2023 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-4 Reactor Component Technology, First Wall, Divertor, Magnet/601-5 Fusion Neutronics/601-6 Fusion Reactor System, Design, Application

[3A05-09] Reactor Components and Risk Assessment

Wed. Mar 15, 2023 10:40 AM - 12:00 PM Room A (11 Bildg.1F 1101)

Chair:Naoko Ashikawa(NIFS)

11:10 AM - 11:25 AM

[3A07] Experimental Study on Li fire with the heat insulator employed in the liquid Li target loop of a fusion neutron source

*Shunsuke Kenjo1, Makoto Oyaidzu1, Kazuhiro Obata1, Kentaro Ochiai1, Satoshi Sato1 (1. QST)

Keywords:A-FNS, fusion neutron source, liquid metal, liquid lithium loop, Li fire

In a fusion neutron source, liquid Li has been applied as target material. For the safety operation of the liquid Li target, Li fire risk reduction is indispensable. In order to reveal the conditions of Li fire ignition for the Li target safety, an experimental study on Li fire has been performed under the IFMIF/EVEDA project. The humidity at which Li fire ignites was investigated by changing the humidity and heating Li samples. The compatibility between Li and a heat insulator was experimentally evaluated since the leaked Li from a loop contact with an insulator. From the results, it is revealed the insulator planned to be employed in a fusion neutron source, A-FNS, has no characteristics encouraging Li fire ignition.