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)

11:20 AM - 11:35 AM

[2M08] Development of Mechanistic Source Term Evaluation Methodology for Sodium-cooled Fast Reactors

Benchmark analyses on fission product gas bubble behavior in liquid sodium coolant

*Yasushi OKANO1, Akihiro UCHIBORI1 (1. JAEA)

Keywords:Fission Product, Transport Phenomena, Sodium, Fast Reactor, TRACER

To quantify the migration behavior of bubbles containing non-condensable gas fission products after being released from fuel pins, it is essential to develop numerical analysis code including physical, chemical, and flow models. In this report, we focus on the breakup behavior of bubbles during elevation in sodium coolant, and we report on the results of benchmark analyses on the correlation between the decontamination factor and the bubble rise velocity.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password