• 대한지하수환경학회지
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• 제5권4호
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• pp.210-214
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• 1998

담수나 해수와 같은 자연수중의 우라늄(U)의 농도는 0.0l∼5 ppb 수준으로서 극미량 원소분석법을 필요로 한다. 본 연구는 고감도의 비파괴법인 중성자방사화분석법을 이용하여 지하수중의 우라늄을 신속, 정확하게 정량할 수 있는 방법에 대하여 시료를 증발농축 전처리하는 방법과 직접 분석하는 방법을 비교 검토하였다. 표준용액(0.5∼100 ppb)을 이용하여 분석법을 검증하였다. 주어진 농도범위에서 검정곡선의 평균편차는 2% 이하를 나타냈으며, 각 측정값의 상대표준편차는 2∼l2% 이내이었다. 동일시료에 대한 시기별 농도의 편차는 10.3%이었다 본 방법을 이용하여 충청지역의 17개 관정으로부터 지하수시료를 채취하여 우라늄 농도를 정량한 결과 1 ppb에서 80 ppb수준인 것으로 확인되었다.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.523-529
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• 2023

Cemented uranium tailings backfill created from alkali-activated slag (CUTB) is an effective method of disposing of uranium tailings. Using some environmental functional minerals with ion exchange, adsorption, and solidification abilities as backfill modified materials may improve the leaching resistance of the CUTB. Natural zeolite, which has good ion exchange and adsorption characteristics, is selected as the backfill modified material, and it is added to the backfill materials with cementitious material proportions of 4%, 8%, 12%, and 16% to prepare CUTB mixtures with environmental functional minerals. After the addition of natural zeolite, the uniaxial compressive strength (UCS) of the CUTB decreases, but the leaching resistance of the CUTB increases. When the natural zeolite content is 12%, the UCS reaches the minimum value of 8.95 MPa, and the concentration of uranium in the leaching solution is 0.28-8.07 mg/L, the leaching rate R₄₂ is 9.61×10^-7 cm/d, and cumulative leaching fraction P₄₂ is 8.53×10^-4 cm, which shows that the alkali-activated slag cementitious material has a good curing effect on the CUTB, and the addition of environmental functional minerals helps to further improve the leaching resistance of the CUTB, but it reduces the UCS to an extent.

• 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.

• 환경위생공학
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• 제22권3호
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• pp.77-87
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• 2007

The ion exchange resins have been synthesized from chlormethyl styrene - 1,4 - divinylbenzene(DVB) with 1%, 3%, and 5%-crosslinking and macro cyclic ligand of OenNen-$H_4$ by copolymerization method and the adsorption characteristics of uranium(VI), iron(II) and samarium(III) metallic ions have been investigated in various experimental conditions. 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 metallic ions 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 ${UO_2}^{2+}>Fe^{2+}>Sm^{3+}$ ion. The adsorption was in order of 1%, 3%, and 5% crosslink resin and adsorption of resin decreased in proportion to order of dielectric constant of solvent.

• 환경위생공학
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• 제20권3호
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• pp.27-35
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• 2005

The ion exchange resins have been synthesized from chlormethyl styrene - 1,4 -divinyl-benzene(DVB) with $1\%,\;4\%,\;and\;10\%$-crosslinking and macrocyclic ligand of cryptand type by copolymerization method and the adsorption characteristics of uranium(VI), calcium(II) and lutetium(III) metallic ions have been investigated in various experimental conditions. 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 metallic ions 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 $(UO_2^{2+})>calcium(Ca^{2+})>lutetium(Lu^{3+})$ ion. The adsorption was order of $1\%,\;4\%,\;and\;10\%$ crosslink resin and adsorption of resin decreased in proportion to order of dielectric constant of solvents.

• 폴리머
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• 제24권2호
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• pp.174-181
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• 2000

방사선 전조사법을 이용하여 아크릴로니트릴을 ACF/PP 복합섬유에 그라프트 반응시켜 섬유형 ACF/PP-g-AN 공중합체를 합성하였다. 합성한 공중합체의 FT-lR 결과 2250$cm^{-1}$ / 부근에서 -C=N에 대한 피크, 3450$cm^{-1}$ / 부근에서 -OH와 -NH$_2$에 의한 피크 확인으로 그라프트 반응 및 아미드옥심화 반응을 확인할 수 있었다. 아미드옥심화된 ACF/PP-g-AN 공중합체의 우라늄 이온에 대한 흡착능의 최적시간은 8일이었으며, 최적 pH는 8이었다. 동일 조건하에서의 흡착능은 아미드옥심기의 함량이 증가할수록, 그라프트율이 116.3%일 때 최대 흡착능을 나타내었다. 또한 ACF/PP-g-AN 공중합체는 10회 이상 흡착능의 변화없이 흡탈착이 가능한 홉착제임을 알 수 있었다.

• 한국수소및신에너지학회논문집
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• 제27권2호
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• pp.163-168
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• 2016

Korea has been developing nuclear fusion fuel storage and delivery system (SDS) technologies including a basic scientific study on hydrogen storage. To develop nuclear fusion technology, it is necessary to store and supply hydrogen isotopes needed for Tokamak operation. SDS is used for storing hydrogen isotopes as a metal hydride form. The rapid hydriding of tritium is very important not only for safety reasons but also for the economic design and operation of the SDS. In this study, we designed and fabricated a medium-scale getter bed of depleted uranium (DU). The hydriding of DU has been measured by varying the initial temperature ($100-300^{\circ}C$) of the DU getter bed to investigate the influence of the cooling temperature. Furthermore, we analyzed the effect of a helium blanket on the hydriding performance with 0 - 12% helium content in hydrogen.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2660-2669
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• 2022

The attractiveness for weapons usage of the proposed fuel cycle for the PT-SCWR was evaluated in this study using the Figure-of-Merit methodology. It was compared to the attractiveness of other fuel cycles namely, Low Enriched Uranium (LEU), U/Th, Re-enriched Reprocessed Uranium (RepU), and Pu/Th/U. The optimal content of natural uranium, which can be added to Pu/Th to render the produced U-233 unattractive, was found to be 9%. A ranking system to compare the attractiveness of the various fuel cycles is proposed. RepU was found to be the most proliferation resistant fuel cycle for the first 100 years,while, the least proliferation resistant fuel cycle was the originally proposed Pu/Th one. The reactivity feedback coefficients were calculated for all proposed fuel cycles. All studied reactivity coefficients have the same sign implying that all the fuel cycles will behave neutronically in a similar way. The Pu/Th/U fuel was found to have the most negative value of the Coolant Void Reactivity which will help to restore the core to a safe status faster in case of a loss-of-coolant accident. The fuel and moderator temperature coefficients did not show significant differences between the fuels studied.

• Nuclear Engineering and Technology
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• 제43권4호
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• pp.391-398
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• 2011

The U metal chips generated in developing nuclear fuel and a gamma radioisotope shield have been stored under immersion of water in KAERI. When the water of the storing vessels vaporizes or drains due to unexpected leaking, the U metal chips are able to open to air. A new oxidation treatment process was raised for a long time safe storage with concepts of drying under vacuum, evaporating the containing water and organic material with elevating temperature, and oxidizing the uranium metal chips at an appropriate high temperature under conditions of controlling the feeding rate of oxygen gas. In order to optimize the oxidation process the uranium metal chips were completely dried at higher temperature than $300^{\circ}C$ and tested for oxidation at various temperatures, which are $300^{\circ}C$, $400^{\circ}C$, and $500^{\circ}C$. When the oxidation temperature was $400^{\circ}C$, the oxidized sample for 7 hours showed a temperature rise of $60^{\circ}C$ in the self-ignition test. But the oxidized sample for 14 hours revealed a slight temperature rise of $7^{\circ}C$ representing a stable behavior in the self-ignition test. When the temperature was $500^{\circ}C$, the shorter oxidation for 7 hours appeared to be enough because the self-ignition test represented no temperature rise. By using several chemical analyses such as carbon content determination, X-ray deflection (XRD), Infrared spectra (IR) and Thermal gravimetric analysis (TGA) on the oxidation treated samples, the results of self-ignition test of new oxidation treatment process for U metal chip were interpreted and supported.

• 대한화학회지
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• 제38권7호
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• pp.502-508
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• 1994

염의 농도가 큰 시료용액중에 미량으로 함유되어 있는 U(VI)과 Th(VI)을 액상크로마토그래피로 동시에 분리, 정량하였다. 약 2ml의 시료를 pH5.5의 0.11M ${\alpha}$-HIBA 용리액과 함께 C_{18}$ 역상농축컬럼에 통과시켜 U(VI)과 Th(VI)을 농축시켰으며, 농축된 이들 원소들을 다시 비활성 C_{18}$ 역상분리컬럼에서 pH3.0의 0.17M ${\alpha}$-HIBA/0.0038 M 1-pentanesulfonate 용리액으로 각각 분리하였다. 분리된 이들 원소들은 Arsenazo III를 사용하는 postcolumn반응으로 검출되었으며, 검출한계는 두 원서 모두 1ppb이었다.