2024 Annual Meeting

Presentation information

Oral presentation

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

[2M05-09] Fast Reactor

Wed. Mar 27, 2024 10:35 AM - 12:00 PM Room M (21Bildg.4F 21-424)

Chair:Erina HAMASE(JAEA)

11:05 AM - 11:20 AM

[2M07] Development of Safety Design Technologies for Sodium-Cooled Fast Reactor Coupled to Thermal Energy Storage System with Sodium–Molten Salt Heat Exchanger

(6) Fundamental experiment on chemical reactivity of sodium-molten salt

*SHIN KIKUCHI1, RIKA SATO1, 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 preparation status of fundamental experiment and some results of preliminary experiment.

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