In KAERI’s previous phosphate precipitation tests, the dispersed powder of lithium phosphate (Li3PO4) as a precipitation agent reacted with various metal chlorides in a simulated LiCl-KCl molten salt. The reaction of metal chlorides composed of actinides such as uranium and three rare earths (Nd, Ce and La) with lithium phosphate is a solid-liquid reaction. A phosphorylation reaction rate is very fast and the metal phosphates as a reaction product precipitated on the bottom of the molten salt crucible. One of the recovery methods of the metal phosphate precipitates is segregation the lower part (precipitates) of the salt ingot using the various cutting tools. Recently, a new phosphorylation experiment using lithium phosphate ingots carried out in order to collect the metal phosphate precipitates into a small recovering vessel, and the test result of this new method was feasible. However, the reaction rate of test using lithium phosphate ingot is extremely slower than that of test using lithium phosphate powder. In this study, the precipitation reactor design (a tapered crucible with polished inner surface) used for phosphorylation reaction showed that the salt ingot with metal phosphate precipitates could be detached from a tapered stainless steel crucible. We propose that the recovery of precipitates from a salt ingot is possible by introducing a dividing plate structure into a molten salt and by positioning it at the interface between salt and precipitated metal phosphate.

When the recycling technology of spent nuclear fuels (SNF) for future nuclear reactor systems and the treatment technology of SNF for disposing of in a disposal site use a molten salt such as LiCl-KCl eutectic as a processing medium one of the essential unit processes is a distillation process that remove the salt component mixed with fission products recovered. Especially, in case of Pyro-SFR recycling system the recovered nuclear fuel materials such as U, TRU and some of rare earths come from main three processes (electro-refining, electro-winning, and drawdown processes) for recycling of SNF. These recovered fuel materials contain large portion of molten salt or liquid cadmium which requires removal of them by distillation. In spent nuclear fuels discharged from PWR the portion of composing element is as follows. Uranium is about 95%, other actinides such as transuranic elements (TRU; Np, Pu, Am, Cm) is about 1%, the rare earths (lanthanides) is about 1%, and the other elements is about 3%. For example, americium (Am) in the recovered fuel materials has a problem that the reported loss of Am inevitably occurs during the vacuum salt distillation operation. A new segregation method of AMM (actinide metal mixture)–salt system is based on the difference in melting point of the actinide elements. It is possible to apply this segregation method to recovering other actinides from AMM with accompanied salt because of relatively large amount and lower melting point of a specific element in other actinides avoiding vacuum salt distillation. This new segregation method successfully tested using a surrogate element such as aluminum due to its similar melting point with a specific element. The segregation principle is solid-liquid separation, thus the solidified actinides mixture ingot can take out of a molten salt medium.

Spin-off pyroprocessing technology and inert anode materials to replace the conventional carbon-based smelting process for critical materials were introduced. Efforts to select inert anode materials through numerical analysis and selected experimental results were devised for the high-throughput reduction of oxide feedstocks. The electrochemical properties of the inert anode material were evaluated, and stable electrolysis behavior and CaCu generation were observed during molten salt recycling. Thereafter, CuTi was prepared by reacting rutile (TiO2) with CaCu in a Ti crucible. The formation of CuTi was confirmed when the concentration of CaO in the molten salt was controlled at 7.5mol%. A laboratory-scale electrorefining study was conducted using CuTi(Zr, Hf) alloys as the anodes, with a Ti electrodeposit conforming to the ASTM B299 standard recovered using a pilot-scale electrorefining device.

Pretreatment system of desalination process using seawater reverse osmosis(SWRO) membrane is the most critical step in order to prevent membrane fouling. One of the methods is coagulation-UF membrane process. Coagulation-UF membrane systems have been shown to be very efficient in removing turbidity and non-soluble and colloidal organics contained in the source water for SWRO pretreatment. Ferric salt coagulants are commonly applied in coagulation-UF process for pretreatment of SWRO process. But aluminum salts have not been applied in coagulation-UF pretreatment of SWRO process due to the SWRO membrane fouling by residual aluminum. This study was carried out to see the effect of residual matal salt on SWRO membrane followed by coagulation-UF pretreatment process. Experimental results showed that increased residual aluminum salts by coagulation-UF pretreatment process by using alum lead to the decreased SWRO membrane salt rejection and flux. As the salt rejection and flux of SWRO membrane decreased, the concentration of silica and residual aluminum decreased. However, when adjusting coagulation pH for coagulation-UF pretreatment process, the residual aluminum salt concentration was decreased and SWRO membrane flux was increased.

As an approach for estimation of the droplet size in the molten salt-liquid metal extraction process, a droplet formation experiment at room temperature was conducted to evaluate the applicability of the Scheele-Meister model with water-mercury system as a surrogate that is similar to the molten salt-liquid metal system. In the experiment, droplets were formed through the nozzle and the droplet size was measured using a digital camera and image analysis software. As nozzles, commercially available needles with inner diameters (ID) of 0.018 cm and 0.025 cm and self-fabricated nozzles with 3-holes (ID: 0.0135 cm), 4-holes (ID: 0.0135 cm), and 2-holes (ID: 0.0148 cm) were used. The mercury penetration lengths in the nozzles were 1.3 cm for the needles and 0.5 cm for the self-fabricated nozzles. The droplets formed from each nozzle maintained stable spherical shape up to 20 cm below the nozzle. The droplet size measurements were within a 10% error range when compared to the Scheele-Meister model estimates. The experimental results show th

The straight nanopores in cellulose acetate (CA) polymers for battery gel separators were generated by utilizing both Ni(NO3)2·6H2O and water pressure. When polymer film was exposed to water pressure, the continuous nanopores were generated after complexing with Ni(NO3)2·6H2O. These results could be explained by that polymer chains were weakened because of the plasticization effect of the Ni(NO3)2·6H2O incorporated into the CA. The well controlled CA membrane after water pressure treatment enabled fabrication of highly reliable cell by utilizing 2032-type coin cell structure. The resulting cell performance exhibited both the effect of the physical morphology of CA separator and the chemical interaction of electrolyte with CA polymer which facilitates the Li-ion in the cell.

has the characteristic is controlling the inhibition or promotion of particle growth by adsorbing onto specific facets of platinum nanoparticles. Therefore, in this study, was added to control the shape of platinum nanoparticles during the liquid phase reduction process. Consequently, platinum cubes were synthesized when of 1.1 mol% (with respect to the Pt concentration) was added into the solution. Platinum octahedrons were synthesized when 32 mol% (with respect to the Pt concentration) was added into the solution. These results demonstrate that the metal salt , effectively controlled the relative growth rates of each facet of Pt nano particles.

PVA/SSA-H+으로 제조된 막은 1가 이온 Li+, Na+, K+, 2가 이온 Mg2+, Ca2+, Ba2+, 3가 이온 Al+로 치환되었다. 각 금속이온이 치환된 막의 금속이온의 효과를 알아보기 위하여 물-에탄올 및 물-메탄올 혼합용액에 대하여 팽윤도 및 투과증발 실험을 수행하였다. 또한 이들의 치환정도를 알아보기 위해 부분적으로 ESCA 실험을 통하여 알아보았다. 물-에탄올 및 물-메탄올 혼합용액에 대한 팽윤도는 Li+> Na+>K+의 순으로 감소하였는데 이는 금속이온의 `salting-out'효과에 기인하는 것으로 사료되었으며, 2가 및 3가이온의 경우의 팽윤도 결과는 `salting-out' 효과뿐만 아니라 electrostatic 가교 및 금속이온의 반응성에 의해 좌우되는 것으로 사료되었다. 투과증발실험을 통한 투과도면에서는 물-에탄올 용액에 대해 PVA/SSA-Na+막에서 최소치를 보였다가 PVA/SSA-K+막에서 다시 증가하는 결과를 얻은 반면에 선택도는 반대의 경향을 얻었다. 대표적 분리 결과는 50℃에서 90%에탄올 수용액에 대하여 투과도는 59 g/m2hr, 선택도는 44의 값을 얻었다. 물-메탄올 용액에 대해서는 1가이온의 경우 에탄올 용액과 같은 경향의 결과를 얻었으나 2가 및 3가 이온의 경우 팽윤도 실험 결과와 마찬가지로 `salting-out' 효과 그리고 electrostatic 가교 등에 의해 영향을 받는다고 할 수 있다.O10 ) 구조 (A-type: 14/mmm, a=3.8178 Å, c=29.9189 Å, V=436.04 Å3, B-type: 142 m, a =3.8376 Å, c=28.023 Å, V=412.6 Å3)가 존재함을 확인하였으나 다른 시료에서는 토소나이트, 금홍석 외에 새로운 합성광물로 제파이트의 존재를 확인하였다.형별 미시적 광물상과 혼성격자 구조형의 특징에 별다른 연계성이 없는 것으로 나타났다.X>-GeO2계 유리미립자들의 고밀화가 시작되는 온도를 각각 1224℃, 1151℃, 953℃, 1130℃에서 관찰하였다. 고농도 cisplatin을 투여할 수 있었으며, 또한 분리 폐 관류 시 cisplatin에 의한 직접적 폐 독성은 발견되지 않았다이 낮았으나 통계학적 의의는 없었다[10.0%(4/40) : 8.2%(20/244), p>0.05]. 결론: 비디오흉강경술에서 재발을 낮추기 위해 수술시 폐야 전체를 관찰하여 존재하는 폐기포를 놓치지 않는 것이 중요하며, 폐기포를 확인하지 못한 경우와 이차성 자연기흉에 대해서는 흉막유착술에 더 세심한 주의가 필요하다는 것을 확인하였다. 비디오흉강경수술은 통증이 적고, 입원기간이 짧고, 사회로의 복귀가 빠르며, 고위험군에 적용할 수 있고, 무엇보다도 미용상의 이점이 크다는 면에서 자연기흉에 대해 유용한 치료방법임에는 틀림이 없으나 개흉술에 비해 재발율이 높고 비용이 비싸다는 문제가 제기되고 있는 만큼 더 세심한 주의와 장기 추적관찰이 필요하리라 사료된다.전 도부타민 심초음파는 관

본 연구는 국내 천일염 생산 대표지역의 갯벌천일염 15종과 외국산 소금 38종에 대한 이화학적 품질 특성, 중금속 함량 및 phthalate 화합물의 오염 수준을 평가하였다. MSS에서 DEHP는 9.00~669.89 ppb 수준으로 검출되었으나 인체 안전성을 우려할만한 수준은 아니었다. 그러나 FS는 FSS 5종(3,440.64, 3,266.56, 2,189.65, 4,010.69, 4,554.20 ppb)과 FLSS 1종(1,983.27 ppb)에서 DEHP 용출규격 1.5 ppm이하를 초과하는 높은 수준이 검출되었으며, FSS 2종(930.15, 1,310.07 ppb), FLSS 1종(924.92 ppb)에서도 비교적 높은 수준이 검출되었다. 그 외의 phthalate 화합물에서는 MSS와 FS 모두에서 인체 안전성을 우려할만한 수준은 검출되지 않았다. Na 이온은 MSS(363,633.98 ppm)에 비해 FS(407,345.87~426,612.14 ppm)에서 높은 수준(p<0.05)이었으며, Mg(p<0.01), K(p<0.05), Ca 이온(p<0.05)은 FRS에서 가장 낮은 함량을, FSS에서 가장 높은 함량을 나타내었다. Cl 이온의 경우 MSS(532,727.07 ppm)에서 가장 낮은 함량(p<0.001)을 나타낸 반면, Br 이온(625.07 ppm)은 가장 높은 함량(p<0.001)을 나타내었으며 SO4 이온에서 유의한 차이는 없었다. MSS에서 Mn 함량이 높았으며, Al과 Fe의 함량은 FLSS에서 높은 수준이었다. MSS와 FS의 중금속에서 유의한 차이는 없었으며, 식용소금에 대한 중금속기준을 초과하지는 않아 소금을 통한 중금속은 안전한 수준으로 판단된다.