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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.

Journal Articles

None

; ; ; ;

Saikuru Kiko Giho, (15), p.41 - 46, 2002/06

None

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.

Journal Articles

Determination of americium in a nitric acid medium using second-order derivative spectrophotometry

Hiyama, Toshiaki; ; Kageyama, Tomio;

Analytical Sciences, 12(3), p.427 - 430, 1996/00

 Times Cited Count:4 Percentile:20.05(Chemistry, Analytical)

None

JAEA Reports

None

; ; ; ; ; *; *

PNC TN8450 95-008, 44 Pages, 1995/09

PNC-TN8450-95-008.pdf:25.05MB

None

JAEA Reports

None

; ; *; ;

PNC TN8410 95-223, 37 Pages, 1995/08

PNC-TN8410-95-223.pdf:0.85MB

None

Journal Articles

Determination of occluded gases in mixed oxide fuel pellets/using gas sampling unit and gas chromatography

; ; ; Kamimura, Katsuichiro

Journal of Nuclear Materials, 218(1), p.1 - 7, 1995/07

 Times Cited Count:2 Percentile:28.12(Materials Science, Multidisciplinary)

None

JAEA Reports

None

; ; *; ;

PNC TN8450 95-001, 110 Pages, 1995/01

PNC-TN8450-95-001.pdf:5.0MB

None

JAEA Reports

None

; ;

PNC TN8410 93-217, 74 Pages, 1993/09

PNC-TN8410-93-217.pdf:3.71MB

None

JAEA Reports

None

Kamimura, Katsuichiro; Sugaya, Shinichi; Fujita, Shinichi*; Hiyama, Toshiaki; Yamamoto, Junta

PNC TN8410 93-211, 47 Pages, 1993/09

PNC-TN8410-93-211.pdf:0.78MB

None

Journal Articles

None

; ; ; Kamimura, Katsuichiro

Donen Giho, (87), p.45 - 52, 1993/09

None

JAEA Reports

None

*

PNC TN8410 90-084, 43 Pages, 1990/09

PNC-TN8410-90-084.pdf:0.63MB

None

Oral presentation

Test of neutralization treatment for radioactive liquid waste by using sodium hydroxide, 1; Outline of neutralization treatment test

Nakamura, Hironobu; Mukai, Yasunobu; Yoshimoto, Katsunobu; Fujiwara, Hideki*; Kamoshida, Shuichi*; Sugaya, Shinichi*; Mine, Tadaharu*

no journal, , 

no abstracts in English

Oral presentation

Test of neutralization treatment for radioactive liquid waste by using sodium hydroxide, 2; Confirmation of decontamination effects by neutralization

Fujiwara, Hideki*; Kamoshida, Shuichi*; Sugaya, Shinichi*; Nakamura, Hironobu; Koiso, Katsuya; Yoshimoto, Katsunobu

no journal, , 

no abstracts in English

Oral presentation

Test of neutralization treatment for radioactive liquid waste by using sodium hydroxide, 3; Behavior of moisture content in a calcined neutralization precipitate

Suzuki, Yoshimasa; Mukai, Yasunobu; Nakamura, Hironobu; Kurosawa, Akira; Fujiwara, Hideki*; Kamoshida, Shuichi*; Sugaya, Shinichi*

no journal, , 

no abstracts in English

Oral presentation

Pu standard materials prepared from a MOX source material

Sumi, Mika; Kikuchi, Takahiro; Abe, Katsuo; Sato, Mitsuhiro; Kageyama, Tomio; Yamaguchi, Kazuya*; Fujiwara, Hideki*; Sugaya, Shinichi*

no journal, , 

Accurate and precise measurements of nuclear materials are critically important for the nuclear nonproliferation and having capabilities to obtain reliable measurement is the premise of safeguards inspection by IAEA and the state at Nuclear Fuel handling facilities. Pu handling laboratories in Japan applies Mass Spectrometry (MS) for isotopic measurement and Isotope Dilution Mass Spectrometry (IDMS) for content measurement for the accountancy purposes, however, Pu standard materials essential for isotope dilution are only available from foreign suppliers. When JNFL starts its operation, required amount of Pu standard materials will increase while transportation of Pu materials are becoming more difficult and has potential risk of shortage. Thus, JAEA has been developing the technique to prepare Pu standard materials by themselves for the reliable and continuous accountancy analysis.

16 (Records 1-16 displayed on this page)
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