• Korean Journal of Materials Research
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• v.30 no.10
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• pp.533-541
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• 2020

UO₂ kernels, a key component of fuel elements for high temperature gas cooled reactors, have usually been prepared by sol-gel methods. Sol-gel processes have a number of advantages, such as simple processes and facilities, and higher sphericity and density. In this study, to produce 900 ㎛-sized UO₂ particles using an external gelation process, contact length extension of the NH₃ gas of the broth droplets pass and the improvement of the gelation device capable of spraying 14 M-NH₄OH solution are used to form 3,000 ㎛-sized liquid droplets. To produce high-sphericity and high-density UO₂ particles, HMTA, which promotes the gelation reaction in the uranium broth solution, is added to diffuse ammonium ions from the outside of the gelation solution during the aging process and generate ammonium ions from the inside of the ADU gel particles. Sufficient gelation inside of ADU gel particles is achieved, and the density of the UO₂ spheres that undergo the subsequent treatment is 10.78 g/㎤; the sphericity is analyzed and found to be 0.948, indicating good experimental results.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.2
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• pp.101-116
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• 2017

The interaction of U(VI) (hexavalent uranium) species with natural organic matter (NOM) in KURT (KAERI Underground Research Tunnel) groundwater is investigated using a laser spectroscopic technique. The luminescence spectra of the NOM are observed in the ultraviolet and blue wavelength regions by irradiating a laser beam at 266 nm in groundwater. The luminescence spectra of U(VI) species in groundwater containing uranium concentrations of $0.034-0.788mg{\cdot}L^{-1}$ are measured in the green-colored wavelength region. The luminescence characteristics (peak wavelengths and lifetime) of U(VI) in the groundwater agree well with those of $Ca_2UO_2(CO_3)_3(aq)$ in a standard solution prepared in a laboratory. The luminescence intensities of U(VI) in the groundwater are weaker than those of $Ca_2UO_2(CO_3)_3(aq)$ in the standard solution at the same uranium concentrations. The luminescence intensities of $Ca_2UO_2(CO_3)_3(aq)$ in the standard solution mixed with the groundwater are also weaker than those of $Ca_2UO_2(CO_3)_3(aq)$ in the standard solution at the same uranium concentrations. These results can be ascribed to calcium-U(VI)-carbonate species interacting with NOM and forming non-radiative U(VI) complexes in groundwater.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.158-163
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• 1996

Attritor mill로 분쇄처리된 $UO_2$-30mo1%CeO2$_2$(masterblend) 분말을 turbular mixer와 attritor mill 에서 $UO_2$와 혼합, $UO_2$-5mol%CeO$_2$ 분말을 만들고, 이를 통해 분말처리 및 소결분위기가 각 성형체의 소결거동에 미치는 영향을 연구하였다. $UO_2$-30mo1%CeO$_2$ 분말을 attritor mill로 1 시간동안 분쇄하면 평균 분말크기는 3.7 $\mu\textrm{m}$ 이었다. Turbular mixer에서 만들어진 $UO_2$-5mol%CeO$_2$ 분말이 H$_2$ 및 Ar-4%H$_2$ 분위기에서 소결되면, 분말처리 방법에 따라서 소결밀도는 각각 10.07-10.11, 9.81-9.85 g/㎤이었다. 이러한 방법으로는 masterblend 분쇄처리 과정에 만들어진 agglomerate 는 소결이 거의 이루어지지 않아서 소결체내에 그대로 잔존되었다. Agglomerate는 그 내부에 균열이 생성되어 있었고, 또한 $UO_2$ 지지내의 확산도 방해하여 기지내부에도 큰 기공들이 많이 분포하였다. 희석혼합을 turbular mixer 대신 attritor mill에서 하게되면, 밀도는 H$_2$ 및 Ar-4%H$_2$ 분위기에서 각각 10.54, 10.39 g/㎤ 이었으며, 결정립크기는 5, 9.5 $\mu\textrm{m}$ 이었다. 이 경우에는 소결체내에 agglomerate가 거의 잔존하지 않았다.

• Journal of the Korean Ceramic Society
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• v.34 no.7
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• pp.722-730
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• 1997

The nonstoichiometry (x) of UO2+x and (Er0.06U0.94)O2+x has been in-situ measure against oxygen activity (Po2) at elevated temperatures by a coulometric titration method. From the dependence of the oxygen excess (x) of UO2+x on Po2 at 1000℃, it has been concluded that (2Vo2Oia2Oib)〃〃and (2Vo2Oia2Oib)' clusters are prevailing at low oxygen partial pressure [log(Po2/atm) -10.6] and at high oxygen partial pressure [log(Po2/atm) -10.6], respectively. The nonstoichiometry is found to be reduced with the addition of Er, which is ascribed to the fact that the fixed-valent Er3+ reduces the oxidation capacities of UO2+x. The enthalpy of oxygen incorporation in (Er0.06li0.94)O2+x has been evaluated from the mean valences of U-ion as -180±70 kJ/mole.

• Journal of the Korean Ceramic Society
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• v.35 no.8
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• pp.783-790
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• 1998

The characterization of the complexation reaction of PVA and Al(III) ion at different pH and the sint-ering behaviour of UO2 containing the PVA-Al(III) complexes were investigated. Compared with pure PVA powder the complexed PVA-Al(III) powder had compacter shape and lower decomposition temperature The major phase of PVA-Al(III) complex decomposed at 90$0^{\circ}C$ was $\alpha$-Al2O3 The PVA-Al(III) complex formed at pH 9 had the lowest relative viscosity the highest Al content of 36% and the smallest particle size of 19${\mu}{\textrm}{m}$ While the pure UO2 pellet appeared with bimodal one. The grain size of the pure UO2 pellet was 7${\mu}{\textrm}{m}$ but that of the PVA-Al(III) complex added UO2 pellet was increased up to 36${\mu}{\textrm}{m}$ The largest grain size was ob-tained when the PVA-Al(III) complex formed at pH9 was added and the PVA-Al(III) complex formed at pH 11 had the greatest effect on increasing pore size.

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.223.1-223.1
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.264-264
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• 1998

• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.261-261
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.262-262
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.340.2-340.2
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• 2003