2022 Fall Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[3F06-10] Small Modular Reactor

Fri. Sep 9, 2022 10:45 AM - 12:00 PM Room F (E1 Bildg.3F No.31)

Chair:Ken-ichi Fukumoto(Univ. of Fukui)

11:15 AM - 11:30 AM

[3F08] Development of an innovative small sodium-cooled fast reactor

(12) 3D thermal hydraulic transient analysis of RVACS heat removal characteristics

*Guillaume Laurent Grandjean1, Hirotaka Nakahara1, Takashi Abe1, Kazuhiro Fujimata1, Kazuhiko Matsumura1 (1. HGNE)

Keywords:Sodium cooled Fast Reactor (SFR), RVACS, Natural circulation, Heat removal, Passive safety, Computational Fluid Dynamics, STAR-CCM+

In the framework of the development of the design of a Sodium cooled Fast Reactor (SFR) Reactor Vessel Auxiliary Cooling System (RVACS), 3D thermal-hydraulics transient analyses are performed to validate the capability of the RVACS to remove passively decay heat from the reactor using natural circulation. A short-term thermal-hydraulics analysis of a Loss Of Heat Sink (LOHS) transient has been carried out using a 3D CFD calculation code (STAR-CCM+). Analyses results showed the transition from forced circulation to natural circulation of primary coolant inside the reactor vessel and the evolution of the RVACS heat removal capacity in the first hour of the transient.