2017 Annual Meeting

Presentation information

Oral presentation

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

[2G04-09] Knowledge preservation of Monju data

Tue. Mar 28, 2017 10:20 AM - 12:00 PM Room G (16-207 Building No.16)

Chair: Naoto Kasahara (Univ. of Tokyo)

11:20 AM - 11:35 AM

[2G08] The results obtained from the 20 years of “Monju” plant data

(8)Purity management of sodium

*Yoshihide Nakamura1, Hiromasa Sawazaki1, Tatsuya Morioka1, Takenobu Uchida1, Takeshi Sato1, Hiroki Shiotani1, Naoyuki Kisohara1 (1. Japan Atomic Energy Agency)

Keywords:Monju, purity control condition , plugging meter, chemical analysis

With the liquid metal sodium cooled fast reactor, sodium has to be maintained and managed at a high purity to prevent the channel blockage by the precipitation of impurities and the material corrosion with sodium.

At Monju, primary heat transport system, secondary heat transport system, and ex-vessel fuel storage tank sodium cooling system are corresponding to this clean-up system.

We evaluate the sodium purity control condition of these facilities for more than 20 years by the measurement of the plugging meter and chemical analysis, and confirm that we could maintain the purity with a value lower enough than the management targeted value.