• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.2
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• pp.77-85
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• 2012

This study was carried out to remove (/recover) the uranium from the Uranium-bearing Lime Precipitate (ULP). An oxidative dissolution of ULP with carbonate-acidified precipitation and a dissolution of ULP with nitric acid-hydrogen peroxide precipitation were discussed, respectively. In point of view the dissolution of uranium in ULP, nitric acid dissolution which could dissolved more than 98% of uranium was more effective than carbonate dissolution. However, in this case, uranium was dissolved together with a large amount of impurities such as Al, Ca, Fe, Mg, Si, etc. and some impurities were also co-precipitated with uranium during a hydrogen peroxide precipitation. On the other hand, in the case of carbonate dissolution-acidified precipitation, U was dissolved less than 90%. Therefore, it was less effective than nitric acid dissolution for the volume reduction of radioactive solid waste. However, it was very effective to recover the pure uranium, because impurities were hardly dissolved and hardly co-precipitated with uranium.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.2
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• pp.85-93
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• 2013

This study has been carried out to elucidate the characteristics of the dissolution for Thermal Decomposed Solid Waste of uranium-bearing sludge (TDSW), the removal of impurities by an alkalization in a nitric acid dissolving solution of TDSW, and the selective removal (/recovery) of uranium by an acidification in an carbonate alkali solution, respectively. TDSW generated by thermal decomposition of U-bearing sludge which was produced in the uranium conversion plant operation, was stored in KAERI as a solid-powder type. It is found that the dissolution of TDSW is more effective in nitric acid dissolution than oxidative-dissolution with carbonate. At 1 M nitric acid solution, TDSW was undissolved about 30wt% as a solid residue, and uranium contained in TDSW was dissolved more than 99%. In order to the alkalization for the nitric acid dissolving solution of TDSW, carbonate alkalization is more effective with respect to remove the impurities. At the carbonate alkali solution controlled to about 9 of pH, Al, Ca, Fe and Zn co-dissolved with U in dissolution step was removed about $98{\pm}1%$. On the other hand, U could be recovered more than 99% by an acidification at pH about 3 in a carbonate alkali solution, which was nearly removed the impurities, adding 0.5M $H_2O_2$. It was found that uranium could be selectively recovered (/removed) from TDSW.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.232-232
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• 2004

우라늄 변환시설 내의 라군 슬러지의 처리를 위해 슬러지의 물 첨가 용해를 실시하고, 여과후 발생한 질산염의 안정적 처리를 위한 열분해를 실시하였다. 라군 슬러지의 질산염 및 우라늄 제거공정은 후속처리공정에서의 부담을 최소화 할 수 있도록 1.5배의 물을 첨가 용해하였으며, 두 개의 라군에 저장된 슬러지 처리방법의 효율성 평가를 위하여 각 라군의 개별적, 혹은 혼합하여 실험을 실시하였다.(중략)

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.455.1-455
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• 2001

• Applied Chemistry for Engineering
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• v.9 no.3
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• pp.388-393
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• 1998

The effects of surface area of $UO_2$ pellets($s:0.034{\sim}0.282cm^2/g-UO_2$), concentration of nitric acid(1.5~10N) and temperature($40{\sim}105^{\circ}C$) on the dissolution rate were investigated in this experiment. The results showed that dissolution rate of $UO_2$ pellets was in direct proportion to effective surface area(s) and well fit to linear plot in high surface area. The dissolution rate was expressed as dc/dt = 10.6s at $90^{\circ}C$, [$HNO_3$]=8N, and proportioned to the power 1.42 of $HNO_3$ concentration. And also, the results showed that dissolution rate was sharply increased according to temperature increase in temperature below $90^{\circ}C$, but decreased in temperature above $90^{\circ}C$. Activation energy(E) was evaluated to be 36.3KJ/mol.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.05a
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• pp.207-208
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• 2011

• Journal of the Korea Academia-Industrial cooperation Society
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• v.6 no.2
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• pp.116-121
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• 2005

Immobilization technique by PVA encapsulation is an effective alternative for wastewater treatment. However little information is available about the effect of PVA characteristics on physical properties as an encapsulation media. This study aims at investigating the effect of the preparation methods of PVA and filler addition to media on the solubility of PVA. The solubility decreased as the freezing temperature decreased and the vacuum-drying was applied. Addition of the PAC (Powered Activated Carbon) and organoclay decreased the solubility of the PVA gels. Organoclay was more effective for lowering the solubility about 25% than the PAC. Nitrification with the PVA-coating media was less sufficient than with the polyurethane media due to the mass transfer restriction for oxygen and nutrients.

• Journal of Sericultural and Entomological Science
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• v.51 no.1
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• pp.15-19
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• 2013

Antheraea pernyi silkworm is one of typical wild silkworms, which spins a tawny color cocoon. The cocoon has been used as a resource for textile material due to strong chemical stability and good mechanical properties. In this study, to increase the solubility efficiency of A. pernyi silk fibroin, the composition of dissolution solvent were examined. Calcium chloride tertiary system, normally used for dissolution of Bombyx mori silk fibroin, does not act on A. pernyi silk fibroin. Calcium nitrate system dissolves A. pernyi silk fibroin, and calcium nitrate ethanol system do more easily than calcium nitrate system. Amino acid composition of A. pernyi silk fibroin obtained after dissolution is mainly composed of alanine, glycine, and serine. A. pernyi silk fibroin would be used for non-textile applications near future.

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 2014.11a
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• pp.89-90
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• 2014

인쇄회로기판 패턴도금 박리공정 중 발생하는 폐솔더 박리액은 주석, 구리, 철, 납 등 유가금속이 함유된 질산계 폐액이다. 본 연구에서는 이러한 폐솔더 박리액에서 질산과 유가금속을 체계적으로 회수하는 기술을 개발하고자 하였다. 먼저 폐액을 $80^{\circ}C$에서 3시간 정도 반응시켜 주석을 $SnO_2$ 상태로 90% 이상 회수가 가능하였다. 주석이 회수되고 구리, 철, 납만이 존재하는 질산계 폐솔더 박리액에서 확산투석을 이용하여 질산을 94% 이상 회수가 가능하였고 회수된 질산의 농도는 5.1 N 이었다. 질산을 추출한 폐액에서 침전제로 옥살산(Oxalic acid)을 사용하여 구리를 구리옥살레이트 상태로 침전시켜 타금속이온과 선택적으로 분리하였다. 마지막으로 폐액 중 용해되어있는 납을 $65^{\circ}C$이상에서 철 스크랩을 이용한 세멘테이션을 통하여 회수하였다.

• Resources Recycling
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• v.20 no.6
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• pp.56-62
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• 2011

Zirconium is used in nuclear reactors as a structural material due to its excellent corrosion resistance and to low neutron crosssection. Variation in the distribution and solubility of Zr(IV) with solution pH was obtained. Distribution of Zr(IV) containing species in HCl and $HNO_3$ solution was analyzed by considering the complex formation of Zr(IV) species with the anion of the inorganic acid. Bromley interaction parameter between $ZrO^{2+}$ and nitrate ion was estimated by using the reported data on the solvent extraction of Zr(IV) by Cyanex272 from $HNO_3$ solution. This Bromley parameter can be utilized in calculating extraction isotherm of Zr(IV) and in predicting the separation factor between Zr(IV) and Hf(IV).