• 멤브레인
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• 제13권3호
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• pp.154-161
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• 2003

본 연구에서는 소수성 PTFE (Polytetrafluoroethylene) 분리막의 산소동위원소 분리특성을 확인하기 위해 물의 온도에 따른 수증기의 막 투과특성을 Air Cap Membrane Distillation (AGMD)과 Vacuum Enhanced Membrane Distillation (VEMD) 방법을 이용하여 각각 측정하였다. 투과된 수증기는 트랩에서 수거하여 투과플럭스 (permeation flux)를 측정하였고$ H_2^{16}O$와 $H_2^{18}O$의 성분비는 다이오드 레이저 흡수분광법을 이용하여 측정하였다. 분리막을 투과한 수증기에서 무거운 산소동위원소의 성분비가 감소함을 확인하였고 분리계수는 실험 조건에 따라 1.004~1.01로 측정되었다. 또한 분리막의 기공에 있는 공기가 산소동위원소의 분리에 미치는 영향을 확인하였고 기공내 공기가 없을 때 동위원소 분리계수가 증가함을 관찰하였다.

• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3291-3300
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• 2023

Recently molybdenum alloys have been introduced as accident tolerating materials for cladding of fuel rods. Molybdenum element has seven stable isotopes with different neutron absorption cross section used in various fields, including nuclear physics and radioisotope production. This study presents separation approaches for all intermediate isotopes of molybdenum element by squared-off cascades using a newly developed numerical code with Salp Swarm Algorithm (SSA) optimization algorithm. The parameters of cascade including feed flow rate, feed entry stage, cascade cut, input feed flow rate to gas centrifuges (GCs), and cut of the first stage are optimized to maximize both isotope recovery and cascade capacity. The squared off and squared cascades are studied, and the efficiencies are compared. The results obtained from the optimization showed that for the selected squared off cascade, Mo⁹⁴ in four separation steps, Mo⁹⁵ in five steps, Mo⁹⁶ in six steps, Mo⁹⁷ in seven steps, and Mo⁹⁸ in two steps are separated to the desired concentrations. The highest recovery factor is obtained 63% for Mo⁹⁴ separation and lowest recovery factor is found 45% for Mo⁹⁵.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.719-726
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• 2016

The problem of separation of isotopes in a concurrent gas centrifuge is solved analytically for an arbitrary binary mixture of isotopes. The separative power of the optimised concurrent gas centrifuges for the uranium isotopes equals to ${\delta}U=12.7(V/700m/s)^2(300K/T)(L/1m)kg{\cdot}SWU/yr$, where L and V are the length and linear velocity of the rotor of the gas centrifuge and T is the temperature. This equation agrees well with the empirically determined separative power of optimised counter-current gas centrifuges.

• Bulletin of the Korean Chemical Society
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• 제22권5호
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• pp.503-506
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• 2001

Separation of lithium isotopes was investigated by chemical ion exchange with a hydrous manganese(IV) oxide ion exchanger using an elution chromatography. The capacity of manganese(IV) oxide ion exchanger was 0.5 meq/g. One molar CH3COO Na solution was used as an eluent. The heavier isotope of lithium was enriched in the solution phase, while the lighter isotope was enriched in the ion exchanger phase. The separation factor was calculated according to the method of Glueckauf from the elution curve and isotopic assays. The single stage separation factor of lithium isotope pair fractionation was 1.021.

• Bulletin of the Korean Chemical Society
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• 제22권6호
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• pp.570-574
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• 2001

Magnesium isotope separation was investigated by chemical ion exchange with the 1-aza-12-crown-4 bonded Merrifield peptide resin using an elution chromatographic technique. The capacity of the novel azacrown ion exchanger was 1.0 meq/g dry resin. The heavier isotopes of magnesium were enriched in the resin phase, while the lighter isotopes were enriched in the solution phase. The single stage separation factor was determined according to the method of Glueckauf from the elution curve and isotopic assys. The separation factors of $^{24}Mg^{2+}$-$^{25}Mg^{2+}$, $^{24}Mg^{2+}$-$^{26}Mg^{2+}$, and $^{25}Mg^{2+}$-$^{26}Mg^{2+}$ were 1.008, 1.019, and 1.006, respectively.

• Bulletin of the Korean Chemical Society
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• 제28권3호
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• pp.451-456
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• 2007

Tetraazamacrocyclic ion exchangers tethered to Merrifield peptide resin (DTDM, TTTM) were prepared and the ion exchange capacity of these was characterized. The isotope separation of lithium was determined using breakthrough method of column chromatography. The isotope separation coefficient was strongly dependent on the ligand structure by Glueckauf's theory. We found that the isotope separation coefficients were increased as the values of distribution coefficients were increased. In this experiment the lighter isotope, 6Li was enriched in the resin phase, while the heavier isotope, 7Li in the solution phase. The ion radius of lighter isotope, 6Li was shorter than the heavier isotope, 7Li. The hydration number of lithium ion with the same charge became small as mass number was decreased. Because 6Li was more strongly retained in the resin than 7Li, the isotopes of lithium were separated with subsequent enrichment in the resin phase.

• 대한방사성의약품학회지
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• 제7권2호
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• pp.69-77
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• 2021

No-carrier-added holmium-166 (n.c.a ¹⁶⁶Ho) separation is performed based on the results of separation conditions using stable isotopes dysprosium (Dy) and holmium (Ho) to minimize radioactive waste from separation optimization procedures. Successful separation of two adjacent lanthanides was achieved by cation-exchange chromatography using a sulfonated resin in the H+ form (BP-800) and α-hydroxyisobutyric acid (α-HIBA) as eluent. For the identification process after separation of stable isotopes, the use of chromogenic reagents alternatively enables on-line detection because the lanthanides are hardly absorb light in the UV-vis region or exhibit radioactivity. Four different chromogenic reagents were pre-tested to evaluate suitable coloring reagents, of which 4-(2-Pyridylazo)resorcinol is the most recommendable considering the sensitivity and specificity for lanthanides. Lanthanide radioisotopes (RI) were monitored for separation with an RI detector using a lab-made separation LC system. Under the proper separation conditions, the n.c.a ¹⁶⁶Ho was effectively obtained from a large amount of 100 mg dysprosium target within 2 hrs.

• 대한화학회지
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• 제45권3호
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• pp.219-222
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• 2001

용리 크로마토그래피를 사용하여 가수된 산화 망간(Ⅳ)이온교환체로 화학적 이온교환을 통하여, 리튬 동위원소를 분리하는 연구를 하였다. 산화 망간(Ⅳ)이온교환체의 이온교환 용량은 0.5meq/g이었다. 무거운 리튬 동위원소는 용액상에, 그리고 가벼운 동위원소는 이온교환 수지상에 농축되었다. 분리인자는, Glueckauf의 방법으로 용리곡선과 동위원서 분석 값들로부터 구하였다. $^6Li^+$-$^7Li^+$ 동위원소쌍의 분별로부터 얻은 분리인자의 값은 1.018이었다.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2867-2873
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• 2020

In reprocessed uranium, derived from an impoverished fuel of light-water moderated reactors, there are isotopes of ^{232, 234, 236}U, which make its recycling remarkably difficult. A method of concentration of ²³⁵U target isotope in cascade's additional product was proposed to recover the isotopic composition of reprocessed uranium. A general calculation procedure is presented and a parameters' optimization of multi-flow cascades with additional products. For the first time a numeric model of a cascade that uses the cuts of partial flows of stages with relatively high separation factors was applied in this procedure. A novel computing experiment is carried out on separation of reprocessed uranium hexafluoride with providing a high concentration of ²³⁵U in cascade's additional product with subsequent dilution. The parameters of cascades' stages are determined so as to allow reducing the ^{232, 234, 236}U isotope content up to the acceptable. It was demonstrated that the dilution of selected products by the natural waste makes it possible to receive a low enriched uranium hexafluoride that meets the ASTM C996-15 specification for commercial grade.

• 대한화학회지
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• 제27권3호
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• pp.189-193
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• 1983

리튬동위원소의 분리 실험이 염산과 양이온 교환 수지를 사용하여 행하여졌다. 이 실험에서는 porous sulfonated styrene-divinylbenzene copolymer와 Dowex 50w-x8의 양이온 교환수지가 사용되었다. 리튬의 양은 원자 흡광 분석기를 사용하여 측정되었다. 리튬 동위 원소의 상대적 질량은 질량 분석기로 측정하였다. 동위 원소의 분리인자는 분별된 용출액의 동위 원소 조성으로 부터 계산되었다. 분리 인자의 값은 염산과 porous sulfonated styrene-divinylbenzene copolymer system에서 1.0020이었고, 염산과 Dowex 50w-x8 system에서 1.0011${\om}$0.0002이었다. 이와 같은 결과로부터 우리들은 분리 인자의 값이 Dowex 50w-x8에서 보다 porous sulfonated styrene-divinylbenzene copolymer에서 더 크게 나타남을 알 수 있었다.