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)

10:35 AM - 10:50 AM

[2M05] Development of Safety Design Technologies for Sodium-Cooled Fast Reactor Coupled to Thermal Energy Storage System with Sodium–Molten Salt Heat Exchanger

(4) Risk assessment technology for heat transfer tube failure in the molten-salt thermal energy storage system

*Kazuya Takano1, Kenichi Kurisaka1, Hidemasa Yamano1 (1. JAEA)

Keywords:sodium-cooled fast reactor, molten salt, sodium-molten salt heat exchanger, heat transfer tube failure

As part of the development of risk assessment technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium–molten salt heat exchanger, the database on the number of heat transfer tube failure in molten salt heat exchanger and exposure time of Concentrated Solar Power (CSP) system to molten-salt was surveyed on the basis of reported practices of incidents/accidents in the existing CSP systems with molten-salt heat storage system. Using the database, a risk assessment methodology of the heat transfer tube failure frequency was also studied with a Bayesian estimation method.

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