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Wakai, Eiichi; Watanabe, Kazuyoshi*; Ito, Yuzuru*; Suzuki, Akihiro*; Terai, Takayuki*; Yagi, Juro*; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; et al.
Plasma and Fusion Research (Internet), 11, p.2405112_1 - 2405112_4, 2016/11
; Nemoto, Masaaki; Saikawa, Takuya*; Sukegawa, Kazuya*
JNC TN9410 2000-008, 66 Pages, 2000/03
JNC-TN9410-2000-008.pdf:1.39MB
The experimental fast reactor "JOYO" served as the MK-II irradiation bed core for testing fuel and material for FBR development for 15 years from 1982 to 1997. During the MK-II operation, impurities concentrations in the sodium and the argon gas were determined by 67 samples of primary sodium, 81 samples of secondary sodium, 75 samples of primary argon gas, 89 samples of secondary argon gas (the overflow tank) and 89 samples of secondary argon gas (the dump tank). The sodium and the argon gas purity control data were accumulated from in thirty-one duty operations, thirteen special test operations and eight annual inspections. These purity control results and related plant data were compiled into database, which were recorded on CD-ROM for user convenience. Purity control data include concentration of oxygen, carbon, hydrogen, nitrogen, chlorine, iron, nickel and chromium in sodium, concentration of oxygen, hydrogen, nitrogen, carbon monoxide, carbon dioxide, methane and helium in argon gas with the reactor condition.
; Sumino, Kozo; Yasu, Tetsunori; ; ; ; Terunuma, Seiichi
PNC TN9410 91-376, 79 Pages, 1991/11
None
Furukawa, Tomohiro; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Iijima, Minoru; Wakai, Eiichi
no journal, ,
The purification performance of lithium by a cold trap which was installed in the EVEDA lithium test loop has been done under the validation activities in the IFMIF/EVEDA. The chemical analysis was conducted for the lithium sampled during the experiment, and the performance was evaluated.
Sato, Takeshi; Okawachi, Yasushi; Nakamura, Yoshihide; Sawazaki, Hiromasa
no journal, ,
In the Monju, before expanding accident in the unlikely event of a water leak from the steam generator tubes, capturing the hydrogen concentration changes in the secondary sodium, it is important to early detect the corresponding water leak. Its detection sensitivity, the amount of hydrogen diffused from the water side to the secondary sodium in through the heat exchanger tube during normal operation, depends on the performance of the cold trap to remove it. So, this time was carried out to confirm the purification efficiency derived by using the operating data of the actual machine of purification efficiency and about 20 years was expected in the design of the secondary sodium purification system cold trap.
Sato, Takeshi; Sawazaki, Hiromasa; Morioka, Tatsuya; Uchida, Takenobu; Nakamura, Yoshihide; Shiotani, Hiroki; Okawachi, Yasushi
no journal, ,
In Monju, it is important to detect and respond to hydrogen concentration changes in secondary sodium at an early stage, before any water leakage from the steam generator heat transfer tube expands. For that purpose, it is necessary to understand the hydrogen concentration during normal operation. In this report, we estimated, using the purification efficiency evaluation of the cold trap reported at the fall programs of 2016, the amount of diffused hydrogen from the characteristic test data of 1995 and evaluated the hydrogen concentration in the secondary sodium during normal operation.
