• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2016년도 추계학술논문요약집
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• pp.179-180
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• 2016

• 분석과학
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• 제25권2호
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• pp.146-151
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• 2012

액체섬광계수기를 이용한 지하수 내 우라늄 동위원소의 최적 측정방법에 대한 연구를 수행하였다. 용매추출법을 이용해 우라늄을 추출하였고, 시료량과 pH에 따른 추출효율을 조사하였다. 우라늄 추출효율에 미치는 영향을 조사하기 위해 표준용액을 사용하여 100 mL~1 L 범위에서 시료량을 변화 시켰으며 pH는 0.5~10 범위에서 측정하였다. 실험결과 우라늄의 추출효율은 pH에 매우 민감한 것으로 나타났으며 pH 2 에서 최고치를 나타냈다. 이에 반해 시료량은 추출효율에 큰 영향을 미치지 않는 것으로 나타났다. 우라늄 표준시료를 이용한 실험 결과 추출효율은 $95.93{\pm}0.77%$ 이었고, 계측시간 5시간을 기준으로 한 우라늄의 검출한계는 0.018 Bq/L 이었다. 본 연구결과로부터 지하수에 함유된 우라늄의 최적추출 및 측정법을 확립할 수 있었고 본 방법의 검증을 위해서 지하수 중 우라늄의 분석에 일반적으로 사용되는 ICP-MS 측정결과와의 비교분석도 함께 수행하였다. 본 연구에서 개발된 분석법을 대전 주변 지역 네 곳의 지하수를 대상으로 우라늄 함량 및 동위원소 비의 측정에 적용한 결과 우라늄의 농도는 0.59~6.69 Bq/L 그리고 $^{234}U/^{238}U$의 방사성 비는 0.88~1.40 범위로 나타내었다.

• 한국재료학회지
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• 제6권8호
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• pp.761-767
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• 1996

아미드옥심기와 복합재료 섬유흡착제를 제조하였고 해수로부터 우라늄이온의 분리 특성을 조사하였다. 흡착량은 흡착시간이 증가함에 따라 증가하였고 An:TEGMA:DVB의 몰비가 1:0.1:0.003인 수지가 pH 8 부근에서 최대 흡착능을 나타내었다. 또한 흡착량은 CFA에 첨가한 흡착제의 양이 증가함에 따라 증가하였으며 1시간 까지 선형적으로 증가하였고, $25^{\circ}C$에서 최대흡착량을 나타내었다. 한편 Ca, Mg 이온은 흡-탈착 cycle이 반복될수록 증가하였으며 그양은 각각 0.3, 0.9mmole/g-Ads로 우라늄 이온의 그것보다 매우 낮았다. 흡착된 우라늄 이온의 탈착은 흡착제의 종류에 관계없이 약 30분 이내에 거의 100% 탈착되었다.

• 대한기계학회논문집A
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• 제31권4호
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• pp.472-482
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• 2007

This study deals with the design and implementation results for a high-capacity vol-oxidizer that can convert Uranium Dioxide pellets to $U_3O_8$ powder for up to several tens of kg HM/batch. We developed two versions of the $1^{st}$ vol-oxidizer and the $2^{nd}$ vol-oxidizer. Through an experiment with the $1^{st}$ vol-oxidizer, we deduced some problems concerning the design considerations such as the recovery rate of $U_3O_8$, the oxidation time of the Uranium Dioxide pellets, the exothermic reaction, and the powder dispersion. From the analyses of the drawbacks of the $1^{st}$ vol-oxidizer, we devised some novel items such as a folding type mesh, vibrators, and mixing blades. Also, we used the Stokes and Density ratio Eq. to determine the most reasonable flux for preventing a powder dispersion. Compared with the results of the $1^{st}$ vol-oxidizer, we showed that both the permeability of the $U_3O_8$ powders and the oxidation rate of the Uranium Dioxide pellets of the $2^{nd}$ vol-oxidizer were remarkably increased, and the temperature of the reactor was controlled well in spite of an exothermic reaction. Also, the powder was not entirely dispersed through the outlet of the voloxidizer. The experimental results of this work can help in the design of a novel and efficient vol-oxidizer with a higher capacity.

• Nuclear Engineering and Technology
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• 제40권6호
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• pp.517-526
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• 2008

The widespread concern regarding the management of spent fuel that mainly contributes to nuclear waste has led to the development of the sodium-cooled fast reactor (SFR) as one of the most promising future types of reactors at both national and international levels. Various reactor deployment scenarios with SFR introductions with different conversion ratios in the existing PWR-dominant nuclear fleet have been assessed to optimize the SFR deployment strategy to replace PWRs with the view toward a reduction in the level of spent fuel as well as efficient uranium utilization through its reuse in a closed fuel cycle. An efficient reactor deployment strategy with the SFR introduction starting in 2040 has been drawn based on an SFR deployment strategy in which burners are deployed prior to breakeven reactors to reduce the amount of PWR spent fuel substantially at the early deployment stage. The PWR spent fuel disposal is reduced in this way by 98% and the cumulative uranium demand for PWRs to 2100 is projected to be 445 ktU, implying a uranium savings of 115 ktU. The SFR mix ratio in the nuclear fleet near the year 2100 is estimated to be approximately 35-40%. PWRs will remain as a main power reactor type until 2100 and SFRs will support waste minimization and fuel utilization.

• Mass Spectrometry Letters
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• 제7권2호
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• pp.50-54
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• 2016

Multi-collector inductively coupled plasma mass spectrometry (MC-ICP-MS) is currently used in our laboratory for isotopic and quantitative analyses of nuclear materials at ultra-trace levels in environmental swipe samples, which is a very useful for monitoring undeclared nuclear activities. In this study, to improve measurement precisions of uranium isotopes at ultratrace levels, we adopted a desolvating nebulizer system (Aridus-II, CETAC., USA), which can improve signal sensitivity and reduce formation of uranium hydride. A peristaltic pump was combined with Aridus-II in the sample introduction system of MC-ICP-MS to reduce long-term signal fluctuations by maintaining a constant flow rate of the sample solution. The signal sensitivity in the presence of Aridus-II was improved more than 10-fold and the formation ratio of UH/U decreased by 16- to 17- fold compared to a normal spray chamber. Long-term signal fluctuations were significantly reduced by using the peristaltic pump. Detailed optimizations and evaluations with uranium standards are also discussed in this paper.

• Nuclear Engineering and Technology
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• 제37권5호
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• pp.479-490
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• 2005

The thermalhydraulic performance of a CANDU-6 reactor loaded with various CANFLEX fuel bundles is evaluated by the NUCIRC code, which is incorporated with recent models of pressure drop and critical heat flux (CHF) predictions based on high-pressure steam-water tests for the CANFLEX bundle as well as a 37-element bundle. The distributions of channel flow rate, channel exit quality, critical channel power (CCP), and critical power ratio (CPR) for the CANFLEX bundles (with natural or recycled uranium fuel) in the CANDU-6 reactor fuel channel are calculated by the code. The effects of axial and radial heat flux on CCP are evaluated by assuming that the recycled uranium fuel (CANFLEX-RU) has the same geometric data as the natural uranium fuel bundle (CANFLEX-NU), but a different power distribution due to different fuel composition and refueling scheme. In addition, the effects of pressure tube creep and bearing-pad height are examined by comparing various results of uncrept, and $3.3\%\;and\;5.1\%$ crept channels loaded with CANFLEX bundles with 1.4 mm or 1.7 mm high bearing-pads with those of the 37-element bundle. The distributions of the channel flow rate and CCP for the CANFLEX-NU or -RU bundle show a typical trend for a CANDU-6 reactor channel, and the CPRs are maintained above at least 1.444 (NU) or 1.455 (RU) in the uncrept channel. The enhanced CHF of the CANFLEX bundle (particularly with 1.7mm height bearing-pads) produces a higher thermal margin and considerably less sensitivity to CCP reduction due to the pressure tube creep than the 37-element bundle. The CCP enhancement due to the raised bearing-pads is estimated to be about $3\%\~5\%$ for the CANFLEX-NU and $2\%\~6\%$ for the CANFLEX-RU bundle, respectively.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1372-1384
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• 2024

The discrimination of the source for xenon gases' release can provide an important clue for detecting the nuclear activities in the neighboring countries. In this paper, three machine learning techniques, which are logistic regression, support vector machine (SVM), and k-nearest neighbors (KNN), were applied to develop the predictive models for discriminating the source for xenon gases' release based on the xenon isotopic activity ratio data which were generated using the depletion codes, i.e., ORIGEN in SCALE 6.2 and Serpent, for the probable sources. The considered sources for the neighboring countries of South Korea include PWRs, CANDUs, IRT-2000, Yongbyun 5 MWe reactor, and nuclear tests with plutonium and uranium. The results of the analysis showed that the overall prediction accuracies of models with SVM and KNN using six inputs, all exceeded 90%. Particularly, the models based on SVM and KNN that used six or three xenon isotope activity ratios with three classification categories, namely reactor, plutonium bomb, and uranium bomb, had accuracy levels greater than 88%. The prediction performances demonstrate the applicability of machine learning algorithms to predict nuclear threat using ratios of xenon isotopic activity.

• 한국분말재료학회지
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• 제4권3호
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• pp.214-221
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• 1997

The densification and grain growth mechanisms of $UO_{2+x}$ in $H_2$ and in $CO_2$ have been investigated. Uranium dioxide powder compacts were sintered at 1$700^{\circ}C$ in $H_2$ or at 110$0^{\circ}C$ in $CO_2$ for various times from 0.5 h to 16 h. The grain size and density of the specimens were measured. From the measured data, the mechanisms of the densification and grain growth were determined by use of available kinetic equations which express the relations between densification and grain growth. In both atmospheres, it has been found that the densification was controlled by the lattice diffusion and the grain growth by the surface diffusion of atoms around pores. It appears that the surface diffusivity as well as the lattice diffusivity increase considerably with the increase in O/U ratio in the specimen.

• 공업화학
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• 제9권5호
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• pp.680-688
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• 1998

친수성 단량체 glycidylmethacrylate (GMA)에 가교제인 divinylbenzene (DVB)과 세공형성제인 2,2,4-trimethylpentane (TMP)량을 각각 0~10 mol %과 0~100 vol %로 변화시켜 현탁중합법으로 macroreticular (MR)형 GMA-DVB 공중합체 (RG라 칭함)을 합성하였다. 이들 공중합체를 벤젠 존재하에서 인산으로 인산화시켜 인산기를 갖는 거대망상형 양이온 교환수지 (macroreticular type cation exchange resins containing phosphoric acid groups, RGP)을 제조하였으며, 이들 수지에 대한 물성과 우라늄의 흡착능을 고찰하였다. RGP수지들의 물성은 합성시 가교도와 희석제량에 따라 영향이 있었으며, 우라늄의 흡착능은 가교도 영향인 경우 $$RGP-10(50){\sim_=}RGP-1(50)>RGP-2(50)>RGP-5(50)>RGP-0(50)$$ 이며, 희석제량의 영향인 경우는 RGP-2(100)>RGP-2(75)>RGP-2(50)>RGP-2(30)>RGP-2(0)순이였다. RGP수지들의 물성과 우라늄의 흡착능에서 가교도의 영향인 경우 RGP 수지의 세공구조, 양이온 교환 용량 및 팽윤비에 의존하며, 희석제량의 영향인 경우는 양이온 교환 용량보다도 비표면적과 세공구조에 더 영향이 있었다.