Oral presentation

[3K01-06] Seismic Technologies, Development of SMR

Fri. Sep 9, 2022 10:15 AM - 11:55 AM Room K (E1 Bildg.4F No.43)

Chair:Tadashi Murofushi(TOSHIBA ESS)

10:15 AM - 10:30 AM

[3K01] Influence of Cut-off Frequency of Modal Superposition Method for Seismic Response Evaluation Using Three-Dimensional Finite Element Method Model

*Takahito Kumagai¹, Kazuma Hirosaka¹, Naotomo Maruyama², Yusuke Minakawa² (1. Hitachi, 2. HGNE)

10:30 AM - 10:45 AM

[3K02] Numerical Analysis for Clarifying Dynamic Buckling Behavior of PWR-CV during a Seismic Excitation

*Shinjiro Hidaka¹, Gaku Shoji¹ (1. University of Tsukuba)

10:45 AM - 11:00 AM

[3K03] Technical Demonstration for NuScale “VOYGR^TM”

(1) Technical Features for NuScale “VOYGR^TM” and Participation in Development Project

*Ryuki Tahara¹, Yasutomi Morimoto¹, Daisuke Koike², Yasuharu Kimura², Masanori Ijichi², Paul Boyadjan³ (1. JGC, 2. IHI, 3. NuScale Power)

11:00 AM - 11:15 AM

[3K04] Technical Demonstration for NuScale “VOYGR^TM”

(2) Engineering and manufacturing technology study on reactor building and components

*Daisuke Koike¹, Satoru Kai¹, Yasutomi Morimoto², Paul Boyadjan³ (1. IHI, 2. JGC, 3. NuScale Power)

11:15 AM - 11:30 AM

[3K05] Technical Demonstration for NuScale “VOYGR^TM”

(3) Structural Study Considering Transportation with Modularization of Reactor Building

*Eiji Kawada¹, Yuuki Sato¹, Shunji Kataoka¹, Tomoyuki Umezawa¹, Tsuyoshi Fujita¹, Shinichi Aya¹, Yasutomi Morimoto¹, Daisuke Koike², Paul Boyadjan³ (1. JGC, 2. IHI, 3. NuScale Power)

11:30 AM - 11:45 AM

[3K06] Technical Demonstration for NuScale “VOYGR^TM”

(4) Preliminary Physical Damage Evaluation of Reactor Building for Aircraft Impact Assessment

*Yuki Sato¹, Shunji Kataoka¹, Eiji Kawada¹, Yasutomi Morimoto¹, Tomoyuki Umezawa¹, Takahisa Kawase², Daisuke Koike³, Paul Boyadjan⁴ (1. JGC, 2. Kajima, 3. IHI, 4. NuScale Power)

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

Oral presentation

[3K07-10] Improving the Operation of Nuclear Regulatory Inspections, Development of Automatic Design System Using AI

Fri. Sep 9, 2022 2:45 PM - 3:55 PM Room K (E1 Bildg.4F No.43)

Chair:Fumihiko Ishibashi(TOSHIBA ESS)

2:45 PM - 3:00 PM

[3K07] Study on the improving the operation of nuclear regulatory inspections

(1) Research on current issues in the operation of the inspection system

*Shintaro Yagi¹, Junji Eto¹, Hiroki Sugino¹, Masaki Onodera¹, Kiyoshi Nakajima¹, Nobuaki yoshizawa¹, Kiyoteru Suzuki¹ (1. Mitsubishi Research Institute)

3:00 PM - 3:15 PM

[3K08] Research on the improving the operation of nuclear regulatory inspections

(2) Examination of improvement measures for current issues

*Junji Eto¹, Hiroki Sugino¹, Masaki Onodera¹, Shintaro Yagi¹, Kiyoshi Nakajima¹, Nobuaki Yoshizawa¹, Kiyoteru Suzuki¹ (1. MRI)

3:15 PM - 3:30 PM

[3K09] Development of Automatic Design System for Piping, Air Conditioning Duct and Cable Tray Using AI

(5) Automatic Design Considering Piping Heat Expansion

*Shiro Takahashi¹, Keita Okuyama¹, Junta Yamada², Tomoyasu Inoue², Eisuke Wakabayashi², Michiaki Kurosaki², syonosuke Yukita³ (1. Hitachi, 2. HGNE, 3. Hitachi Industry & Control Solutions)

3:30 PM - 3:45 PM

[3K10] Development of Automatic Design System for Piping, Air Conditioning Duct and Cable Tray Using AI

(6) Application example 2 to nuclear power plant

*Junta Yamada¹, Tomoyasu Inoue¹, Michiaki Kurosaki¹, Eisuke Wakabayashi¹, Shiro Takahashi², Keita Okuyama², Shonosuke Yukita³ (1. HGNE, 2. Hitachi, 3. Hitachi Industry & Control Solutions)

Time reserved for Chair （3:45 PM - 3:55 PM）

Sessions

IV. Nuclear Plant Technologies » 401-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

[3K01-06] Seismic Technologies, Development of SMR

[3K01] Influence of Cut-off Frequency of Modal Superposition Method for Seismic Response Evaluation Using Three-Dimensional Finite Element Method Model

[3K02] Numerical Analysis for Clarifying Dynamic Buckling Behavior of PWR-CV during a Seismic Excitation

[3K03] Technical Demonstration for NuScale “VOYGR^TM”

(1) Technical Features for NuScale “VOYGR^TM” and Participation in Development Project

[3K04] Technical Demonstration for NuScale “VOYGR^TM”

(2) Engineering and manufacturing technology study on reactor building and components

[3K05] Technical Demonstration for NuScale “VOYGR^TM”

(3) Structural Study Considering Transportation with Modularization of Reactor Building

[3K06] Technical Demonstration for NuScale “VOYGR^TM”

(4) Preliminary Physical Damage Evaluation of Reactor Building for Aircraft Impact Assessment

[3K07-10] Improving the Operation of Nuclear Regulatory Inspections, Development of Automatic Design System Using AI

[3K07] Study on the improving the operation of nuclear regulatory inspections

(1) Research on current issues in the operation of the inspection system

[3K08] Research on the improving the operation of nuclear regulatory inspections

(2) Examination of improvement measures for current issues

[3K09] Development of Automatic Design System for Piping, Air Conditioning Duct and Cable Tray Using AI

(5) Automatic Design Considering Piping Heat Expansion

[3K10] Development of Automatic Design System for Piping, Air Conditioning Duct and Cable Tray Using AI

(6) Application example 2 to nuclear power plant

Authentication

Sessions

IV. Nuclear Plant Technologies » 401-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

[3K01-06] Seismic Technologies, Development of SMR

(1) Technical Features for NuScale “VOYGRTM” and Participation in Development Project

(2) Engineering and manufacturing technology study on reactor building and components

(3) Structural Study Considering Transportation with Modularization of Reactor Building

(4) Preliminary Physical Damage Evaluation of Reactor Building for Aircraft Impact Assessment

[3K07-10] Improving the Operation of Nuclear Regulatory Inspections, Development of Automatic Design System Using AI

(1) Research on current issues in the operation of the inspection system

(2) Examination of improvement measures for current issues

(5) Automatic Design Considering Piping Heat Expansion

(6) Application example 2 to nuclear power plant

Authentication

(1) Technical Features for NuScale “VOYGR^TM” and Participation in Development Project