본 연구는 연안해양 수치모델에 활용되는 LDAPS 강우예보 자료의 시공간적 오차와 한계점을 분석하고 자료의 신뢰성을 검증 하였다. LDAPS 강우자료의 검증은 진해만 주변 우량계 3개소를 기준으로 2020년의 강우를 비교하였으며 우량계와 LDAPS의 비교 결과, LDAPS 강우자료는 장기적인 강우의 경향은 대체로 잘 재현하였으나 단기적으로는 큰 차이를 보였다. 정량적인 강우량 오차는 연간 197.5mm였으며, 특히 하계는 285.4mm로 나타나 계절적으로 강우변동이 큰 시기일수록 누적 강우량의 차이가 증가하였다. 강우 발생 시점 의 경우 약 8시간의 시간 지연을 나타내어 LDPAS 강우자료의 시간적 오차가 연안해양환경 예측 시 정확도를 크게 감소시킬 수 있는 것 으로 나타났다. 연안의 강우를 정확히 반영하지 못하는 LDAPS 강우자료를 무분별하게 사용할 경우 연안역에서 오염물질 확산 또는 극한 강우로 인한 연안환경 변화 예측에 심각한 문제를 발생시킬 수 있으며 LDAPS 강우자료의 적절한 활용을 위해서는 검증과 추가적인 개선 을 통한 정확도 향상이 필요하다.

본 연구에서는 레이더 관측 영역 내에 강수 에코(echo)가 없는 지역을 비강수 정보라고 정의하고 자료 동화에 활용하였다. 비강수 정보는 레이더로 관측할 수 있는 최대 영역 내에서 강수에 의한 에코가 나타나지 않고 레이더에서 관측할 수 없을 정도로 약한 강수나 구름 입자가 있거나, 강수 자체가 없다는 것을 의미한다. 기존의 레이더 자료를 동 화한 연구가 강수에 의한 반사도와 시선속도를 동화하여 모델 내의 강수를 만들어내는 것에 초점을 두었다면, 본 연구 에서는 에코가 없다는 것도 하나의 정보로 고려하고 이를 동화함으로써 모델 내에서 잘못 예측한 강수를 억제하였다. 비강수 정보를 자료동화에 적용시키기 위해 레이더 비강수 정보를 수상체와 상대습도로 변환하는 관측 연산자를 제시 하고 이를 Weather Research and Forecasting (WRF) 모델의 자료동화 시스템인 WRF Data Assimilation system (WRFDA)에 적용하였다. 또한 비강수 정보를 효과적으로 활용하기 위한 레이더 자료의 처리 방법을 제시하였다. 비강 수 정보가 모델 내에서 잘못 예측한 강수를 억제할 수 있는지 확인하기 위해 단일 관측실험을 수행하였으며 비강수 정 보가 수상체와 습도 그리고 기온을 낮춤으로써 대류가 억제될 수 있는 환경을 만들었다. 비강수 정보의 동화 효과를 실제 사례에 적용한 2013년 7월 23일 대류 사례 실험을 통해 9시간 예측을 수행하여 결과를 분석하였다. 레이더 비강 수 정보를 추가로 동화한 실험이 비강수 정보를 제외한 실험보다 Fractional Skill Score (FSS)가 증가하고 False Alarm Ratio (FAR)는 감소하여 모델의 강수 예측성을 향상시켰다.

Currently, non-volatile nuclides such as 94Nb, 99Tc, 90Sr, 55Fe, and 59/63Ni are used a sequential separation. In this study, we developed a separation for 99Tc and 90Sr by a carbonate precipitation. Sodium Carbonate (Na2CO3) was inserted in the aqueous sample from a Dry Active Waste (DAW) and a carbonate precipitation was produced. The precipitate is composed of di- or tri-valent element such as Co, Sr, Fe, Ni and the supernatant is composed of mono-valent element (Cs) and anion materials (ReO4 -, TcO4 -). In DAW, it was confirmed that the recovery of 90Sr (precipitate) and 99Tc (supernatant) were > 90%, respectively. The precipitate and supernatant separated by using a Sr-resin and an anion-exchange resin, respectively. The separated samples were measured by a Liquide Scintillation Counter (LSC, 90Sr) and Induced-Coupled Plasma-Mass Spectroscopy (ICPMS, 99Tc).

This study used optical and scanning electron microscopy to analyze the surface oxidation phenomenon that accompanies a γ'-precipitate free zone in a directional solidified CM247LC high temperature creep specimen. Surface oxidation occurs on nickel-based superalloy gas turbine blades due to high temperature during use. Among the superalloy components, Al and Cr are greatly affected by diffusion and movement, and Al is a major component of the surface oxidation products. This out-diffusion of Al was accompanied by γ' (Ni3Al) deficiency in the matrix, and formed a γ'-precipitate free zone at the boundary of the surface oxide layer. Among the components of CM247LC, Cr and Al related to surface oxidation consist of 8 % and 5.6 %, respectively. When Al, the main component of the γ' precipitation phase, diffused out to the surface, a high content of Cr was observed in these PFZs. This is because the PFZ is made of a high Cr γ phase. Surface oxidation of DS CM247LC was observed in high temperature creep specimens, and γ'-rafting occurred due to stress applied to the creep specimens. However, the stress states applied to the grip and gauge length of the creep specimen were different, and accordingly, different γ'-rafting patterns were observed. Such surface oxidation and PFZ and γ'-rafting are shown to affect CM247LC creep lifetime. Mapping the microstructure and composition of major components such as Al and Cr and their role in surface oxidation, revealed in this study, will be utilized in the development of alloys to improve creep life.

A phosphorylation (phosphate precipitation) technology of metal chlorides is considering as a proper treatment method for recovering the fission products in a spent molten salt. In KAERI’s previous precipitation tests, the powder of lithium phosphate (Li3PO4) as a precipitation agent reacted with metal chlorides in a simulated LiCl-KCl molten salt. The reaction of metal chlorides containing actinides such as uranium and rare earths with lithium phosphate in a molten salt was known as solidliquid reaction. In order to increase the precipitation reaction rate the powder of lithium phosphate dispersed by stirring thoroughly in a molten salt. As one of the recovery methods of the metal phosphates precipitated on the bottom of the molten salt vessel cutting method at the lower part of the salt ingot is considered. On the other hand, a vacuum distillation method of all the molten salt containing the metal phosphates precipitates was proposed as another recovering method. In recent study, a new method for collecting the phosphorylation reaction products into a small recovering vessel was investigated resulting in some test data by using the lithium phosphate ingot in a molten salt containing uranium and three rare earth elements (Nd, Ce, and La). The phosphorylation experiments using lithium phosphate ingots carried out to collect the metal phosphate precipitates and the test result of this new method was feasible. However, the reaction rate of test using lithium phosphate ingot is very slower than that of test using lithium phosphate powder. In this presentation, the precipitation reactor design used for phosphorylation reaction shows that the amount of molten salt transferred to the distillation unit will reduce by collecting all of the metal phosphates that will be generated using lithium phosphate powder into a small recovering vessel.

The major concern in the deep geological disposal of spent nuclear fuels include sulfide-induced corrosion and stress corrosion cracking of copper canisters. Sulfur diffusion into copper canisters may induce copper embrittlement by causing Cu2S particle formation along grain boundaries; these sulfide particles can act as crack initiation sites and eventually cause embrittlement. To prevent the formation of Cu2S along grain boundaries and sulfur-induced copper embrittlement, copper alloys are designed in this study. Alloying elements that can act as chemical anchors to suppress sulfur diffusion and the formation of Cu2S along grain boundaries are investigated based on the understanding of the microscopic mechanism of sulfur diffusion and Cu2S precipitation along grain boundaries. Copper alloy ingots are experimentally manufactured to validate the alloying elements. Microstructural analysis using scanning electron microscopy with energy dispersive spectroscopy demonstrates that Cu2S particles are not formed at grain boundaries but randomly distributed within grains in all the vacuum arc-melted Cu alloys (Cu-Si, Cu-Ag, and Cu-Zr). Further studies will be conducted to evaluate the mechanical and corrosion properties of the developed Cu alloys.

The effect of Li2O addition on precipitation behavior of uranium in LiCl-KCl-UCl3 has been investigated in this study. 99.99% LiCl-KCl eutectic salt is mixed with 10wt% UCl3 chips at 550°C in the Pyrex tube in argon atmosphere glove box, with 10 ppm O2 and 1 ppm H2O. Then, Li2O chunks are added in mixed LiCl-KCl-UCl3 and the system has been cooled down to room temperature for 10 hours to form enough UO2 particles in the salt. The solid salt has been taken out from the glove box, and cut into three sections (top, middle and bottom) by low-speed saw for further microscopic analysis. Three pieces of solid salt are dissolved in deionized water at room temperature and the solution is filtered by a filter paper to collect non-dissolved particles. The filter paper with particles is baked in vacuum oven at 120°C for 6 hours to evaporate remaining moisture from the filter paper. Further analysis was performed for the powder remaining on the filter paper, and periphery of the powder (cake) on the filter paper. Scanning electron microscopy (SEM), electron diffraction spectroscopy (EDS), and X-ray powder diffraction (XRD) are adopted to analysis the characteristic of the particles. From SEM analysis, the powders are consisted of small particles which have 5 to 10 m diameter, and EDS analysis shows they are likely UO2 with 23 at. % of uranium and 77 at. % oxygen. Cake is also analyzed by SEM and EDS, and needle like structures are widely observed on the particle. The length of needle is distributed from 5 to 20 m, and it has 6 to 10 at. % of chlorine, which are not fully dissolved into deionized water at room temperature. From XRD analysis, the particles show the peak position of UO2, and the result is well matched with the SEM-EDS results. We are planning to add more Li2O in the system for fully reacting uranium in UCl3, and compare the results to find the effect of Li2O concentration on UO2 precipitation.

Cloud-aerosol interactions are one of the paramount but least understood forcing factors in climate systems. Generally, an increase in the concentration of aerosols increases the concentration of cloud droplet numbers, implying that clouds tend to persist for longer than usual, suppressing precipitation in the warm boundary layer. The cloud lifetime effect has been the center of discussion in the scientific community, partly because of the lack of cloud life cycle observations and partly because of cloud problems. In this study, the precipitation susceptibility (So) matrix was employed to estimate the aerosols' effect on precipitation, while the non-aerosol effect is minimized. The So was calculated for the typical coupled, well-mixed maritime stratocumulus decks and giant cloud condensation nucleus (GCCN) seeded clouds. The GCCN— artificially introduced to the marine stratocumulus cloud decks—is shown to initiate precipitation and reduces So to approximately zero, demonstrating the cloud lifetime hypothesis. The results suggest that the response of precipitation to changes in GCCN must be considered for accurate prediction of aerosol-cloud-precipitation interaction by model studies

본 연구는 영국기상청에서 개발된 지역기후모델 Hadley Centre Global Environmental Model version 3 regional climate model (HadGEM3-RA)로부터 모의된 동아시아 지역의 기온과 강수 결과를 평가하였다. HadGEM3-RA 는 Coordinated Regional climate Downscaling Experiment-East Asia (CORDEX-EA) Phase II 영역에서 15년 (2000- 2014년) 모의되었다. 동아시아 여름 몬순에 의한 HadGEM3-RA 강수대 분포는 Asian Precipitation Highly ResolvedObservational Data Integration Towards Evaluation of water resources (APHRODITE) 자료와 잘 일치한다. 그러나, 동 남아시아 강수는 과대 모의하며 남한에서는 과소 모의한다. 특히 모의된 여름철 강수량과 APHRODITE 강수량은 남한 지역에서 가장 낮은 상관 계수와 가장 큰 오차크기(RMSE)를 보인다. 동아시아 기온 예측은 과소 모의하며 겨울철 오 차가 가장 크다. 남한 기온 예측은 봄 동안 가장 큰 과소 모의 오차를 나타냈다. 국지적 예측성을 평가하기 위하여 서 울기상관측소 ASOS 자료와 비교한 기온과 강수의 시계열은 여름철 강수와 겨울철 기온이 과소 모의하는 공간 평균된 검증 결과와 유사하였다. 특히 여름철 강수량 증가시 과소 모의 오차가 증가하였다. 겨울철 기온은 저온에서는 과소 모 의하나 고온은 과대 모의하는 경향이 나타났다. 극한기후지수 비교 결과는 폭염은 과대 모의하여, 집중호우는 과소 모 의하는 오차가 나타났다. 수평해상도25km로 모의된 HadGEM3-RA는 중규모 대류계와 지형성 강수 예측에서 한계를 보였다. 본 연구는 지역기후모델 예측성 개선을 위한 초기 자료 개선, 해상도 향상, 물리 과정의 개선이 필요함을 지시 한다.

Concrete is one of the largest wastes, by volume, generated during the decommissioning of nuclear facilities, which significantly influences the projected costs for the disposal of decommissioning wastes. Concrete consists of aggregates and a cement binder. In radioactive concrete, the radioisotopes are mainly associated with the cement component. If the radioactive isotope can be separated from the concrete to below the clearance criteria, the volume of radioactive concrete waste could be reduced effectively. We were studied to separate the radioactive materials from the concrete by using the thermomechanical and chemical treatment processes, sequentially. From the study, separated aggregate could be treated to achieve the clearance level. However, these processes generate a large volume of secondary acidic radioactive wastewater, which might be a critical problem to reduce the volume of radioactive concrete waste. In this research, separating the 137Cs and 90Sr from dissolved concrete wastewater to below the discharge criteria by precipitation method, it would be released to the environment under industrial waste guidelines. The experiments were conducted to using a simulated radioactive wastewater, formed by the dissolution of concrete within HCl, which was spiking the 137Cs and 90Sr, respectively. In addition, we applied the chemical precipitation methods with wastewater, using ferrocyanide for 137Cs and BaSO4 coprecipitation for 90Sr. As a result, targeted radionuclides could be removed to the discharge level (137Cs: 0.05 Bq·ml−1, 90Sr: 0.02 Bq·ml−1) by precipitation method. Therefore, it could reduce the secondary wastewater effectively by precipitation method and enhance the additional volume reduction for radioactive concrete waste.

The purpose of this study was to effectively purify U-contaminated soil-washing effluent using a precipitation/distillation process, reuse the purified water, and self-dispose of the generated solid. The U ions in the effluent were easily removed as sediments by neutralization, and the metal sediments and suspended soils were flocculated–precipitated by polyacrylamide (PAM). The precipitate generated through the flocculation–precipitation process was completely separated into solid–liquid phases by membrane filtration (pore size < 45 μm), and Ca2+ and Mg2+ ions remaining in the effluent were removed by distillation. Even if neutralized or distilled effluent was reused for soil washing, soil decontamination performance was maintained. PAM, an organic component of the filter cake, was successfully removed by thermal decomposition without loss of metal deposits including U. The uranium concentration of the residual solids after distillation is confirmed to be less than 1 Bq·g−1, so it is expected that the self-disposal of the residual solids is possible. Therefore, the treatment method of U-contaminated soil-washing effluent using the precipitation/distillation process presented in this study can be used to effectively treat the washing waste of U-contaminated soil and self-dispose of the generated solids.

The capacity of high nickel Li(NixCoyMn1-x-y)O2 (NCM, x ≥ 0.8) cathodes is known to rapidly decline, a serious problem that needs to be solved in a timely manner. It was reported that cathode materials with the {010} plane exposed toward the outside, i.e., a radial structure, can provide facile Li+ diffusion paths and stress buffer during repeated cycles. In addition, cathodes with a core-shell composition gradient are of great interest. For example, a stable surface structure can be achieved using relatively low nickel content on the surface. In this study, precursors of the high-nickel NCM were synthesized by coprecipitation in ambient atmosphere. Then, a transition metal solution for coprecipitation was replaced with a low nickel content and the coprecipitation reaction proceeded for the desired time. The electrochemical analysis of the core-shell cathode showed a capacity retention of 94 % after 100 cycles, compared to the initial discharge capacity of 184.74 mA h/g. The rate capability test also confirmed that the core-shell cathode had enhanced kinetics during charging and discharging at 1 A/g.

Extensive research is being carried out on Ni-rich Li(NixCoyMn1-x-y)O2 (NCM) due to the growing demand for electric vehicles and reduced cost. In particular, Ni-rich Li(NixCoyMn1-x-y-zAlz)O2 (NCMA) is attracting great attention as a promising candidate for the rapid development of Co-free but electrochemically more stable cathodes. Al, an inactive element in the structure, helps to improve structural stability and is also used as a doping element to improve cycle capability in Ni-rich NCM. In this study, NCMA was successfully synthesized with the desired composition by direct coprecipitation. Boron and tin were also used as dopants to improve the battery performance. Macro- and microstructures in the cathodes were examined by microscopy and X-ray diffraction. While Sn was not successfully doped into NCMA, boron could be doped into NCMA, leading to changes in its physicochemical properties. NCMA doped with boron revealed substantially improved electrochemical properties in terms of capacity retention and rate capability compared to the undoped NCMA.

Cobalt (Co) is mainly used to prepare cathode materials for lithium-ion batteries (LIBs) and binder metals for WC-Co hard metals. Developing an effective method for recovering Co from WC-Co waste sludge is of immense significance. In this study, Co is extracted from waste cemented carbide soft scrap via mechanochemical milling. The leaching ratio of Co reaches approximately 93%, and the leached solution, from which impurities except nickel are removed by pH titration, exhibits a purity of approximately 97%. The titrated aqueous Co salts are precipitated using oxalic acid and hydroxide precipitation, and the effects of the precipitating agent (oxalic acid and hydroxide) on the cobalt microstructure are investigated. It is confirmed that the type of Co compound and the crystal growth direction change according to the precipitation method, both of which affect the microstructure of the cobalt powders. This novel mechanochemical process is of significant importance for the recovery of Co from waste WC-Co hard metal. The recycled Co can be applied as a cemented carbide binder or a cathode material for lithium secondary batteries.