2019 Fall Meeting

Presentation information

Oral presentation

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

[2G01-05] Severe Accident of Sodium-Cooled Fast Reactor 1

Thu. Sep 12, 2019 9:30 AM - 10:50 AM Room G (Common Education Bildg. 2F C22)

Chair:Takaaki Sakai(Tokai Univ.)

10:30 AM - 10:45 AM

[2G05] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(15)Viscosity Measurement of 7mass%B4C-SS Eutectic Molten Material

*Tsuyoshi Nishi1, Hiroki Kokubo1, Yuriko Takatsuka1, Hiromichi Ohta1, Hidemasa Yamano2 (1. Ibaraki Univ., 2. JAEA)

Keywords:Boron carbide, Stainless steel , Crucible rotational viscometer, 7mass%B4C-SS Eutectic Molten Material, Viscosity

B4C-SS共晶溶融物の粘度データはシビアアクシデント解析のパラメータとして必要不可欠な物性値である。本研究では、5mass%B4C、10mass%B4Cにつづき7mass%B4C-SS溶融混合物の粘度をるつぼ回転粘度計にて測定したので報告する。