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JAEA Reports

Evaluation of dissolution rate on high plutonium content MOX fuel

; Endo, Hideo; Ogasawara, Masahiro*; Shinada, Masanori*; *

JNC TN8440 2003-004, 24 Pages, 2003/05

JNC-TN8440-2003-004.pdf:5.0MB

The dissolution rate of high Pu content MOX fuel into the nitric acid was measured as a function of Pu content. MOX fuel sample which was pressed and sintered, were dissolved in boiling 7M nitric acid, and dissolution rate was measured by analysis of the Pu and U concentration in the solution. Dissolution rate of MOX fuel had the following tendencies : it decreased with increase of the Pu content and was reduced after 6 hours dissolution. These results agreed well to previous one, but dissolution rate was 3-6 times larger than that. It is estimated that the cause of this difference was due to the underestimate of surface area of MOX fuel powder and the difference of MOX O/M ratio.

JAEA Reports

Determination of neptunium in neptunium-uranium-plutonium mixed oxide fuel by spectrophotometry.

; ; ; ; ; *; *

JNC TN8400 2001-026, 29 Pages, 2001/12

JNC-TN8400-2001-026.pdf:0.99MB

The measurement condition by spectrophotometry was evaluated to measure Np content in MOX fuel containing Np. The Np concentration was obtained by measuring the 727nm absorption peak, after the valence of Np in the sample solution was adjusted to the Np(Ⅳ). The calibration curve showed the linearity up to Np concentration 0.8mg/ml. Though Pu and U quantity were respectively added to the Np solution to 30 times and 60 times of Np concentration, there was no effect to the Np analysis. By using this method, relative standard deviation (RSD) of the analyzed values of Np content for 2%Np - MOX fuel was about 4%. In addition, It was confirmed that the Np content could be measured without separating Np from Pu and U. This method can be sufficiently applied as a quick simple method to analyze Np content in MOX fuel containing Np.

Oral presentation

In situ analysis of radioactive strontium-90 (yttrium-90) in decontaminated waters in dam of the storage tanks in Fukushima Daiichi Nuclear Power Station

Suwa, Toshio; Kuno, Takehiko; Sato, Soichi; Onuma, Kazuhiro*; Kohata, Masato*; Kawasaki, Satoshi

no journal, , 

no abstracts in English

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