Oral presentation

[1G01-04] Fast Reactor Safety

Wed. Mar 16, 2022 9:30 AM - 10:45 AM Room G

Chair: Kenta Murakami (UTokyo)

9:30 AM - 9:45 AM

[1G01] Investigation of irradiation model in fast reactor safety analysis code SAS4A through CABRI experimental analyses

*Shinya Ishida¹, Yasushi Okano¹ (1. JAEA)

9:45 AM - 10:00 AM

[1G02] Thermodynamic stability of volatile radionuclides in cladding failure accident of sodium–cooled fast reactor

*Ikuo Yamamoto¹, Munemichi Kawaguchi¹, Shinya Miyahara¹, Masayoshi Uno¹ (1. University of Fukui)

10:00 AM - 10:15 AM

[1G03] Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors

(10)Analysis on fragmentation and cooling behavior in a limited volume sodium pool

*Hatsuki Matsushita¹, Ren Kobayashi¹, Takaaki Sakai¹, Shinya Kato², Ken-ichi Matsuba², Kenji Kamiyama² (1. Tokai Univ., 2. JAEA)

10:15 AM - 10:30 AM

[1G04] Super-Prompt Critical Transient Induced by Sloshing Motion of Molten Fuel Pool

*Satoshi Fujita¹, Tomoko Ishizu¹, Koji Morita² (1. NRA, 2. Kyushu Univ.)

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

Oral presentation

[1G05-08] Plant Safety

Wed. Mar 16, 2022 10:45 AM - 12:00 PM Room G

Chair: Kenichi Matsuba (JAEA)

10:45 AM - 11:00 AM

[1G05] Safety requirements for new NPPs in Japan and its feasibility (No.1: Background and Research Plan)

*Hiroshi Yamagata¹ (1. Nagaoka University of Technology)

11:00 AM - 11:15 AM

[1G06] Evaluation of Containment Structure Integrity to Fuel-Coolant Interaction

*Yoshiki Ihara¹, Nobuyuki Aono¹, Kenta Nishimon¹, Isamu Jinno¹, Ryo Fukuda², Hiroshi Goda², Hisashi Takahashi³ (1. YONDEN, 2. MHI, 3. MHI NSE)

11:15 AM - 11:30 AM

[1G07] Development of a Filter Venting System to Prevent Exposure to Radioactive Noble Gases

(4)Removal of radioactive noble gases by silica membrane with high durability

*Takahisa Matsuzaki¹, Naoyuki Ishida², Naohisa Watahiki², Kazuo Tominaga¹, Kazuaki Kito¹ (1. HGNE, 2. Hitachi)

11:30 AM - 11:45 AM

[1G08] The accident evaluation of JRR-3

*Shintaro Iguchi¹, Hironori Horiguchi¹, Masaaki Araki¹ (1. JAEA)

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

Oral presentation

[1G09-13] Severe Accident Analysis

Wed. Mar 16, 2022 2:45 PM - 4:15 PM Room G

Chair: Yoshiro Nishioka (Toshiba ESS)

2:45 PM - 3:00 PM

[1G09] Evaluation of accident management measures in Early-in-vessel phase in PWR by MAAP5.06

*Takumi Kitao¹ (1. NEL)

3:00 PM - 3:15 PM

[1G10] Numerical analysis of IVR code benchmark by MAAP5

(2)Heavy metal layer model

*Kazuyuki Katsuragi¹, Naoya Hayashi¹, Kenichiro Ueda¹, Noboru Matsui¹ (1. MHI)

3:15 PM - 3:30 PM

[1G11] Development of a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

(1)A Method of CFD Compressible Fluid Dynamics

*Toshiharu Mitsuhashi¹, Atsuo Takahashi¹, Fumitomo Onishi¹, Achihiro Hamano¹, Hirotaka Hadachi¹, Hideaki Koike¹, Masanori Naitoh¹ (1. AdvanceSoft Corporation)

3:30 PM - 3:45 PM

[1G12] Development of a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

(2)Distribution analysis of hydrogen concentration

*Fumitomo Onishi¹, Achihiro Hamano¹, Toshiharu Mitsuhashi¹, Atsuo Takahashi¹, Hirotaka Hadachi¹, Hideaki Koike¹, Masanori Naitoh¹ (1. AdvanceSoft Corporation)

3:45 PM - 4:00 PM

[1G13] Development of a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

(3)Cesium behavior analysis

*Atsuo Takahashi¹, Toshiharu Mitsuhashi¹, Fumitomo Onishi¹, Hirotaka Hadachi¹, Achihiro Hamano¹, Hideaki Koike¹, Masanori Naitoh¹ (1. AdvanceSoft)

Time reserved for Chair （4:00 PM - 4:15 PM）

Sessions

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

[1G01-04] Fast Reactor Safety

[1G01] Investigation of irradiation model in fast reactor safety analysis code SAS4A through CABRI experimental analyses

[1G02] Thermodynamic stability of volatile radionuclides in cladding failure accident of sodium–cooled fast reactor

[1G03] Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors

(10)Analysis on fragmentation and cooling behavior in a limited volume sodium pool

[1G04] Super-Prompt Critical Transient Induced by Sloshing Motion of Molten Fuel Pool

[1G05-08] Plant Safety

[1G05] Safety requirements for new NPPs in Japan and its feasibility (No.1: Background and Research Plan)

[1G06] Evaluation of Containment Structure Integrity to Fuel-Coolant Interaction

[1G07] Development of a Filter Venting System to Prevent Exposure to Radioactive Noble Gases

(4)Removal of radioactive noble gases by silica membrane with high durability

[1G08] The accident evaluation of JRR-3

[1G09-13] Severe Accident Analysis

[1G09] Evaluation of accident management measures in Early-in-vessel phase in PWR by MAAP5.06

[1G10] Numerical analysis of IVR code benchmark by MAAP5

(2)Heavy metal layer model

[1G11] Development of a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

(1)A Method of CFD Compressible Fluid Dynamics

[1G12] Development of a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

(2)Distribution analysis of hydrogen concentration

[1G13] Development of a CFD Compressible Fluid Dynamics Simulation Code: BAROC for Safety Analysis of Containment Vessel and Reactor Building Under Severe Accident Conditions

(3)Cesium behavior analysis

Authentication