Search for presentations

7 results (1 - 7)

Tue. Mar 26, 2024 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)

[1D01-07] PRA Method 1

Oral presentation
｜ IV. Nuclear Plant Technologies
| 403-1 Risk Assessment Technology, Application of Risk Information

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

Chair:Takuro Toubou(TOSHIBA ESS)

Tue. Mar 26, 2024 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)

[1D01-07] PRA Method 1

Oral presentation
｜ IV. Nuclear Plant Technologies
| 403-1 Risk Assessment Technology, Application of Risk Information

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

Chair:Takuro Toubou(TOSHIBA ESS)

[1D_PL02] Development of Probabilistic Risk Assessment Methodology Using Artificial Intelligence Technology

2. Automatic Fault Detection Method for Building Reliability Database

*Hiroshi Ujita¹ (1. Advance Soft)

[1D_PL] Cutting edge of application of AI technology to PRA

Planning Lecture
｜ Technical division and Network
| Risk Science and Technology Division

Tue. Mar 26, 2024 1:00 PM - 2:30 PM Room D (21Bildg.3F 21-312)

Chair:Masahiro Tatsumi(NEL)

Wed. Mar 27, 2024 3:15 PM - 3:30 PM

[2D11] Analyses of accident progression in domestic 4-loop PWR plant using MELCOR2.2

*Junichi Kaneko¹, Masami Taira¹, Wataru Kikuchi¹, Akitochi Hotta¹, Saoto Fukui², Masahiko Yamadi², Souichirou Tanimori² (1. NRA, 2. AdvanceSoft)

[2D09-12] Accident Analysis

Oral presentation
｜ IV. Nuclear Plant Technologies
| 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

Wed. Mar 27, 2024 2:45 PM - 3:50 PM Room D (21Bildg.3F 21-312)

Chair:Yuki Nakamura(TOSHIBA ESS)

Thu. Mar 28, 2024 11:05 AM - 11:20 AM

[3D06] Study of FP transport behavior through TeRRa-CsOH experimental analysis using FP behavior analysis code FIPRA

*Yoshihiro Morita¹, Masanori Naitoh¹ (1. AdvanceSoft)

[3D06-08] Behaviors of FP and Hydrogen

Oral presentation
｜ IV. Nuclear Plant Technologies
| 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

Thu. Mar 28, 2024 11:05 AM - 11:55 AM Room D (21Bildg.3F 21-312)

Chair:Junichi Kaneko(NRA)

Thu. Mar 28, 2024 2:45 PM - 3:00 PM

[3D09] Development of Reactor Building and Containment Vessel Thermo-Fluid Dynamics Code, Advance/BAROC

(9)Parametric Evaluation of Hydrogen Inflow Locations into Reactor Building on Overall Hydrogen Distribution

*Fumitomo Onishi¹, Achihiro Hamano¹, Toshiharu Mitsuhashi ¹, Atsuo Takahashi¹, Hirotaka Hadachi¹, Hideaki Koike¹, Masanori Naitoh¹ (1. AdvanceSoft)

[3D09-13] Methodology Development

Oral presentation
｜ IV. Nuclear Plant Technologies
| 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

Thu. Mar 28, 2024 2:45 PM - 4:05 PM Room D (21Bildg.3F 21-312)

Chair:SHIN KIKUCHI(JAEA)

Thu. Mar 28, 2024 3:00 PM - 3:15 PM

[3D10] Development of Reactor Building and Containment Vessel Thermo-Fluid Dynamics Code, Advance/BAROC

(10)Improvements and sample analysis to simulate transient behavior of FP aerosol leak through the shield plug

*Atsuo Takahashi¹, Toshiharu Mitsuhashi¹, Achihiro Hamano¹, Fumitomo Onishi¹, Hirotaka Hadachi¹, Koike Hideaki¹, Masanori Naitoh¹ (1. AdvanceSoft Corporation)

[3D09-13] Methodology Development

Oral presentation
｜ IV. Nuclear Plant Technologies
| 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

Thu. Mar 28, 2024 2:45 PM - 4:05 PM Room D (21Bildg.3F 21-312)

Chair:SHIN KIKUCHI(JAEA)

Search for presentations

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

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

[1D01-07] PRA Method 1

[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

[1D01-07] PRA Method 1

[1D_PL02] Development of Probabilistic Risk Assessment Methodology Using Artificial Intelligence Technology

2. Automatic Fault Detection Method for Building Reliability Database

[1D_PL] Cutting edge of application of AI technology to PRA

[2D11] Analyses of accident progression in domestic 4-loop PWR plant using MELCOR2.2

[2D09-12] Accident Analysis

[3D06] Study of FP transport behavior through TeRRa-CsOH experimental analysis using FP behavior analysis code FIPRA

[3D06-08] Behaviors of FP and Hydrogen

[3D09] Development of Reactor Building and Containment Vessel Thermo-Fluid Dynamics Code, Advance/BAROC

(9)Parametric Evaluation of Hydrogen Inflow Locations into Reactor Building on Overall Hydrogen Distribution

[3D09-13] Methodology Development

[3D10] Development of Reactor Building and Containment Vessel Thermo-Fluid Dynamics Code, Advance/BAROC

(10)Improvements and sample analysis to simulate transient behavior of FP aerosol leak through the shield plug

[3D09-13] Methodology Development

Narrow down the search

Category: