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Oral presentation

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

[2G06-09] Severe Accident of Sodium-Cooled Fast Reactor 2

Thu. Sep 12, 2019 10:50 AM - 11:55 AM Room G (Common Education Bildg. 2F C22)

Chair:Daisuke Ito(Kyoto Univ.)

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10:50 AM - 11:05 AM

[2G06] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(16)Immersion Tests of B₄C into Molten Stainless Steel

*Yuki Emura¹, Kenji Kamiyama¹, Hidemasa Yamano¹ (1. JAEA)

11:05 AM - 11:20 AM

[2G07] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(17)Reaction Behavior between Molten Stainless Steel and Solid Boron Carbide

*Kinya Nakamura¹, Hirokazu Ohta¹, Yuki Emura², Toshihide Takai², Hidemasa Yamano² (1. CRIEPI, 2. JAEA)

11:20 AM - 11:35 AM

[2G08] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(18)Validation of Eutectic Reaction Model for Use in Reactor Safety Analysis Code

*Xiaoxing Liu¹, Koji Morita¹, Hidemasa Yamano² (1. Kyushu Univ., 2. JAEA)

11:35 AM - 11:50 AM

[2G09] Studies on Relocation Behavior of Molten Core Materials in the Core Disruptive Accident of Sodium-cooled Fast Reactors

(7)Validation of Analysis Models for the Melt Discharge Experiments into a Shallow Water Pool

*Kai Igarashi¹, Takaaki Sakai¹, Shinya Kato², Kenichi Matsuba², Kenji Kamiyama² (1. Tokai University , 2. JAEA)

Time reserved for Chair (11:50 AM - 11:55 AM)

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