2023 Annual Meeting

Presentation information

Oral presentation

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

[2L01-04] Improvement design of Molten salt reactor

Tue. Mar 14, 2023 9:30 AM - 10:35 AM Room L (13 Bildg.2F 1323)

Chair:Hirokazu Ohta(CRIEPI)

10:00 AM - 10:15 AM

[2L03] Development of Safety Design Technologies for Sodium-Cooled Fast Reactor Coupled to Thermal Energy Storage System with Sodium–Molten Salt Heat Exchanger

(3) Study on Chemical Reactivity of Sodium-Moten Salt

*Shin Kikuchi1, Toshiki Kondo1, Ryota Umeda1, Hidemasa Yamano1 (1. Japan Atomic Energy Agency)

Keywords:sodium-cooled fast reactor, molten salt, chemical reaction, thermal analysis

As part of the development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium–molten salt heat exchanger, we are considering the chemical reactivity between liquid metallic sodium and nitric acid-based molten salt, assuming boundary failure in heat exchangers. In this report, we present the fundamental experiment planning and the status of the present study for the cited reaction.