2022 Annual Meeting

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Oral presentation

IV. Nuclear Plant Technologies » 401-2 Operational Management, Inspection and Maintenance of Reactor

[1F12-15] Advanced Management Technology of Reactor Operation Management

Wed. Mar 16, 2022 4:10 PM - 5:20 PM Room F

Chair: Takayuki Miyagawa (JAPC)

4:25 PM - 4:40 PM

[1F13] Sodium discharge test of dummy fuel assembly

*Munemichi Kawaguchi1, Yasushi Hirakawa1, Yusuke Sugita1, Yutaka Yamaguchi1 (1. JAEA)

Keywords:Sodium-cooled fast reactor, Simulated fuel assembly, adhesion sodium

A small-scale sodium discharge test was carried out to estimate the amount of sodium remained on the dummy fuel assembly of the prototype fast breeder reactor "Monju" after withdrawing from the sodium pool.