• Nuclear Engineering and Technology
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• v.35 no.4
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• pp.299-308
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• 2003

Fabrication technique of $(Th,U)O_2$ pellets has been investigated. Powder mixtures of $ThO_2\;and\;UO_2$ were milled in two different ways-dry and wet milling. Milled powder was compacted and sintered to $(Th,U)O_2$ pellets. The wet-milled powder leads to a $(Th,U)O_2$ pellet having a high sintered density and uniform distribution of U and Th, compared to the dry-milled powder. The sintered density of a $(Th,U)O_2$ pellet tends to decrease by increasing the content of $ThO_2$. The thermal conductivity of $ThO_2\;and\;(Th,U)O_2$ pellets was measured by the laser flash method. The thermal conductivity of the $ThO_2$ pellet is higher than that of the $UO_2$ pellet, and the thermal conductivities of $(Th,U)O_2$ pellets containing $65wt\%\;and\;35wt\%\;ThO_2$ pellets are lower than that of the $UO_2$ pellet.

• The Korean Journal of Ceramics
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• v.4 no.3
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• pp.204-206
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• 1998

The Gibbs free energy of formation of $BaThO_3$ from elemental oxides has been measured at temperatures between 853 and 903 K using a $CaF_2$ solid electrolyte galvanic cell. The galvanic cell consisted of Pt, $O_2, CaO+CaF_2 \parallel CaF_2 \parallelBaThO_3+ThO_2+BaF_2, O_2$, Pt EMF gave the standard Gibbs free energy for the reaction $CaF_2+BaThO_3=CaO+BaF_2+ThO_3$ as $\DeltaG^o$,/TEX>=124111.031-117.597 T(J/mol).

• Bulletin of the Korean Chemical Society
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• v.11 no.4
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• pp.339-342
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• 1990

$Gd_2O_3-ThO_2$ solid solutions containing 8,10 and 12 mol % $ThO_2$ were synthesized with spectroscopically pure $Gd_2O_3,$ and $ThO_2$ polycrystalline powders. X-ray diffraction revealed that all synthesized specimens have the modified fluorite structure, and the lattice parameter of $Gd_2O_3$ is nearly unchanged with increasing $ThO_2$ mol %. Both ac and dc conductivities were measured in the temperature range $500-1100^{\circ}C$ under $Po_2's$ from $10^{-6}$ to $10^{-1}$ atm. The dc conductivities are nearly independent of $Po_2,$ and agree with the ac values. This implies that the solid solutions are ionic conductors. The conductivity increases with increasing $ThO_2$ mol % with an average activation energy of 1.23 eV. An oxygen interstitial defect and ionic hopping conduction are suggested.

• The Journal of Engineering Geology
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• v.32 no.2
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• pp.295-310
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• 2022

The Weolaksan and Sokrisan granites yield high SiO₂ and alkali (Na₂O+K₂O) contents and low CaO and P₂O₅ contents. The Al saturation index is ≥1.3, which indicates that the granites are peraluminous. The mean U and Th contents are 8.3 and 39.3 ppm, respectively, higher than typical Mesozoic granites in South Korea and about twice the global mean for granitic rocks. The causes of such high radioelement contents are related to high degrees of fractionation and the crustal origin of the granites. U- and Thbearing radioactive minerals occur in the granites include zircon, thorite, monazite, xenotime, fergusonite and uraninite. The fact that the mean Th/U ratio of the granites (5.4) is similar to the global average crustal value suggests that the radioelement contents of granite were controlled by the crustal source material. Given the correlation of Zr, Y, and heavy rare earth elements for U and Th, radioelements are more likely hosted by xenotime than zircon and monazite.

• Nuclear Engineering and Technology
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• v.52 no.6
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• pp.1099-1109
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• 2020

The performance of gadolinium burnable absorber (GdBA) for reactivity control in UO₂ and (U, Th)O₂ fuels and its impact on spent fuel characteristics was performed. Five fuel assemblies: one without GdBA fuel rod and four each containing 16, 24, 34 and 44 GdBA fuel rods in both fuels were investigated. Reactivity swing in all the FAs with GdBA rods in UO₂ fuel was higher than their counterparts with similar GdBA fuel rods in (U, Th)O₂ fuel. The excess reactivity in all FAs with (U, Th)O₂ fuel was higher than UO₂ fuel. At the end of single discharge burn-up (~ 49.64 GWd/tHM), the excess reactivity of (U, Th) O₂ fuel remained positive (16,000 pcm) while UO₂ fuel shows a negative value (-6,000 pcm), which suggest a longer discharge burn-up in (U, Th)O₂ fuel. The concentration of plutonium isotopes and minor actinides were significantly higher in UO₂ fuel than in (U, Th)O₂ fuel except for ²³⁶Np. However, the concentration of non-actinides (gadolinium and iodine isotopes) except for ¹³⁵Xe were respectively smaller in (U, Th)O₂ fuel than in UO₂ fuel but may be two times higher in (U, Th)O₂ fuel due to its potential longer discharge burn-up.

• Nuclear Engineering and Technology
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• v.53 no.7
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• pp.2418-2425
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• 2021

Monazite is a phosphate mineral that contains thorium (Th) and rare earth elements. The Th concentration in monazite can be as high as 500 ppm, and it has the potential to be used as fuel in the nuclear power system. Therefore, this study aimed to conduct the techno-economic analysis (TEA) of Th extraction in the form of thorium oxide (ThO₂) from monazite. Th can be extracted from monazite through an alkaline fusion method. The TEA of ThO₂ production studied parameters, including raw materials, equipment costs, total plant direct and indirect costs, and direct fixed capital cost. These parameters were calculated for the production of 0.5, 1, and 10 ton ThO₂ per batch. The TEA study revealed that the highest production cost was ascribed to installed equipment. Furthermore, the highest return on investment (ROI) of 21.92% was achieved for extraction of 1 ton/batch of ThO₂, with a payback time of 4.56 years. With further increase in ThO₂ production to 10 ton/batch, the ROI was decreased to 5.37%. This is mainly due to a significant increase in the total capital investment with increasing ThO₂ production scale. The minimum unit production cost was achieved for 1 ton ThO₂/batch equal to 335.79 $/Kg ThO₂.

• Proceedings of the Korean Environmental Sciences Society Conference
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• 2008.11a
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• pp.452-457
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• 2008

분말 TiO$_2$를 코팅한 전극은 전기저항으로 인해 0.5 A 이상의 전류를 인가할 수 없었으며, 1 A를 적용하였을 때 60분의 반응시간 후 최종 RhB 농도를 측정한 결과 Ru/Ti 전극의 RhB 농도 감소 가장 큰 것으로 나타났고, Ru/Ti > Ti > SG-TiO$_2$ > Th-TiO$_2$로 나타났다. 전기분해 공정만 적용한 경우 RhB 농도 감소의 순서는 Ru/Ti = Ti > SG-TiO$_2$ > Th-TiO$_2$ 전극의 순서로 나타났다. UV만 적용한 경우 RhB 제거는 작았으며, Ti와 Ru/Ti 전극은 UV만 적용한 경우와 RhB 제거농도가 비슷하였는데 이는 전극 표면에서 광촉매 반응이 일어나지 않는다는 것을 의미한다. 반면 TiO$_2$를 전극 표면에 형성하거나 코팅한 전극은 UV만 적용한 경우보다 RhB 농도가 낮게 나타났고, TiO$_2$가 형성되거나 코팅된 전극은 P-TiO$_2$ > Th-TiO$_2$ > SG-TiO$_2$의 순서로 나타났으나 차이는 크지 않았다. 광전기촉매 공정에서 시너지 효과가 거의 없는 것은 전극 표면에 코팅되거나 형성된 TiO$_2$의 양이 적고 광촉매 반응에 의한 분해 정도가 낮아 전자-정공의 재결합 감소효과가 적기 때문인 것으로 사료되었다. Th-TiO$_2$와 SG-TiO$_2$ 전극의 경우 전해질로 Na$_2$SO$_4$를 사용한 경우의 RhB 농도가 NaCl을 사용한 경우보다 RhB 낮게 나타났으나, Ti와 Ru/Ti 전극의 경우는 반대 현상이 나타났다. 이와 같은 결과는 광촉매 반응이 높은 Th-TiO$_2$와 SG-TiO$_2$ 전극에서의 Cl$^-$의 광촉매 반응 저해현상이 높게 나타났기 때문이라고 사료되었다. 반면 DSA 전극인 Ti와 Ru/Ti 전극의 경우 광촉매 반응이 거의 나타나지 않기 때문에 주반응인 전기분해 반응에서의 촉진 반응이 지배적이기 때문에 Th-TiO$_2$와 SG-TiO$_2$ 전극과는 정 반대의 현상이 나타났다고 사료되었다. 전기/UV 공정에서는 최적 전류는 0.75 A, NaCl 투입량은 0.5 g/L로 나타났으며, 최적 UV램프 전력은 16 W인 것으로 나타났다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.46-51
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• 1998

토륨핵연료를 이용한 플루토늄 소모에 대한 연구를 목적으로 조직된 IAEA CRP(Coordinated Research Program) 업무의 일환으로, 농축우라늄 및 플루토늄을 seed로한 토륨핵연료를 국내의 900MWe 가압경수로에 이용하였을 경우에 플루토늄을 비롯한 heavy isotope의 원소량 변화, 사용 후 핵연료로부터의 방사능 준위, 노심의 반응도 특성을 분석하여 혼합핵연료 노심과 비교하였다. (Th+Pu)O$_2$,는 혼합핵연료 보다 플루토늄의 소모량이 약 2.4배 많으며, fissile 플루토늄 원소의 존재비율은 10% 정도 더 감소하는 것으로 나타나 플루토늄 소모의 특성이 유리하고 핵비확산 성격이 강한 것으로 나타났다 사용후 핵연료의 방사능은, 핵연료가 노심에서 바로 인출된 시점에서 는 (Th+Pu)O$_2$,가 가장 낮으나, 그 이후로는 (Th+Pu)O$_2$와 혼합핵연료의 방사능은 비슷한 반면, (Th+U)O$_2$,의 방사능이 가장 낮은 것으로 나타나 장기적으로는 (Th+U)O$_2$가 가장 유리하다. 대략적인 전환비는 (Th+Pu)O$_2$노심이 약 0.56, (Th+U)O$_2$ 노심은 약 0.63, 혼합핵연료 노심은 약 0.61 정도로 추정되었다. 토륨핵연료의 연소도에 따른 반응도 변화, 가돌리니아봉의 중성자 횹수 성질 및 반응도 특성 등 노심특성은 seed 물질의 특성과 함량에 따라 좌우되는 것으로 나타났다.

• Journal of the Mineralogical Society of Korea
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• v.32 no.2
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• pp.127-143
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• 2019

The geology of the Chulmasan area consists of Precambrain Sogeunri formation, granitic gneiss, foliated biotite granite, foliated mica granite, basic dyke and acidic dyke. REE mineralization in the area occurs at granitic gneiss and foliated mica granite. Minerals with minor amounts of REE and Th from granitic gneiss and foliated mica granite are zircon ($Y_2O_3$ 0.00~1.18 wt.%, $Gd_2O_3$ 0.00~0.59 wt.%, $Er_2O_3$ 0.00~0.22 wt.%, $Yb_2O_3$ 0.00~0.34 wt.%, $Lu_2O_3$ 0.00~0.48 wt.%, $ThO_2$ 0.00~0.33 wt.%), thorianite ($Nd_2O_3$ 0.00~0.24 wt.%, $Lu_2O_3$ 0.00~0.26 wt.%), berthierine ($La_2O_3$ 0.04~0.26 wt.%, $Nd_2O_3$ 0.00~0.20 wt.%, $Tb_2O_3$ 0.04~0.12 wt.%, $Dy_2O_3$ 0.17~0.26 wt.%, $Er_2O_3$ 0.33~0.44 wt.%, $Lu_2O_3$ 0.00~0.19 wt.%, $ThO_2$ 0.61~0.93 wt.%), chlorite ($La_2O_3$ 0.44~0.68 wt.%, $Ce_2O_3$ 0.12~0.13 wt.%, $Nd_2O_3$ 0.31~0.44 wt.%, $Eu_2O_3$ 0.03~0.08 wt.%, $Dy_2O_3$ 0.09~0.21 wt.%, $Ho_2O_3$ 0.04~0.14 wt.%, $Er_2O_3$ 0.18~0.32 wt.%, $Lu_2O_3$ 0.07~0.21 wt.%, $ThO_2$ 0.00~0.97 wt.%), biotite ($Nd_2O_3$ 0.02~0.08 wt.%, $Gd_2O_3$ 0.07~0.08 wt.%, $Tb_2O_3$ 0.02~0.07 wt.%, $Dy_2O_3$ 0.35~0.43 wt.%, $Ho_2O_3$ 0.15~0.26 wt.%, $Er_2O_3$ 0.24~0.28 wt.%, $Yb_2O_3$ 0.06~0.18 wt.%, $ThO_2$ 0.00~0.12 wt.%), orthoclase ($Dy_2O_3$ 0.05~0.12 wt.%, $Ho_2O_3$ 0.05~0.06 wt.%, $Er_2O_3$ 0.28 wt.%, $Yb_2O_3$ 0.06~0.12 wt.%) and plagioclase ($Ho_2O_3$ 0.01~0.03 wt.%, $Er_2O_3$ 0.10~0.27 wt.%, $ThO_2$ 0.11~0.13 wt.%). REE minerals (bastnaesite and fergusonite) were sealed fractures in mainly fledspar, mica, zircon, apatite and ilmenite. Therefore, bastnaesite and fergusonite from the Chulmasan area were formed from redissolution/reconcentration of REE-and Th-bearing minerals from granitic gneiss and foliated mica granite at late stage by several igneous activies and metamorphism.

• Nuclear Engineering and Technology
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• v.47 no.3
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• pp.315-322
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• 2015

The research carried out on thorium-based fuels indicates that these fuels can be considered as economic alternatives with improved physical properties and proliferation resistance issues. In the current study, neutronic assessment of $UO_2$ in comparison with two $(Th-^{233}U)O_2$, and $(Th-^{235}U)O_2$ thorium-based fuel loads in a heavy water research reactor has been proposed. The obtained computational data showed both thorium-based fuels caused less negative temperature reactivity coefficients for the modeled research reactor in comparison with $UO_2$ fuel loading. By contrast, $^{235}U$-containing thorium-based fuel and $^{235}U$-containing thorium-based fuel loadings in the thermal core did not drastically reduce the effective delayed neutron fractions and delayed neutron fractions compared to $UO_2$ fuel. A provided higher conversion factor and lower transuranic production in the research core fed by the thorium-based fuels make the fuel favorable in achieving higher cycle length and less dangerous and costly nuclear disposals.