Development of Fast Reactor Containment Safety Analysis Code, CONTAIN-LMR

Munemichi Kawaguchi

Presentation information

Oral presentation

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

[3L01-04] Fast Reactor

Fri. Mar 22, 2019 9:30 AM - 10:35 AM Room L (Common Education Bildg. 2 3F No.36)

Chair:Kennichi Matsuba(JAEA)

10:15 AM - 10:30 AM

[3L04] Development of Fast Reactor Containment Safety Analysis Code, CONTAIN-LMR

Validation Study of Sodium-concrete Reaction Model

*Munemichi Kawaguchi¹, Ikuo Yamamoto¹, Hiroshi Seino¹ (1. JAEA)

Keywords:Fast reactor, Sever accident assessment, Containment vessel, Sodium-concrete reaction, CONTAIN-LMR

The CONTAIN-LMR code has been developed in Japan Atomic Energy Agency (JAEA) for the quantitative assessment of severe accident consequences in sodium-cooled fast reactor (SFR). We will present results of the development and validation for the sodium-concrete reaction model (SLAM) in this code.