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Journal Articles

Preliminary study on separation of Dy and Nd by multi-step extraction using TDdDGA

Sasaki, Yuji; Ban, Yasutoshi; Morita, Keisuke; Matsumiya, Masahiko*; Ono, Ryoma*; Shiroishi, Hidenobu*

Solvent Extraction Research and Development, Japan, 27(1), p.63 - 67, 2020/00

 Times Cited Count:6 Percentile:31.74(Chemistry, Multidisciplinary)

Mutual separation technique of Dy and Nd in Nd magnet is studied. Dy is more valuable than Nd, then Dy might be isolated and reused. Lanthanide elements can be extracted thoroughly by diglycolamide (DGA) extractants, we use this reagent for the recovery and isolation of Dy. Tetradodecyl-DGA (TDdDGA) has relatively high separation factors(SF) between Dy and Nd (SF=17-18) in HNO$$_{3}$$ extraction system, counter-current extraction using TDdDGA was applied for their mutual separation. From the present study, using the condition, four extraction stages, organic phase: 0.1M TDdDGA in n-dodecane, aqueous phase: 0.3M HNO$$_{3}$$, 92% Dy can be recovered with 0.7% co-extraction of Nd.

JAEA Reports

None

*; *; ; Takeda, Seiichiro

PNC TN8410 97-433, 49 Pages, 1997/12

PNC-TN8410-97-433.pdf:1.44MB

None

JAEA Reports

None

; ; *; ; Takeda, Seiichiro

PNC TN8410 97-425, 34 Pages, 1997/11

PNC-TN8410-97-425.pdf:0.97MB

None

JAEA Reports

None

; *; ; ; Takeda, Seiichiro

PNC TN8410 97-104, 56 Pages, 1997/04

PNC-TN8410-97-104.pdf:2.06MB

None

Journal Articles

Plutonium and uranium ion determination and differentiation besed on twin electrode flow coulometry

; ; *

Anal. Chem., 59, p.400 - 405, 1987/00

 Times Cited Count:35 Percentile:84.9(Chemistry, Analytical)

no abstracts in English

JAEA Reports

Determination of Plutonium in Nitric Acid Solution by Spectrophotometry of Pu(VI)

; ; ; ;

JAERI-M 86-032, 10 Pages, 1986/03

JAERI-M-86-032.pdf:0.39MB

no abstracts in English

Journal Articles

Formation of radioactive organic iodides and its suppression

Tachikawa, Enzo

Genshiryoku Kogyo, 19(12), p.50 - 52,76, 1973/12

no abstracts in English

Journal Articles

The potentiometric determination of plutonium in nitric acid medium

;

Bunseki Kagaku, 18(10), p.1264 - 1265, 1969/00

no abstracts in English

Oral presentation

Study on corrosion of stainless steel in high activity liquid waste concentrator, 2; Effect of precipitates on corrosion

Ueno, Fumiyoshi; Irisawa, Eriko; Seki, Masaharu; Abe, Hitoshi

no journal, , 

no abstracts in English

Oral presentation

Effect of re-oxidation rate of additive cation on corrosion rate of stainless steel in boiling nitric acid solution

Yamamoto, Masahiro; Kato, Chiaki; Motooka, Takafumi; Irisawa, Eriko; Ban, Yasutoshi; Ueno, Fumiyoshi

no journal, , 

Stainless steels used in nuclear fuel reprocessing plant occur intergranular corrosion by boiling nitric acid solution containing some cations. Reduction reaction of these cations accelerates corrosion rate of stainless steel, and then, they are re-oxidized to initial state in bulk nitric acid solution. These re-oxidized cations repeatedly concern corrosion reaction of stainless steel. The re-oxidation rates of typical cations were analyzed in the present work. As the result, Np ion accelerates corrosion of stainless steel in a little amount because it has both large reduction reaction rate and re-oxidation rate.

Oral presentation

Effect of nitric acid concentration on corrosion behavior of Fe-12Cr-6Al based oxide dispersion strengthened steels

Ambai, Hiromu; Takahatake, Yoko; Sano, Yuichi; Takeuchi, Masayuki; Koizumi, Kenji; Yamashita, Shinichiro; Sakamoto, Kan*

no journal, , 

A FeCrAl-ODS steel has been developed for the accident tolerant fuel cladding of light water reactors in Japanese projects. Spent fuel are reprocessed in Japan, namely spent fuel pins are chopped and immersed into a hot nitric acid solution to leach out the fuel. Behavior of the corrosion products from fuel cladding should be evaluated to estimate the influence of those on the reprocessing process. In this study, effect of nitric acid concentration on corrosion behavior of Fe-12Cr-6Al based oxide dispersion strengthened steels was evaluated.

Oral presentation

Zirconium separation on uranium nitrate solution by zeolite

Takahatake, Yoko; Sakamoto, Atsushi; Asanuma, Noriko*; Matsuura, Haruaki*; Watanabe, So; Watanabe, Masayuki

no journal, , 

no abstracts in English

16 (Records 1-16 displayed on this page)
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