OS-s(部門単独)

[S081] 原子力システムおよび要素技術 (1)

Mon. Sep 4, 2023 11:15 AM - 12:00 PM Room 35 (11-306)

座長:大川富雄

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11:15 AM - 11:30 AM

[S081-01] Effect of Oxide Film Damage on Electrochemical Property of Stainless Steels

〇Osamu Kuwazuru¹, Kodai Yuri¹, Misaki Tanaka¹ (1. 福井大学)

11:30 AM - 11:45 AM

[S081-02] Fatigue Crack Coalescence Behavior of Stainless Steel Plate with Multiple Cracks

〇Kaito Ikeda³, Noriyo Horikawa¹, Takahiro Kinoshita¹, Shigeki Okamura¹, Hideo Machida², Hiroshi Ogawa², Manabu Arakawa², Suzuko Tamashiro², Ryota Uchikawa² (1. 富山県立大学、2. 株式会社テプコシステムズ、3. 富山県立大学大学院)

11:45 AM - 12:00 PM

[S081-03] Coalescence Behavior of Creep Crack Propagation in Stainless Steel Plate with Multiple Cracks

〇Yusuke Nishikawa³, Noriyo Horikawa¹, Takahiro Kinoshita¹, Shigeki Okamura¹, Hideo Machida², Hiroshi Ogawa², Manabu Arakawa², Suzuko Tamashiro², Ryota Uchikawa² (1. 富山県立大学、2. 株式会社テプコシステムズ、3. 富山県立大学大学院)

OS-s(部門単独)

[S081] 原子力システムおよび要素技術 (2)

Mon. Sep 4, 2023 1:00 PM - 2:00 PM Room 35 (11-306)

座長:西村聡

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1:00 PM - 1:15 PM

[S081-04] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress until JFY2022

〇Hidemasa Yamano¹, Toshihide Takai¹, Yuki Emura¹, Hiroyuki Fukuyama², Tsuyoshi Nishi³, Koji Morita⁴, Kinya Nakamura⁵, Marco Pellegrini⁶ (1. 日本原子力研究開発機構、2. 東北大学、3. 茨城大学、4. 九州大学、5. 電力中央研究所、6. 東京大学)

1:15 PM - 1:30 PM

[S081-05] Development of Reactor Vessel Thermal-hydraulic Analysis Method in Natural Circulation Conditions -Investigation of Thermal-hydraulic Analysis Model for Interwrapper Gap between Assemblies-

〇Erina HAMASE¹, Yasuhiro MIYAKE², Yasutomo IMAI², Norihiro DODA¹, Ayako ONO¹, Masaaki TANAKA¹ (1. 日本原子力研究開発機構、2. 株式会社エヌデーデー)

1:30 PM - 1:45 PM

[S081-06] 講演取り下げ

1:45 PM - 2:00 PM

[S081-07] Design optimization of containment vessel by severe accident integrated analysis in sodium-cooled fast reactors

〇Akihiro Uchibori¹, Yasutomo Imai², Yoshimi Shiina², Yasushi Okano¹ (1. 日本原子力研究開発機構、2. 株式会社エヌデーデー)

OS-s(部門単独)

[S081] 原子力システムおよび要素技術 (3)

Mon. Sep 4, 2023 2:15 PM - 3:15 PM Room 35 (11-306)

座長:山野秀将

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2:15 PM - 2:30 PM

[S081-08] Study and development of cutting methods for lead shielding materials associated with decommissioning of nuclear power plants

〇Tomohisa Goto¹, Takeyoshi Sunagawa¹, Glenn Harvel² (1. 福井工業大学、2. オンタリオ工科大学)

2:30 PM - 2:45 PM

[S081-09] Improvements of thermal performance by nanoparticle layer in heat pipes

〇Menglei Wang¹, Yifan Liu¹, Tomio Okawa¹ (1. 電気通信大学)

2:45 PM - 3:00 PM

[S081-10] Prediction of wall thinning due to flow-accelerated corrosion at drift region in T-joint pipe

〇Shun Watanabe¹, Ryo Morita¹ (1. 一般財団法人電力中央研究所)

3:00 PM - 3:15 PM

[S081-11] Simplification of the estimation method of wall thinning at the T tube junction in an actual plant

〇Shun Watanabe¹, Ryo Morita¹ (1. 一般財団法人電力中央研究所)

OS-s(部門単独)

[S081] 原子力システムおよび要素技術 (4)

Mon. Sep 4, 2023 3:30 PM - 4:30 PM Room 35 (11-306)

座長:内堀昭寛

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3:30 PM - 3:45 PM

[S081-12] Heat transfer experiment on spray cooling in spent fuel pool

〇Taizo Kanai¹, Satoshi Nishimura¹ (1. 電中研)

3:45 PM - 4:00 PM

[S081-13] Decontamination factor of Aerosol in pool scrubbing

〇Taizo Kanai¹, Satoshi Nishimura¹ (1. 電中研)

4:00 PM - 4:15 PM

[S081-14] A correlation between large bubble formation and the onset of significant void based on the global bubble coalescence mechanism model

〇Binh Thanh Nguyen¹, Okawa Tomio¹, Ryoma Tsujimura¹ (1. 電気通信大学)

4:15 PM - 4:30 PM

[S081-15] Comparison of Quench Velocity Between One and Two Cooling Surfaces Using Metal Plates

〇Akbari Akbari¹, Tomio Okawa¹ (1. 電気通信大学)

Sessions

OS-s(部門単独) » S081 原子力システムおよび要素技術

[S081] 原子力システムおよび要素技術 (1)

[S081-01] Effect of Oxide Film Damage on Electrochemical Property of Stainless Steels

[S081-02] Fatigue Crack Coalescence Behavior of Stainless Steel Plate with Multiple Cracks

[S081-03] Coalescence Behavior of Creep Crack Propagation in Stainless Steel Plate with Multiple Cracks

[S081] 原子力システムおよび要素技術 (2)

[S081-04] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress until JFY2022

[S081-05] Development of Reactor Vessel Thermal-hydraulic Analysis Method in Natural Circulation Conditions -Investigation of Thermal-hydraulic Analysis Model for Interwrapper Gap between Assemblies-

[S081-06] 講演取り下げ

[S081-07] Design optimization of containment vessel by severe accident integrated analysis in sodium-cooled fast reactors

[S081] 原子力システムおよび要素技術 (3)

[S081-08] Study and development of cutting methods for lead shielding materials associated with decommissioning of nuclear power plants

[S081-09] Improvements of thermal performance by nanoparticle layer in heat pipes

[S081-10] Prediction of wall thinning due to flow-accelerated corrosion at drift region in T-joint pipe

[S081-11] Simplification of the estimation method of wall thinning at the T tube junction in an actual plant

[S081] 原子力システムおよび要素技術 (4)

[S081-12] Heat transfer experiment on spray cooling in spent fuel pool

[S081-13] Decontamination factor of Aerosol in pool scrubbing

[S081-14] A correlation between large bubble formation and the onset of significant void based on the global bubble coalescence mechanism model

[S081-15] Comparison of Quench Velocity Between One and Two Cooling Surfaces Using Metal Plates

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