Kosugi³, Ryusuke Haraguchi⁴, Masatsugu Bando⁵, Shinichi Hisatomi⁶, Ryotaro Tatsuzawa⁶, Kento Furuya⁶ (1. TOSHIBA ESS, 2. HGNE, 3. Hitachi, 4. MHI, 5. MHI NS Engineering, 6. TEPCO HD)

3:15 PM - 3:30 PM

[1D10] Quantification of Uncertainties in Seismic Fragility Evaluation of Equipment and Civil Structures Considering Ageing Deterioration (Part1)

*Ayumi Yuyama¹, Yohei Ninomiya¹, Masato Nakajima¹ (1. CRIEPI)

3:30 PM - 3:45 PM

[1D11] Strike probability evaluation of tornado missile considering arrangement of target

*Takahiro Murakami¹, Kota Fujiwara¹, Yuzuru Eguchi¹, Yasuo Hattori¹ (1. CRIEPI)

3:45 PM - 4:00 PM

[1D12] An evaluation method of annual strike probability of typhoon-borne missiles toward typhoon PRA

*YUZURU EGUCHI¹, MITSUHARU NOMURA¹, YASUO HATTORI¹, TAKAHIRO MURAKAMI¹ (1. CRIEPI)

Time reserved for Chair （4:00 PM - 4:10 PM）

Oral presentation

[1D13-17] External Event PRA 2

Tue. Mar 26, 2024 4:10 PM - 5:30 PM Room D (21Bildg.3F 21-312)

Chair:Tomokazu Higuchi(TOSHIBA ESS)

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4:10 PM - 4:25 PM

[1D13] Research on Seismic Correlation on PRA

Part5 Influence of building and component non-linearities on the response correlation between components

*Masahiro Ourai¹, Yasuki Ohtori¹, Hitoshi Muta¹, Masato Nakajima² (1. TCU, 2. CRIEPI)

4:25 PM - 4:40 PM

[1D14] Evaluation of Seismic Diversity of SSC system in PRA

Part7 : A study on the effectiveness of floor isolation considering seismic diversity using various strong motion records

*Katayama Yoshifumi¹, Yasuki Ohtori², Hitoshi Muta², Toshiaki Sakai³ (1. Chuden Engineering Consultants, 2. TCU, 3. CRIEPI)

4:40 PM - 4:55 PM

[1D15] The importance of correlation considerations in seismic risk accident sequence assessment

*Hitoshi Muta¹, Yasuki Ohtori¹ (1. Tokyo City University)

4:55 PM - 5:10 PM

[1D16] Development of AI surrogate models for seismic risk assessment

(1) Proposal of AI surrogate model

*Ryoto Kobayashi¹, Yasuki Ohtori¹, Hitoshi muta¹ (1. TCU)

5:10 PM - 5:25 PM

[1D17] Research on seismic risk assessment of large-scale and complex systems using quantum computers

(2)Application for small-scale FT model

*Shota Terayama¹, Yasuki Ohtori¹, Hitoshi Muta¹ (1. TCU)

Time reserved for Chair （5:25 PM - 5:30 PM）

Oral presentation

[2D01-08] PRA Method 2

Wed. Mar 27, 2024 9:45 AM - 11:55 AM Room D (21Bildg.3F 21-312)

Chair:Seung hyun Jang(Hokkaido Univ.)

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9:45 AM - 10:00 AM

[2D01] Proposal to use a DQFM result to set a truncation value for minimal cutsets

*SHOTA SOGA¹, Eishiro Higo¹, Hiromichi Miura¹ (1. CRIEPI)

10:00 AM - 10:15 AM

[2D02] Analysis of Accident Scenarios for Simplified PRA at NSRR

*Yuiko Motome¹, Hitoshi Tamaki¹, Masaki Amaya¹, Taisuke Yonomoto¹ (1. JAEA)

10:15 AM - 10:30 AM

[2D03] Comparison of computation time required to generate MCS for PRA tools (CAFTA)

*Yosuke Atake¹ (1. CRIEPI)

10:30 AM - 10:45 AM

[2D04] Study on Probabilistic Approach for Best Estimate of Fuel Rod Fracture

*Hiroki Tanaka¹, Takafumi Narukawa¹, Takashi Takata¹ (1. UTokyo)

10:45 AM - 11:00 AM

[2D05] Study on Simple Importance Evaluation Method of Installed Equipment Using Structural Importance for Nuclear Fuel Reprocessing and Fabrication Facilities

(1) Overview of the Study of the Simple Importance Evaluation Method

*Kenji MORI¹, Muneyuki YOKOTSUKA¹, Toshio TERAGAKI¹ (1. NRA)

11:00 AM - 11:15 AM

[2D06] Study on Simple Importance Evaluation Method of Installed Equipment Using Structural Importance for Nuclear Fuel Reprocessing and Fabrication Facilities

(2)Trial Analysis Using Simple Importance Evaluation Method

*Muneyuki YOKOTSUKA¹, Kenji MORI¹, Toshio TERAGAKI¹ (1. NRA)

11:15 AM - 11:30 AM

[2D07] Development of Probabilistic Risk Assessment Methods for multiple tanks and multiple events at the Rokkasho Reprocessing Plant

(1)Policy and Plan

*Kazumi Takebe¹, Masahiro Yamamoto^1,4, Takashi Kodama¹, Futoshi Tanaka², Asei Kawasaki³, Isao Hongo², Makoto Takahashi⁴ (1. JNFL, 2. MHI, 3. MHI NSE, 4. Tohoku Univ.)

11:30 AM - 11:45 AM

[2D08] Development of Probabilistic Risk Assessment Methods for multiple tanks and multiple events at the Rokkasho Reprocessing Plant

(2)Feasibility study of the method to assess reprocessing facility risk (Case Study of 2 tanks)

*Masahiro Yamamoto^1,4, Kazumi Takebe¹, Takashi Kodama¹, Futoshi Tanaka², Asei Kawasaki³, Isao Hongo², Makoto Takahashi⁴ (1. JNFL, 2. MHI, 3. MHI NSE, 4. Tohoku Univ.)

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

Sessions

IV. Nuclear Plant Technologies » 403-1 Risk Assessment Technology, Application of Risk Information

[1D01-07] PRA Method 1

(2) Application of Automatic Tools to Component Level Fault Tree Creation

(3) Application of Automatic Failure Detection Methodology to Preliminary Analysis for Reliability Database Construction

(3)Comprehensive study of metrics use in simplified exposure assessment method

(4)Analysis of Core Release Fractions

(1) Evaluation of plant operation support using a simple plant model

[1D08-12] External Event PRA 1

(2) Capacity test and improved fragility evaluation method

[1D13-17] External Event PRA 2

Part5 Influence of building and component non-linearities on the response correlation between components

Part7 : A study on the effectiveness of floor isolation considering seismic diversity using various strong motion records

(1) Proposal of AI surrogate model

(2)Application for small-scale FT model

[2D01-08] PRA Method 2

(1) Overview of the Study of the Simple Importance Evaluation Method

(2)Trial Analysis Using Simple Importance Evaluation Method

(1)Policy and Plan

(2)Feasibility study of the method to assess reprocessing facility risk (Case Study of 2 tanks)

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