• Nuclear Engineering and Technology
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• v.52 no.6
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• pp.1120-1130
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• 2020

The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices. To analyze these experiments with accuracy an elaborate calculation scheme using the Monte Carlo method implemented in the MCNP6.1 code and the ENDF/B-VII.1 cross section library has been developed. We have used the ENDF/B-VII.1 data provided with the MCNP6.1.1 version in ACE format and the Makxsf utility to handle the data in the specific temperatures not available in the MCNP6.1.1 original library. The main purpose of this analysis is the qualification of the ENDF/B-VII.1 nuclear data for the prediction of the Reactivity Temperature Coefficient while ensuring the ability of the MCNP6.1 system to model such a complex experiment as CREOLE. We have analyzed the case of UO₂ lattice with 1166 ppm of boron in ordinary water moderator in specified temperatures. A detailed comparison of the calculated effective multiplication factors with the reference ones [1] in room temperature presented in this work shows a good agreement demonstrating the validation of our 3D calculation model. The discrepancies between calculations and the differential measurements of the Reactivity Temperature Coefficient for the analyzed configuration are relatively small: the maximum discrepancy doesn't exceed 1,1 pcm/℃. In addition to the analysis of direct differential measurements of the reactivity temperature coefficient performed in the poisoned UO₂ lattice configuration, we have also analyzed integral measurements in UO₂ clean lattice configuration using equivalency of the integral temperature reactivity worth with the driver core fuel reactivity worth and soluble boron reactivity worth. In this case both of the ENDF/B-VII.1 and JENDL.4 libraries were used in our analysis and the obtained results are very similar.

• Journal of Powder Materials
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• v.19 no.6
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• pp.398-404
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• 2012

This paper describes the spherical ammonium diuranate gel particles which are the intermediated material of the $UO_2$ microsphere for an VHTR(very high temperature reactor) nuclear fuel. The characteristics of the intermediate-ADU gel particles prepared by AWD(ageing, washing, and drying) and FB(fluidized-bed) apparatus were examined and compared in a sol-gel fabrication process. The electrical conductivity of washing filtrate from the FB treating and the surface area of dried-ADU gel particles were higher than those of AWD treating. Also, an internal pore volume in dried-ADU gel particles showed a more decrease in AWD treatment than FB treatment because of decomposition of PVA affected by the washing time. However, the internal microstructures of ADU gel particles were similar regardless of the process variation.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.02a
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• pp.60-63
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• 2004

Sulfurization of rare-earth oxides R203 (R=Nd, Eu) using sulfurizing reagents, such as $H_2S$ and $SC_2$was examined for the sulfide magnetic separation of spent fuel. $EU_2O_3$was found to react with H$_3$S gas forming the mixture of $EU_2O_2S$ and EuS at 500 oC, while EuS was formed by $SC_2$ at 800 oC. In the case of the mixture of $R_2O_3$and $UO_2$, EuS and $ND_3S_4$ were formed as well as $EU_2O_2S$ and $Nd_2O_2S$ at 500oC in $H_2S$, though $UO_2$ remained unreacted.

• Journal of the Korean Chemical Society
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• v.47 no.3
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• pp.199-205
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• 2003

Complexes of uranyl ion $UO^{+2}_2$with Schiff-bases obtained by condensing glycylglycine with salicylaldehyde; 2-hydroxy-1-naphthaldehyde, 2,3-dihydroxybenzaldehyde, and 2,4-dihydroxybenzaldehyde have been synthesized and characterized through elemental analysis, conductivity measurements, magnetic susceptibility determinations, u.v., i.r. and $^1H$ nmr spectra as well as d.t.a., t.g. and d.s.c. techniques. Structures and mechanisms of thermal decomposition are proposed.

• Nuclear Engineering and Technology
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• v.46 no.6
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• pp.863-868
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• 2014

The evaluation of thermal properties of actinide oxide fuels is a problem of high importance for the development of new generation reactors. In the present study, an expression obtained for n-dimensional Debye functions is used to derive a simple analytical expression for the specific heat capacity of nuclear fuels. To test the validity and reliability of this expression, the analytical expression is applied to $UO_2$, $NpO_2$, $ThO_2$, and $PuO_2$. It is seen that the formula was in agreement with the experimental and theoretical results reported in the literature.

• Journal of environmental and Sanitary engineering
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• v.11 no.1
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• pp.17-25
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• 1996

Resins with cryptand 22 macrocyclic ligand attached to chloromethylated styrene-1,4-divinylbenzene by substitution reaction were prepared and the effect of pH, metal concentration and cross-linkage of the matrix on the adsorption for $UO_2^{2+}$, $Cd^{2+}$ and $Sm^{3+}$ was investigated. The metal ion was not adsorbed on the resins pH range below 3 but above pH 4 fast adsorption behavior was showed. The resin selectivity determined in ethanol matrix was in increasing order $UO_2^{2+}{\;}>Cd^{2+}{\;}Sm^{3+}$. In addition, these metal ion could be separated on the column packed with 1% crosslinked resin by pH 2.5 $HNO_3$ as an eluent.

• Journal of environmental and Sanitary engineering
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• v.20 no.4 s.58
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• pp.38-44
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• 2005

Cryptand resins were synthesized with 1-aza-15-crown-5 macrocyclic ligand attached to styrene divinylbenzene (DVB) copolymer with crosslink of $1\%,\;2\%,\;5\%\;and\;10\%$ by substitution reaction. The synthesis of these resins was confirmed by content of chlorine, element analysis, and IR-spectrum. The effects of pH, time, dielectric constant of solvent and crosslink on adsorption of uranium$(UO_2^{2+})$ ion were investigated. The uranium ion was showed fast adsorption on the resins above pH 3. The optimum equilibrium time for adsorption of metallic ions was about two hours. The adsorption selectivity determined in ethanol was in increasing order uranium$(UO_2^{2+})$ > zinc$(Zn^{2+})$ > samarium$(Sm^{3+})$ ion. The adsorption was in order of $1\%>2\%>5\%>10\%$ crosslink resin and adsorption of resin decreased in proportion to order of dielectric constant of solvents.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.733-738
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• 1995

$UO_2$ 및 CeO$_2$ 분말을 turbular mixer에서 혼합, 또는 attritor mill에서 분쇄한 후, 각 분말의 특성변화와 이에 따른 소결특성의 변화를 관찰하였다. 혼합된 분말은 평균입자크기와 비표면적이 각각 22.9$\mu\textrm{m}$, 5.1g/㎤이었고, 2시간 분쇄된 분말은 0.5$\mu\textrm{m}$, 6.7g/㎤이었다. 혼합분말로 성형할 경우의 소결밀도는 성형압력의 증가에 관계없이 약 9.6 g/㎤로서 매우 낮았고, 2시간 분쇄된 분말은 10.35 9/㎤ 이상으로 나타나, 혼합핵연료 소결체 제조시 분쇄공정이 반드시 필요함을 나타내었다. 분쇄된 분말을 환원성분위기에서 소결할 경우에는 분쇄시간이 증가함에 따라 결정립이 8$\mu\textrm{m}$까지 증가하였는데 이것은 CeO$_2$ 분말의 미세화와 함께 Ce 성분이 균질 하게 분포되었기 때문으로 사료된다. 그러나 산화성분위기에서는 분쇄시간이 증가할 때 평균 결정립크기는 6$\mu\textrm{m}$로서 변화가 거의 없었다.

• Journal of the Korean institute of surface engineering
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• v.23 no.4
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• pp.225-229
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• 1990

Solubility Products of metal oxides, such as Al2O3 and UO2 in KCl-LiCl eutectic composition was calculated by using an exact an exact thermodynamic. The values for Al2O3 ThO2 and UO2 were found to be 2.51$\times$10-27, 4.97$\times$10-15and 2.17$\times$10-12in mole per liter basis at 743 K, respectively. The correlation of theoretical values with those of experiment were in good agreement. It is worth to note that the exact cycle method was proved to be satisfactory in making predictions of solubillities and also solubility products of sparingly soluble metal oxides in an ionic salt system.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.727-732
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• 1995

사용후핵연료 중간저장 시설의 누수사고시 예상되는 핵연료봉의 온도상승을 SFUEL 컴퓨터 코드 분석결과에 따른 실제 $UO_2$의 산화거동을 실험하였다. 외기 온도 38$^{\circ}C$에서 환기회수가 시간당 0, 1, 2회인 조건에서 저장용기 밑바닥 구멍 크기가 2.54, 5.08, 7.62 cm인 경우의 실험결과 환기회수 0회 바닥구멍 크기 2,54 cm 일 때 약 15시간 후 건전성 상실(0.6% 무게증가)이 일어났으며 환기회수 2회 바닥구멍 크기 7.62 cm 일 때는 약 21시간 이후에 건전성 상실이 일어나 가장 느렸다. 바닥구멍 크기가 증가할수록 공기 순환비의 영향을 크게 받으며, 또 외기 온도가 낮을 수록 공기 순환비의 영향을 크게 받았다.