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Journal Articles

Extraction and separation of Am(III) and Sr(II) by N,N,N',N'-tetraoctyl-3-oxapentanediamide (TODGA)

Suzuki, Hideya*; Sasaki, Yuji; Sugo, Yumi; Apichaibukol, A.; Kimura, Takaumi

Radiochimica Acta, 92(8), p.463 - 466, 2004/08

 Times Cited Count:80 Percentile:97.75(Chemistry, Inorganic & Nuclear)

The promising extractant for the partitioning of HLLW, TODGA, was used and investigated for the extraction of Sr(II) and separation from Am(III). Both metal ions can be extracted by TODGA based on the extraction reaction accompanying the neutral HNO$$_{3}$$ as well as the counter anion, NO$$_{3}$$$$^{-}$$. The mixture of TODGA and monoamide can reduce the distribution ratio of Sr(II), compared to the D(Sr) without monoamide, this solvent may extract only Am(III) with holding Sr(II) in the aqueous phase. After extraction of An by TODGA and monoamide, Sr(II) remaining in HLLW can be extracted by using enough high concentration of TODGA at the next step. Because of its high D value, Sr(II) can be coextracted with An by TODGA. It was observed that D(Sr) decrease with an increase of HNO$$_{3}$$ from 3M to 6M HNO$$_{3}$$ at the same TODGA concentration, while Am(III) has still high D values at least until 6M HNO$$_{3}$$. By using 6M HNO$$_{3}$$ of aqueous phase, An and Sr(II) can be separated after coextraction.

Journal Articles

The Adsorption behavior of strontium and cesium on zeolite A, Mordenite and titanium oxide

H.K.Lee*; Ishiyama, Shintaro; Eto, Motokuni; *; *

Proc. of the Int. Symp. on Material Chemistry in Nuclear Environment, p.525 - 537, 1992/00

no abstracts in English

JAEA Reports

Effects of Noble Metal Elements on Properties of Simulated Vitrified Products for High-Level Liquid Waste

; ; Takahashi, Takeshi

PNC TN8410 91-247, 29 Pages, 1991/12

PNC-TN8410-91-247.pdf:0.8MB

The effects of noble metal elements such as ruthenium, rhodium and palladium on the viscosity and electrical resistivity of simulated nuclear waste glass were studied. The glass enriched with noble metals showed the viscosity of a non-Newtonian fluid. The viscosity of the waste g1ass with 10 wt% RuO$$_{2}$$ was 3 to 7 times higher than that of glass without noble metals. The RuO$$_{2}$$ was mainly responsible for the increase in viscosity for the glass enriched with noble metals. Electrical resistivity of the glass with 15 wt% RuO$$_{2}$$, was one seventh to two orders of magnitude lower than that of glass without noble metals. The three noble metals contributed to the decrease in resistivity. The quantitative effects of noble metals on these properties were obtained.

Oral presentation

Development of recovery process of platinum-group metals from HLLW for stable production and volume reduction of homogeneous vitrified object, 24; Comprehensive evaluation of sorbent for separation of platinum group species

Amamoto, Ippei; Kobayashi, Hidekazu; Ayame, Yasuo; Onishi, Takashi; Inaba, Yusuke*; Utsumi, Kazuo*; Takeshita, Kenji*; Onoe, Jun*; Koshizaka, Akiko*; Hasegawa, Yoshio*

no journal, , 

The development on synthesis of sorbent was carried out to separate the platinum group species such as Ru, Rh and Pd in high-level radioactive liquid waste. After sorption test using developed sorbents, the spherical porous silica impregnated aluminium ferrocyanide was effective to sorb the species of Ru and Pd in the nitric solution. This sorption effect remained stable when tested on actual high-level radioactive liquid waste. It was found that more treated waste could be loaded into the borosilicate glass than untreated waste.

Oral presentation

Development of a new extraction method for minor actinide separation

Suzuki, Hideya*; Ban, Yasutoshi; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Kurosawa, Tatsuya*; Shibata, Mitsunobu*; Kawasaki, Tomohiro*; Matsumura, Tatsuro

no journal, , 

A highly practical hybrid-type (soft ${it N}$-donor and hard ${it O}$-donor) extractant, which is an alkyldiamideamine (ADAAM), was investigated for the minor actinides (MA) separation. The new process aims at recovering americium (Am) alone from high-level waste liquid (HLLW) using an ADAAM. The principle of the process is based on the extraction of Am together with light lanthanides (La, Ce, Pr and Nd) and Mo having close values of distribution ratio, while curium, other lanthanides, and other fission products remain in the aqueous phase. The Am was subsequently selectively stripped from the light lanthanides and Mo using mixed solution (DTPA, malonic acid and ammonium nitrate). As a result, Am was directly separated from the simulated HLLW with high yield (95%).

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