Oral presentation

[2F01-04] Tool Development for Safety Assessment

Thu. Mar 18, 2021 9:30 AM - 10:45 AM Room F (Zoom room 6)

Chair: Chiaki Kino (IAE)

9:30 AM - 9:45 AM

[2F01] Development of internal flooding propagation analysis system

(1)Summary of internal flooding propagation analysis system

*Takashi Takeuchi¹, Ken Nosaka¹, Naoki Takahashi¹, Mingxi Wei², Hiroyuki Fujita², Daisuke Fujiwara², Tooru Shimano² (1. TEPCO HD, 2. TEPSYS)

9:45 AM - 10:00 AM

[2F02] Development of internal flooding propagation analysis system

(2)Internal flooding propagation analysis tool

*Tooru Shimano¹, Mingxi Wei¹, Hiroyuki Fujita¹, Daisuke Fujiwara¹, Takashi Takeuchi², Ken Nosaka², Naoki Takahashi² (1. TEPCO SYSTEMS CORPORATION, 2. Tokyo Electric Power Company Holdings, Inc.)

10:00 AM - 10:15 AM

[2F03] Development of Internal Flooding Propagation Analysis System

(3)High Temperature Steam Propagation Analysis Function

*Mingxi Wei¹, Hiroyuki Fujita¹, Daisuke Fujiwara¹, Tooru Shimano¹, Takashi Takeuchi², Ken Nosaka², Naoki Takahashi² (1. TEPCO SYSTEMS CORPORATION, 2. TOKYO ELECTRIC POWER COMPANY Holdings Inc.)

10:15 AM - 10:30 AM

[2F04] Development of the automation tool for wildfire evaluation with FARSITE

(1)Development of functions for FARSITE to create input files and post-process output files

*Kota Tominaga¹, Daisuke Fujiwara¹, Hisayuki Kyou¹, Ryunosuke Yamaguchi¹ (1. TEPSYS)

Time reserved for Chair （10:30 AM - 10:45 AM）

Oral presentation

[2F05-08] Safety Measures

Thu. Mar 18, 2021 10:45 AM - 12:00 PM Room F (Zoom room 6)

Chair: Satoshi Takeda (Osaka Univ.)

10:45 AM - 11:00 AM

[2F05] Risk of Japanese PWR Plants by shutting off forced core cooling at an accident

Comparison of reactor coolant pumps stop method on receiving of SI actuation signals in Japan, the US and Europe

*Yoshitaka Yoshida¹ (1. Research Institute of Nuclear Engineering, University of Fukui)

11:00 AM - 11:15 AM

[2F06] Development of a Filter Venting System to Reduce Exposure Dose from Radioactive Noble Gases

(1)Overview of the System

*Kazuaki Kito¹, Taichi Takii¹, Kazuo Tominaga¹, Takahisa Matsuzaki¹, Tasuku Yano¹ (1. HGNE)

11:15 AM - 11:30 AM

[2F07] Development of a Filter Venting System to Reduce Exposure Dose from Radioactive Noble Gases

(2)Filter Selection and Evaluation of Dose Reduction Effect

*Takahisa Matsuzaki¹, Katsuki Hamada², Naoyuki Ishida¹, Naohisa Watahiki², Kazuo Tominaga¹, Kazuaki Kito¹ (1. HGNE, 2. Hitachi)

11:30 AM - 11:45 AM

[2F08] Development of a Filter Venting System to Reduce Exposure Dose from Radioactive Noble Gases

(3)Lifetime Prediction of Filter Material with Molecular Simulation

Tasuku Yano¹, Takahisa Matsuzaki¹, Kazuaki Kito¹, *Kazuo Tominaga¹ (1. HGNE)

Time reserved for Chair （11:45 AM - 12:00 PM）

Oral presentation

[2F09-12] Safety Analysis

Thu. Mar 18, 2021 2:45 PM - 4:00 PM Room F (Zoom room 6)

Chair: Yoshiro Nishioka (Toshiba ESS)

2:45 PM - 3:00 PM

[2F09] Numerical Analysis of melt spreading behavior by MELTSPREAD code

(3)Crust Formation versus Bulk Freezing

*Kazuyuki Katsuragi¹, Hiroshi Goda¹, Naoya Hayashi¹, Kenichiro Ueda¹ (1. MHI)

3:00 PM - 3:15 PM

[2F10] Study on discharge behavior of molten core materials in core on core disruptive accidents of sodium cooled fast reactors

Consideration on discharge behavior through a sodium-filled channel with an internal structure

*Shinya Kato¹, Kenichi Matsuba¹, Kenji Kamiyama¹, Anatoly Mikisha², Assan Akayev², Alexandr Vurim², Viktor Baklanov² (1. JAEA, 2. NNC)

3:15 PM - 3:30 PM

[2F11] Severe accidents analyses of LWR plant behavior with simulator of RELAP/SCDAPSIM code and graphical interface.

(5)Damage level analysis of BWR core at station blackout.

*Yuji kato¹, Takanori Kameyama¹ (1. Tokai Univ.)

3:30 PM - 3:45 PM

[2F12] Numerical analysis for explosion phenomena of High Energy Arcing Faults (HEAF)

(1)Discussion on pressure rise evaluation model of electrical cabinet by AUTODYN

*Kosuke MATSUDA¹, Fumio KASAHARA¹, Hajime KABASHIMA¹, Toshiyuki MIYAZAKI² (1. Nuclear Regulation Authority, 2. AdvanceSoft Corporation)

Time reserved for Chair （3:45 PM - 4:00 PM）

Sessions

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

[2F01-04] Tool Development for Safety Assessment

[2F01] Development of internal flooding propagation analysis system

(1)Summary of internal flooding propagation analysis system

[2F02] Development of internal flooding propagation analysis system

(2)Internal flooding propagation analysis tool

[2F03] Development of Internal Flooding Propagation Analysis System

(3)High Temperature Steam Propagation Analysis Function

[2F04] Development of the automation tool for wildfire evaluation with FARSITE

(1)Development of functions for FARSITE to create input files and post-process output files

[2F05-08] Safety Measures

[2F05] Risk of Japanese PWR Plants by shutting off forced core cooling at an accident

Comparison of reactor coolant pumps stop method on receiving of SI actuation signals in Japan, the US and Europe

[2F06] Development of a Filter Venting System to Reduce Exposure Dose from Radioactive Noble Gases

(1)Overview of the System

[2F07] Development of a Filter Venting System to Reduce Exposure Dose from Radioactive Noble Gases

(2)Filter Selection and Evaluation of Dose Reduction Effect

[2F08] Development of a Filter Venting System to Reduce Exposure Dose from Radioactive Noble Gases

(3)Lifetime Prediction of Filter Material with Molecular Simulation

[2F09-12] Safety Analysis

[2F09] Numerical Analysis of melt spreading behavior by MELTSPREAD code

(3)Crust Formation versus Bulk Freezing

[2F10] Study on discharge behavior of molten core materials in core on core disruptive accidents of sodium cooled fast reactors

Consideration on discharge behavior through a sodium-filled channel with an internal structure

[2F11] Severe accidents analyses of LWR plant behavior with simulator of RELAP/SCDAPSIM code and graphical interface.

(5)Damage level analysis of BWR core at station blackout.

[2F12] Numerical analysis for explosion phenomena of High Energy Arcing Faults (HEAF)

(1)Discussion on pressure rise evaluation model of electrical cabinet by AUTODYN

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