• Journal of the Korean Ceramic Society
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• v.39 no.2
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• pp.204-209
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• 2002

In this study, $UO_4{\cdot}2NH_4F$, the precipitates which has low solubility, was obtained by chemical precipitation method to recover and reuse the trace uranium from the liquid waste producing in AUC process and for this compound it was characterized by means of chemical analysis, TG-DTA, XRD and FT-IR analyses. This compound was analyzed as $UO_4{\cdot}2NH_4F$ and shape of this precipitate was hexagonal type, having the size of 2∼3 ${\mu}m$. Also, the intermediates were obtained as $UO_4F,\;UO_4,\;UO_3,\;and\;U_3O_8$ by the thermal decomposition over the temperature of 220, 310, 515 and 640$^{\circ}C$, respectively. It is concluded that under the condition of a constant heating rate of 5$^{\circ}C$/min in air atmosphere range of between room temperature and 800$^{\circ}C$, thermal decomposition reaction mechanism of $UO_4{\cdot}2NH_4F$ is as follow; $UO_4{\cdot}2NH_4F{\rightarrow}UO_4F{\rightarrow}UO_4{\rightarrow}UO_3{\rightarrow}U_3O_8$.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.668-673
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• 1995

$UO_2$-CeO$_2$ 모의혼합분말에 첨가제를 미량 첨가하여 소결체의 미세구조 변화를 $UO_2$분말의 경우와 비교, 관찰하였다. 소결 첨가제로서 Ta, Ti 및 Nb를 사용하였으며, 이들을 미세한 산화물의 형태로 $UO_2$ 및 $UO_2$-CeO$_2$에 첨가하여 환원성 및 산화성 분위기에서 각각 소결하였다. Ta, Ti 및 Nb는 환원소결에서 $UO_2$의 결정립을 성장시켰으나 산화소결에서는 첨가효과가 크게 나타나지 않았다. $UO_2$-0.lw%TiO$_2$와 $UO_2$-0.6w%Ta$_2$O$_{5}$의 환원소결체에서 eutectic phase가 관찰되었으나 산화소결체에서는 나타나지 않았다. $UO_2$-4wt%CeO$_2$의 환원소결에서는 Ti만이 결정립성장에 기여하는 것으로 나타났으며 Ta, Nb와 같이 $UO_2$에 치환형으로 고유되는 원소는 Ce 이온과 Cluster를 형성함으로 결정립성장에 거의 기여하지 못하고, Ti와 같이 UO2$_2$ 침입형으로 고용되는 원소는 일부가 인접한 Ce$_{U}$' 이온과 cluster를 형성하더라도 나머지가 V$_{U}$'의 형성에 기여하므로서 결정립을 성장시킬 수 있다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.46-51
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• 1996

본 연구는 MDD(modified direct denitration)공정의 주 우라늄염인 암노늄 우라닐 나이트레이트의 화학특성을 밝히고 이들 화합물의 열분해 및 환원반응의 반응기구에 대하여 조사되었다. 암모늄 우라닐 나이트레이트는 제조 조건에 따라 N $H_4$$UO_2$N $O_3$와 (N $H_4$)$_2$$UO_2$(N $O_3$)$_4$.2$H_2O$의 두가지 형태의 복염으로 존재함이 화학 및 원소분석, X산 회절 분석, 그리고 적외선 분광분석에 의하여 확인되었다. 암모늄 우라닐 나이트레이트는 질소분위기에서 N $H_4$$UO_2$(N $O_3$)$_3$$\longrightarrow$ Amorphous $UO_3$$\longrightarrow$ a-$UO_3$$\longrightarrow$ U$_3$ $O_{8}$$\longrightarrow$ $\alpha$-U$_3$ $O_{8}$의 경로를 따라서 열분해 되며, 수소분위기에서는 N $H_4$$UO_2$(N $O_3$)$_3$$\longrightarrow$ $UO_3$$\longrightarrow$ U$_3$ $O_{8}$$\longrightarrow$ U$_4$ $O_{9}$ $\longrightarrow$ $UO_2$의 경로로 환원되었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.74-79
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• 1997

$UO_2$ 및 $UO_2$-3.23wt%CeO$_2$가 128$0^{\circ}C$에서 소결되면 밀도는 각각 93%T.D., 91.2%T.D.이었으나, Li$_2$O가 0.lwt%씩 첨가된 경우에는 소결밀도가 95.5%T.D., 95.1%T.D.로 증가하였다. 소결온도가 증가함에 따라서 $UO_2$ 및 $UO_2$-3.23wt%CeO$_2$의 소결밀도는 현저하게 증가되는 반면에, Li$_2$O가 첨가된 경우에는 저온에서도 이미 치밀화가 많이 일어났기 때문에 소결밀도의 증가폭이 완만하였다. Li$_2$O가 첨가된 분말에서는 소결온도가 더 높아지면, 결정립성장이 주로 일어나게 되어 168$0^{\circ}C$에서 소결되었을 때, $UO_2$와 $UO_2$-0.1wt%Li$_2$O의 결정립크기가 각각 8.7$\mu\textrm{m}$, 120$\mu\textrm{m}$ 이고, $UO_2$-3.23wt%CeO$_2$와 $UO_2$-3.23wt%CeO$_2$-0.lwt%Li$_2$O는 각각 10.9$\mu\textrm{m}$, 34$\mu\textrm{m}$ 이었다. $UO_2$와 $UO_2$-3.23wt%CeO$_2$ 그리고, 두 조성에 Li$_2$O가 각각 첨가된 경우, Ar-4vol.%H$_2$ 분위기보다 H$_2$분위기에서 소결했을 때 밀도가 더 높았다. 그러나, 결정립은 $UO_2$와 $UO_2$-Li$_2$O의 경우, 수소분위기에서 소결했을 때, (U,Ce)O$_2$와 (U,Ce)O$_2$-Li$_2$O에서는 Ar-4vol.%H$_2$분위기에서 소결했을 때 더욱 성장하였다.

• Nuclear Engineering and Technology
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• v.30 no.2
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• pp.128-139
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• 1998

The effect of UO$_2$ powder property and oxygen potential on characteristics of sintered UO$_2$-Gd$_2$O$_3$ fuel pellets has been investigated. Two types of powder, mixture of AUC-UO$_2$ and Gd$_2$O$_3$powders (type I) and mixture of ADU-UO$_2$ and Gd$_2$O$_3$powders (type II), have been prepared, pressed, and sintered at 168$0^{\circ}C$ for 4 hours. Four sintering atmospheres with different mixing ratios of $CO_2$to H$_2$ gas ranging from 0 to 0.3 have been used. UO$_2$-Gd$_2$O$_3$ fuel has lower sintered density than UO$_2$ fuel, and the density drop is larger for powder type I than for powder type II. As the oxygen potential increases, the sintered density of UO$_2$-2wt% Gd$_2$O$_3$pellets increases but that of UO$_2$-10wt% Gd$_2$O$_3$ pellets decreases. It is found that pores are newly formed in UO$_2$-10wt% Gd$_2$O$_3$ pellets in accordance with the decrease in density. The grain size of UO$_2$-Gd$_2$O$_3$ fuel increases and a short range G4 distribution becomes homogeneous as the oxygen potential increases. A long range ed distribution and grain structure are inhomogeneous for powder type II. The lattice parameter of (U,Gd)O$_2$solid solution decreases linearly with Gd$_2$O$_3$ content. The dependence of UO$_2$-Gd$_2$O$_3$fuel characteristics on powder type and sintering atmosphere have been discussed.

• Journal of the Korean Chemical Society
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• v.29 no.2
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• pp.121-128
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• 1985

The electrochemical reduction of uranyl ion in aqueous basic media has been examined by d. c. polarography, differential pulsed polarography and cyclic voltammetry. From voltammograms obtained in uranyl solutions containing 0.1M sodium bicarbonate, either with or without the same amounts of sodium tripolyphosphate it is concluded that the first wave corresponds to the reduction of $UO_2^{2+}$ to $UO_2^+$. It is assumed that the uranyl ion undergoes appreciable hydrolysis in these media. The hydrolysis product $UO_2OH^+$ from $UO_2^{2+}$ is not reduced at the first wave, but is reduced at the second wave together with $UO_2^+$. The diffusion current was found proportional to the uranyl concentration in a range between $7.5 {\times} 10^{-4}$ and $3.75 {\times}10^{-3}$M.

• Journal of the Korea Institute of Information and Communication Engineering
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• v.12 no.6
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• pp.1128-1133
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• 2008

Context-aware computing has been attracting the attention as an approach to alleviating the inconvenience in human-computer interactions. This paper proposes a context-aware system architecture to be implemented on an UoC (Ubiquitous system on Chip). A new proposed technology of CRS (Context Recognition Switch) and DOS (Dynamic and Optimal Standard) based on Context-awareness system architecture with pre-processor, HPSP(High Performance Signal Processor) in this paper. And proposed a new algorithm using in network topology processor shows for Ubiquitous Computing System. implementing in UoC (Ubiquitous System on Chip) base on the IEEE 802.15.4 WPAN (Wireless Personal Area Network) standard. Also, This context-aware based UoC architecture has been developed to apply to mobile intelligent robots which would support human in a context-aware manner.

• Nuclear Engineering and Technology
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• v.31 no.6
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• pp.608-617
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• 1999

The powder mixture which has a bimodal size distribution, with a large mode corresponding to AUC-UO$_2$ powder and a small one corresponding to ADU-UO$_2$ powder, was prepared, pressed into compacts, and sintered at 1680t for 4 hours in hydrogen gas. The compact density of the powder mixture increases with increasing ADU-UO$_2$content within a content of 20 wt %, since small ADU-UO$_2$ particles can fill interstices between large AUC-UO$_2$particles. The UO$_2$ pellet made using the powder mixture has a lower open porosity than that made using AUC-UO$_2$ powder alone. The mechanism for the formation of a flake-like pore is proposed, and the decrease in open porosity may be ascribed to the decrease in the number of flake-like pores.

• Nuclear Engineering and Technology
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• v.36 no.1
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• pp.104-111
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• 2004

The melting temperatures of $UO_2,\;UO_2-6wt\%Gd_{2}O_3,\;UO_2-12wt\%Gd_{2}O_3,\;UO_2-2wt\%Er_{2}O_3,\;and\;UO_2-4wt\%Er_{2}O_3$ fuels were measured. Fuel materials were loaded in a tungsten capsule of which shape met the black body condition. The melting temperature was measured by the thermal arrest method during heating of the capsule in an induction furnace. The measured melting temperature of $UO_2$ fuel was $2815{\pm}20^{\circ}C$. The solidus and liquidus temperatures of $UO_2-Gd_{2}O_3\;and\;UO_2-Er_{2}O_3$ had also been measured, and it was observed that the solidus temperatures of them were lower than the liquidus temperature by $15{\sim}25^{\circ}C$. Measured melting temperatures of $UO_2,\;UO_2-Gd_{2}O_3\;and\;UO_2-Er_{2}O_3$ fuels were as follows:

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.739-744
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• 1996

The U solubility in the Zircaloy melt including the other investigators' result was investigated in a range of reaction temperatures from 2223k to 2473k and for the mole ratios of UO$_2$ crucible/Zircaloy-4 melt(subsequently abbreviated as UO$_2$/Zry) from 2.4 to 18.2, The U solubility in the melt increased with increasing reaction temperature and with decreasing the mole ratio of UO$_2$/Zry. An empirical correlation was obtained as functions of UO$_2$/Zry mole ratio and reaction temperature including other investigators' results. The experimental results with use of internally heated fuel element simulators were analyzed by the empirical correlation from UO$_2$ crucible experiments.