Oral presentation

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

[1J04-07] Analysis Technology 2

Wed. Sep 7, 2022 10:50 AM - 12:00 PM Room J (E1 Bildg.4F No.42)

Chair:Koji Morita(Kyushu Univ.)

10:50 AM - 11:05 AM

[1J04] Speedup by Parallel Processing in a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

*Atsuo Takahashi¹, Mamoru Shimizu¹, Fumitomo Onishi¹, Achihiro Hamano¹, Toshiharu Mitsuhashi¹, Hideaki Koike¹, Masanori Naitoh¹ (1. AdvanceSoft Corporation)

11:05 AM - 11:20 AM

[1J05] Effect of Turbulence on Hydrogen deflagration Behavior during SA of LWR

*Sei Yura¹, Kosuke Motegi², Tomoyuki Sugiyama², Kazuhiro Sawa¹ (1. Hokkaido Univ., 2. JAEA)

11:20 AM - 11:35 AM

[1J06] Plant incident progress scenario analysis for Mihama nuclear emergency exercise of Kansai Electric Power Co., Inc. 2021

*Ikuo Kawasaki¹, Toshiya Takaki¹, Yoshinori Yamamoto², Tsuyoshi Yamazaki², Hiroyuki Ikeda², Hajime Takebe² (1. INSS, 2. KEPCO)

11:35 AM - 11:50 AM

[1J07] Examination of Transient Reactor Analysis code Toshiba version (TRACT^TM) application for Loss-of-Coolant Accident analyses

*Fumie Sebe¹, Hideki Horie¹, Yutaka Takeuchi¹, Takanori Fukunaga¹ (1. Toshiba Energy Systems & Solutions Corporation)

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

Session information

[1J04-07] Analysis Technology 2

[1J04] Speedup by Parallel Processing in a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

[1J05] Effect of Turbulence on Hydrogen deflagration Behavior during SA of LWR

[1J06] Plant incident progress scenario analysis for Mihama nuclear emergency exercise of Kansai Electric Power Co., Inc. 2021

[1J07] Examination of Transient Reactor Analysis code Toshiba version (TRACT^TM) application for Loss-of-Coolant Accident analyses

Authentication

Session information

[1J04-07] Analysis Technology 2

[1J04] Speedup by Parallel Processing in a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

[1J05] Effect of Turbulence on Hydrogen deflagration Behavior during SA of LWR

[1J06] Plant incident progress scenario analysis for Mihama nuclear emergency exercise of Kansai Electric Power Co., Inc. 2021

[1J07] Examination of Transient Reactor Analysis code Toshiba version (TRACTTM) application for Loss-of-Coolant Accident analyses

Authentication

[1J07] Examination of Transient Reactor Analysis code Toshiba version (TRACT^TM) application for Loss-of-Coolant Accident analyses