• Proceedings of the Korean Powder Metallurgy Institute Conference
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• 2000.04a
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• pp.20-20
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• 2000

• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.259-259
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.39-45
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• 1996

핵비확산 목적으로 원심분무방법으로 저농축 우라늄 고밀도의 U$_3$Si$_2$구형분말 분산핵연료를 개발하는 일환으로 융점이 높은 U$_3$Si$_2$원심분무용 도가니와 nozzle에 적합한 재료를 선정하고자 zirconia계 물질과 yttria물질에 대한 양립성을 시험하였다. ZrO$_2$계 세라믹은 U$_3$Si$_2$와 우수한 양립성을 나타냈는데 부분 안정화시킨 Zirconia가 Crack 발생이 없어 완전 안정화시킨 것보다 내열충격이 더 양호한 것으로 보인다. Zirconia 도가니는 흑연과 반응하여 표면에 carbide를 형성하여 박리 되는 현상이 발생되었는데 부분 안정화 zirconia가 약간 더 많이 형성됨을 나타냈다. Yttria는 180$0^{\circ}C$이상에서 흑연과 반응하여 액상으로 형성되고 U$_3$Si$_2$와도 반응하여 사용에 부적합한 것으로 판명되었다. 내열충격이 비교적 우수한 부분 안정화 zirconia로 tundish를 제조하여 U$_3$Si$_2$를 원심분무한 결과 nozzle확장되지 않아서 입도분포가 협소한 분말을 얻는데 성공하였다.

• Journal of Powder Materials
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• v.1 no.1
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• pp.72-78
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• 1994

Two kinds of $U_3Si$ powders and $U_3Si$ dispersed nuclear fuel meats have been prepared by conventional comminution process and a newly developed rotating disk atomization process. In contrast to angular shape and broad size distribution of the conventionally processed powder, the atomized powder was spherical and showed narrow size distribution. For the atomized powder, the heat treatment time for the formation of $U_3Si$ by a peritectoid reaction was reduced to about one tenth, thanks to microstructure refinement by rapid cooling of about 5$\times$104 K/s. The extruding pressure of atomized $U_3Si$ powder and Al powder mixture was lower than that of comminuted $U_3Si$ and Al powder mixture. The elongation of the atomization processed fuel meats was much higher than that of the comminution processed fuel meats and remained over 10% up to 80wt.% of $U_3Si$ powder fraction in the fuel meats. It appears therefore that the loading density of $U_3Si$ in fuel meat can be increased by using atomized $U_3Si$ powder. The atomized spherical particles were randomly distributed, while the comminuted particles with angular and longish shape were considerably aligned along the extrusion direction. Along the transverse direction of the extraction the electrical conductivity of the atomization processed fuel meats was appreciably higher than that of comminution processed fuel meats. This tendency became pronounced as $U_3Si$ content increased. Because the thermal conduction which is believed to be proportioned to the electrical conduction in the nuclear fuel meats occurs in radial direction, the atomization processed fuel can be better used in research reactors where high thermal conductivity is required.

• Nuclear Engineering and Technology
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• v.50 no.6
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• pp.899-906
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• 2018

The irradiation performance of $U_3Si$ dispersion fuel in an Al matrix, $U_3Si-Al$, under the Hi-Flux Advanced Neutron Application Reactor (HANARO) design full-power condition of 30 MW was tested for full-power qualification of the fuel. A test assembly was fabricated containing 18 fuel rods made with atomized $U_3Si$ powder manufactured at the Korea Atomic Energy Research Institute. The test assembly was irradiated for 188 full-power operation days in the HANARO subject to the normal fuel-loading scheme and achieved about 60 at% U-235 average burnup and 75 at% U-235 peak burnup. The maximum linear power of the test assembly was 98 kW/m. Nondestructive and destructive postirradiation examinations were conducted. The measured postirradiation examination data were compared with data from previous irradiations and the design criteria required for HANARO fuel. Consequently, it was concluded that in-pile performance was acceptable and fuel integrity was maintained, and the behavior satisfied the fuel design requirements.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.745-752
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• 1995

고연소도 액체금속로용 금속연료를 개발하고자 U-l0wt%Zr 합금중 Zr 원소 대신에 X(:Si, Ta, Nb, W, Mo) 원소를 첨가한 U-7wt%Zr-3wt%X(:Si, Ta, Nb, W, Mo) 합금을 제조하여 미세조직에 미치는 합금원소 첨가의 영향을 조사하였다. 그 결과 U-7 wt%Zr-3wt%Si 합금을 제외한 모든 U-7wt%Zr-3wt%X(:Ta, Nb, W, Mo) 합금은 Matrix에 있어서 Laminar Structure를 그대로 유지하였다. U-7wt%Zr-3wt%Si 함금을 제외한 모든 U-7wt%Zr-3wt%X(:Ta, Nb, W, Mo) 합금의 주요한 상은 U-l0wt% Zr 합금과 마찬가지로 $\alpha$-U 및 $\delta$-UZr$_2$ 상이었다. U-7wt%Zr-3wt%X(:Ta, Nb, W, Mo) 합금은 U-l0wt%Zr 합금에 비해 Lamina Thickness가 크게 감소되었다. 특히 U-7wt%Zr-3wt%Mo 합금의 경우에 있어서는 U-l0wt%Zr 합금에 비해 1/3배 정도까지 Lamina Thickness가 크게 감소하였다. 이와 같은 합금원소 첨가에 의한 Laminar Structure의 미세화는 액체금속로강 금속연료내 Fission Gas의 Inter-connected Path가 보다 더 잘 형성됨으로 인해 Fission Gas Bubble에 대한 방출속도를 크게 증가시켜서 궁극적으로는 Fission Gas Bubble에 의한 Swelling을 저감시킬 것으로 기대된다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.623-629
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• 1995

To investigate the effects of powder shape on U loading density of fuel meat, two kinds of fuel meats were prepared with atomized and comminuted U$_3$Si$_2$ powders by extrusion or rolling process. Extruded fuel meats with atomized spherical U$_3$Si$_2$ powder appeared to have much less porosity than those with comminuted irregular U$_3$Si$_2$ powder at higher U$_3$Si$_2$ fraction- The U$_3$Si$_2$ particles with spherical shape are less fractured in extrusion than in rolling. Most of atomized particles on the whole maintained to have spherical shapes in the extrusion. It has been shown that atomized spherical particles are expected to approach similar upper loading limits comparing with comminuted particles in rolled plates, but exceed comminuted powder loading limits in extruded rods.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.272.2-272
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• 2001

• Analytical Science and Technology
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• v.13 no.5
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• pp.584-591
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• 2000

The separation of Nd from the simulated $U_3Si/Al$ spent fuel solution with sequential two-step anion exchange separation has been studied. To prepare the simulated $U_3Si/Al$ spent nuclear fuel, unirradiated $U_3Si/Al$ whose composition consists of small $U_3Si$ particle dispersed in an Al matrix with Al cladding was dissolved with a mixture of 4 M HCl and 10 M $HNO_3$ and 8 or 15 fission product elements were added to the dissolved solution. The trace amount of silica in the solutions was removed by evaporating to dryness with HF and the U was adsorbed on the first anion exchange resin. Neodymium can be purely isolated from the fission product elements with a methanol-nitric acid eluent using the second anion exchange resin. A large excess of Al didn't influence on the elution velocity of Nd, but reduced the eluted contents of Nd, Al, Eu, Gd, Sm and Sr, A large amount of Al was removed first from the column with 3 mL of loading solution (0.8 M $HNO_3$/99.8% MeOH) before Nd elution by the eluent [0.04 M $HNO_3$-99.8% MeOH(1:9)]. The recovery of Nd was more than 94%, regardless of Al contents. Taking the 9 to 13 mL fraction of eluate was effective to purely isolate Nd.

• Journal of the Korean Magnetics Society
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• v.21 no.4
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• pp.127-131
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• 2011

In this paper, we study the electronic and magnetic properties of Cr substituted SiTe in the rock-salt structure compound using the full potential linearized augmented plane wave method within the generalized gradient approximation to the exchange correlation potential. Two stoichiometries are studied: $CrSi_3Te_4$ with 25 %, and $CrSiTe_2$ with 50 % Cr substitution. We found, from the total energy calculations, that the equilibrium lattice constant for cubic $CrSi_3Te_4$ is 11.64 a.u. and a = 7.89 a.u. and c = 11.13 a.u. for tetragonal $CrSiTe_2$. The integer value of the calculated magnetic moment per unit cell, $4{\mu}_B$ for $CrSiTe_2$ suggests that this compound is halfmetallic. The magnetic moment per unit cell for $CrSi_3Te_4$ is slightly larger than $4{\mu}_B$. The magnetic moment on Cr atoms are 3.61 and $3.62{\mu}_B$ in the $CrSi_3Te_4$ and $CrSiTe_2$, respectively. The presence of Cr atoms causes that the other atoms become slightly magnetized in both compounds. The electronic properties and the magnetism are discussed with the calculated spin-polarized density of states.