기후 변화의 가속화로 국내 제주 및 남부 지방을 중심으로 열대 및 아열대 작물의 재배 및 소비가 증가하는 추세이다.오크라는 식용적 가치가 있을 뿐만 아니라, 품종별 고유의 꼬 투리와 잎의 색은 관상적 가치가 있어 조경 식물로 많이 사용 되고 있다. 본 연구는 도심 내 옥상 온실에 관상식물인 오크 라를 도입하기 위해 피트모스와 펄라이트 비율에 따른 기초 종자 발아 및 육묘기 실험을 진행하였다. 피트모스와 펄라이 트 비율은 PT:PL=1:2, 1:1, 2:1, 4:1 네 가지로 조성하였다. 발 아율은 파종 후 7일차부터 다른 처리구에 비해 피트모스:펄라 이트=1:2의 처리구에서 가장 높았다. 파종 후 28일차와 70일 차에 줄기길이, 경경, 뿌리길이, 지상부와 지하부의 생체중과 건물중 그리고 엽면적은 피트모스:펄라이트=1:2 처리구에서 가장 높았다. 그러나, 파종 후 56일 이후부터 엽수는 피트모 스:펄라이트=1:2, 2:1, 4:1 처리구에서 감소하였다. 피트모스: 펄라이트=1:1, 2:1, 4:1 처리구에서 식물이 필요로 하는 피트 모스의 비율이 지나치게 높아 높은 피트모스 비율로 인하여 수분함수량이 과도하게 높아 식물이 고사한 것으로 판단된다. 따라서 오크라를 관상식물로 활용하기 위해서는 피트모스와 펄라이트를 1:2로 혼합한 배지가 가장 적합하다.

털부처꽃(Lythrum salicaria L.)은 전국에 분포하는 다년생 초본식물로 척박하고 습한 지역을 포함한 다양한 환경에서 잘 자라는 것으로 알려져 있다. 따라서 하천변, 척박지에서 정원 용, 화훼용 및 관상용 식물로 이용이 가능하다. 본 연구는 털 부처꽃의 적정 육묘 조건(토양종류, 플러그 트레이 셀 크기,파종립수, 액비농도 및 차광)을 조사하였다. 대조구(원예상토) 에서 재배된 유묘의 생육이 가장 우수하였다. 반면 피트모스 와 펄라이트의 혼합용토는 육묘기간이 지속되면서 생육수치 가 감소하는 경향을 나타냈다. 셀 크기는 용적이 가장 큰 162 셀에서 재배된 유묘의 생육이 우수하였으나, 200셀과 288셀에 서 자란 묘도 건강했다. 한편 유묘의 결주발생을 고려하면 셀 당 2립을 파종하는 것이 적합하였다. 액비 처리는 유묘의 생 육을 촉진하였다. 특히 Hyponex 1000배는 초장, 줄기직경, 엽수, 마디수, 근장, 지상부 생체중 및 지하부 생체중을 증가 시켰다. 또한 유묘의 생육은 55% 차광 하에서 우수하였다. 따 라서 털부처꽃의 가장 효과적인 생육조건은 원예상토가 충진 된 288셀 플러그 트레이에 셀 당 2립을 파종하고 Hyponex 1000배를 시비하면서 55% 차광 하에서 재배하는 것이었다.

This study is a follow-up paper on “Development of flipped learning class model for nail beauty education” published by Seol (2022). This model was conducted from March to June 2022 for 70 students taking the “Nail color design 1” course. After 15 weeks of class, a survey of the students’ perceptions of flipped learning and their self-evaluation of goal achievement was conducted, which was composed of questionnaires using a 5-step Likert scale. 15 questions were designed to evaluate the students’ satisfaction with their experience and class operations; 4 questions to evaluate whether the class goal had been reached through flipped learning; and 9 questions to evaluate the students’ perceptions of flipped learning. As a result of applying this model to theoretical and practical nail beauty classes, it was confirmed that flipped learning helped students better understand the content and had a positive effect on learning, while the subject’s educational goals were also achieved. By evaluating the students’ perceptions of flipped learning, we may conclude that they experienced learning satisfaction and perceived the approach positively. Moreover, they have expressed a desire for additional flipped learning. This study is thus meaningful in confirming the procedure’s effectiveness by applying the flipped classroom model to theoretical and practical subjects with a focus on the nail beauty field, and showing how it achieved students’ positive perceptions and educational goals.

Polarimetric measurements of the lunar surface from lunar orbit soon will be available via Wide-Field Polarimetric Camera (PolCam) onboard the Korea Pathfinder Lunar Orbiter (KPLO), which is planned to be launched in mid 2022. To provide calibration data for the PolCam, we are conducting speckle polarimetric measurements of the nearside of the Moon from the Earth’s ground. It appears that speckle imaging of the Moon for scientific purposes has not been attempted before, and there is need for a procedure to create a “lucky image” from a number of observed speckle images. As a first step of obtaining calibration data for the PolCam from the ground, we search for the best sharpness measure for lunar surfaces. We then calculate the minimum number of speckle images and the number of images to be shift-and-added for higher resolution (sharpness) and signal-to-noise ratio.

Flipped learning research has been applied in various educational fields since 2015 and the educational effects have been discussed in previous literature. In the beauty field, flipped learning research is insufficient; in particular, it is difficult to find research on flipped learning specifically concerning nail beauty education. The purpose of this study is to develop a model for applying flipped learning to nail beauty education which should involve practical training based on theory. Such an approach is considered effective. Data were collected and analyzed focusing on previous studies with flipped learning applied as a research method. The subject of the research is “Nail Color Design 1”, a common nail major elective subject at J college. The “Nail Color Design 1” course is a practice-oriented course in the form of theory and practical classes. Consequently, the flipped learning education model for nail beauty was designed by reflecting learners’ needs through the ADDIE instructional design model. It was applied based on the education structure of the Pre-class, In-class, and Post-class of the PARTNER instructional learning model. This study deviates from the traditional practical education model, and has educational significance as a practical model in which flipped learning is applied to nail beauty subjects and self-reflection is derived through project practice.

In recent years, juvenile offenders have made up an increasing number of all criminal suspects, and minor crimes are becoming a more serious social problem in most countries and regions around the world. While community correction occupies a very important position in the minor crime punishment system, current community correction risk assessments mainly depend on qualitative analysis or simple mathematical statistics using collected data. In combination with relevant theories and regulations, this paper offers a systematic look at the development and theories of community correction and the related risk assessment system and analyzes the characteristics of community correction risk assessment methods of juvenile offenders in different countries. Moreover, it discusses some new risk assessment technologies based on artificial intelligence theory for community correction risk evaluation of juvenile offenders. The effectiveness of the proposed community correction risk assessment method is verified using some real-world community correction assessments.

Pleurotus ostreatus is a globally cultivated mushroom crop. Cap color is a quality factor in P. ostreatus. However, cap color can spontaneously mutate, degrading the quality of the mushroom on the market. Early detection and removal of mutant strains is the best way to maintain the commercial value of the crop. To detect the cap color mutant Gonji7ho, molecular markers were developed based on insertion/deletions (InDels) derived from the comparison of mitogenomes of Gonji7ho and Gonji7hoM mushrooms. Sequencing, assembly, and comparative analysis of the two mitogenomes revealed genome sizes of 73,212 bp and 72,576 bp with 61 and 57 genes or open reading frames (ORFs) in P. ostreatus Gonji7ho and Gonji7hoM, respectively. Fourteen core protein-encoding genes, two rRNA, and 24 tRNA with some OFRs were predicted. Of the 61 genes or OFRs in the wild type, dpo, rpo, and two orf139 were missing (or remnant) in the mutant strain. Molecular markers were developed based on the sequence variations (InDels) between the two mitogenomes. Six polymorphic molecular markers could detect the mutated mitochondria by PCR. These results provide basic knowledge of the mitogenomes of wild-type and mutant P. ostreatus, and can be applied to discriminate mutated mitochondria.

Veronica L., the largest genus in the family Plantaginaceae, is widespread in various habitats. Due to their long-blooming flowers, Veronica species have high horticultural value as indoor potted, garden, and landscape plants. Furthermore, Veronica plants are extremely important owing to their notable diversity in habitat usage, ploidy level, and evolution. Several native taxa, which are of key interest in breeding programs and phylogenetic studies, have been identified in Korea. The genome sizes and chromosomal characteristics are basic cytogenetic features of all taxa, and their knowledge is a prerequisite when commencing genome sequencing projects. It can provide essential information for cytogenetic, taxonomic, phylogenetic, and evolutionary studies. Thus, cytogenetic analysis and genome size estimation of seven Veronica taxa native to Korea were conducted in this study. Fluorescence in situ hybridization (FISH) karyotype analysis and chromosome counting was conducted using metaphase chromosomes probed with 5S and 45S rDNA. Nuclear DNA content and genome size were determined using flow cytometry. FISH karyotype analysis revealed a common number of 5S loci and varying 45S signals that create distinctive rDNA distribution patterns in each taxon. The results indicated that the seven investigated Veronica taxa have calculated genome sizes (1C values) ranging from 517.1 to 862.0 Mbp. This study is the first to report the chromosome number and karyomorphology of seven Veronica taxa native to Korea, as well as the use of rDNA markers for identifying individual chromosomes. These findings contribute to the crucial understanding the genomic characteristics of species within the genus Veronica, serve as a basis for studying Veronica phylogeny and evolution, and provide valuable information for future breeding programs.

At high temperatures, molten salt has heat transfer properties like water. Molten salt has the characteristics of a strong natural circulation tendency, large heat capacity, and low thermal conductivity. Unlike sodium, molten salt does not react explosively exothermically with air. However, molten salt has a strong tendency to corrode materials, and its properties are easily changed by a sensitive reaction to oxygen and moisture. Therefore, it is necessary to study material corrosion properties and chemical control methods for nuclear fuel salts, which are eutectic mixtures. In this study, the optimal operation method of the thermal convection loop is established to perform the experiments on the molten salt. The process describes briefly as follows. The operation step consists of preparation, purification, transportation, and operation. In the preparation, the step checks the entire structure and equipment (TC, blower, vacuum pump, etc.). And melt the salt mixture at a high temperature (670°C) slowly in the purification step. Before injecting the molten salt, the surface temperature of the entire loop must retain temperature (about 500°C) constantly. Completely melted molten salt in the melting pot is flow along the pipe of the thermal convection loop in the transportation step. Lastly, the convection of molten salt goes to keep by the temperature difference. The thermal convection loop can be utilized for various experiments such as corrosion tests, component analyses, chemistry control, etc.

Molten salt used in the multipurpose molten salt experiment must be of high purity. Depending on the purpose of the experiment, only the base component of the molten salt be used, or a component simulating a nuclear fission product be added to the base component and used. In all cases, an increase in the concentration of impurities such as oxygen and moisture may lead to an erroneous interpretation when analyzing the experimental results. Therefore, molten salt should be purified before use. In this study, the purification of molten salt is described for multi-purpose molten salt experiments. The salt mixture is selected as MgCl2-NaCl and is quantified at a mixing ratio of 43mol%:57mol%. The salt mixture is treated in a glove box environment because of must minimize the reaction of adsorbing oxygen and moisture when the salt mixture is exposed to the atmosphere. MgCl2 is more likely to contain water than NaCl, the purification of the NaCl-MgCl2 mixture is established according to the purification process for removing water from MgCl2. A process for purifying the salt mixture briefly consists as follows: drying moisture, melting salts, purification, removing HCl, and stabilization. Through the process be able to obtain high-purity molten salt and more accurate experiment results.

As the number of aging nuclear power plants increases, the market for dismantling nuclear power plants is growing rapidly. About 40% of the cost of dismantling nuclear power plants is the waste treatment cost incurred during the dismantling process, of which concrete waste accounts for a significant portion of the total waste. Securing technology for reducing and recycling concrete waste is very important not only in terms of economy but also in terms of environment. The objective is to synthesize geopolymer using inorganic materials from cement fine powder in concrete waste. Cement fine powder in concrete waste has a large amount of inorganic elements necessary for filing materials for radioactive waste treatment such as CaO and SiO2. In particular, Ca(OH)2 is synthesized by extracting Ca2+ from concrete waste. It can be used as an alkali activator to synthesize geopolymer. The mortar from crushed concrete was used as a source of calcium. The first step is to react with concrete waste and hydrochloric acid to extract ions. The second step is to react with NaOH and synthesize Ca(OH)2. The product was divided into two stages according to the reaction method and order. The first and second products were washed and dried, and then XRD and XRF were performed. The second product was matched only Ca(OH)2 and CaCO3 at the XRD peak. In the case of XRF, it was analyzed to have a purity of 67.80–78.73%. Synthesis of geopolymer by recycling materials extracted from concrete waste can reduce disposal costs and improve the utilization rate of disposal sites.

In this study, an aerosol process was introduced to produce CaCO3. The possibility of producing CaCO3 by the aerosol process was evaluated. The characteristics of CaCO3 prepared by the aerosol process were also evaluated. In the CaCO3 prepared in this study, as the heat treatment proceeded, the calcite phase disappeared. The portlandite phase and the lime phase were formed by the heat treatment. Even if the CO2 component is removed from the calcite phase, there is a possibility that the converted CO2 component could be adsorbed into the Ca component to form a calcite phase again. Therefore, in order to remove the calcite phase, carbon components should be removed first. The lime phase was formed when CO2 was removed from the calcite phase, while the portlandite phase was formed by the introducing of H2O to the lime phase. Therefore, the order in which each phase formed could be in the order of calcite, lime, and portlandite. The reason for the simultaneous presence of the portlandite phase and the lime phase is that the hydroxyl group (OH−) introduced by H2O was not removed completely due to low temperature and/or insufficient heating time. When the sufficient temperature (900°C) and heating time (60 min) were applied, the hydroxyl group (OH−) was removed to transform into lime phase. Since the precursor contained the hydrogen component, it could be possible that the moisture (H2O) and/or the hydroxyl group (OH−) were introduced during the heat treatment process.

Uranium-235, used for nuclear power generation, has brought radioactive waste. It could be released into the environment during reprocessing or recycling of the spent nuclear fuel. Among the radioactive waste nuclides, I-129 occurs problems due to its long half-life (1.57×107 y) with high mobility in the environment. Therefore, it should be captured and immobilized into a geological disposal system through a stable waste form. One of the methods to capture iodine in the off-gas treatment process is to use silver loaded zeolite filter. It converts radioactive iodine into AgI, one of the most stable iodine forms in the solid state. However, it is difficult to directly dispose of AgI itself in an underground repository because of its aqueous dissolution under reducing condition with Fe2+. It must be immobilized in the matrix materials to prevent release of iodine as a result of chemical reaction. Among the matrix glasses, silver tellurite glass has been proposed. In this study, additives including Al, Bi, Pb, V, Mo, and W were added into the silver tellurite glass. The thermal properties of each matrix for radioactive iodine immobilization were evaluated. The glasses were prepared by the melt-quenching method at 800°C for 1 h. Differential scanning calorimetry (DSC) was performed to evaluate the thermal properties of the glass samples. From the study, the glass transition temperature (Tg) was increased by adding additives such as V2O5, MoO3, or WO3 in the silver tellurite glass. The relative electro-static field (REF) values of V2O5, MoO3, and WO3 are about three times higher than that of the glass network former, TeO2. It could provide sufficient electro-static field (EF) to the TeO2 interacting with the non-bridging oxygen forming Te-O-M (M = V, Mo, W) links. Therefore, the addition of V2O5, MoO3, or WO3 reinforced the glass network cohesion to increase the Tg of the glass. The addition of MoO3or WO3 in the silver tellurite glass increased Tg and crystallization temperature (Tc) with remaining the glass stability.

During the treatment of spent nuclear fuel, radioactive iodine is generated in a liquefied or gaseous form in a specific process. In the case of iodine 129, it is a long-lived nuclide with a very long halflife and has high groundwater mobility under repository conditions. Despite showing a low radioactivity value, research on the management of radioactive iodine from a long-term perspective is continuously being performed. Although research has been conducted using borosilicate glass as a medium for solidifying iodine, compatibility of I in borosilicate glass is very small and the volatility is high in the solidification process. So it is not suitable as a solidified substance of iodine. Therefore, studies on other solidification media to replace them are continuously being conducted. Our research team tried to develop a new medium that can contain iodine in a solidified body stably through a simple heat treatment process and can improve problems such as volatility and waste loading. Iodine is captured as AgI in the Ag ion-exchanged zeolite. So, TeO2, Ag2O, and Bi2O3 having a high AgI loading rate were used as main components. It was named TAB after taking the first letter of each element. In previous studies, the physical properties, structure, and chemical stability of TAB materials were confirmed. PCT (Product Consistent test) was performed to confirm chemical stability. It is mainly used to compare the chemical stability of glass materials with other glass materials, but there are limitations in evaluating the long-term chemical stability of materials. In this experiment, we tried to evaluate the long-term stability of TAB and compare it with borosilicate, which is conventionally used to treat radioactive waste. In addition, we tried to understand the leaching behavior inside the TAB medium. For this purpose, ASTM C1308 test was performed for 365 days, and distilled water and KURT groundwater were used as leachates to examine the effect of ions in the groundwater on the solidified body. To analyze the leaching behavior, ICP-MS and ICP-OES analyses were performed, and the cross-section of the sample after leaching was observed through SEM.

To reduce the environmental burden caused by the disposal of spent nuclear fuel and maximize the utilization of the repository facility, waste burden minimization technology is currently being developed at the Korea Atomic Energy Research Institute (KEARI). The technology includes a nuclide management process that can maximize disposal efficiency by selectively separating and collecting major nuclides in spent nuclear fuel. In addition, for efficient storage facility utilization, the short-term decay heat generated by spent nuclear fuel must be removed from the waste stream. To minimize the short-term thermal load on the repository facility, it is necessary to separate heat generating nuclides such as Cs-137 and Sr-90 from the spent fuel. In particular, Sr-90 must be separated because it generates high heat during the decay process. KAERI has developed a technology for separating Sr nuclides from Group II nuclides separated through the nuclide management process. In this study, we prepared Sr ceramic waste form, SrTiO3, by using the solid-state reaction method for long-term storage for the decay of separated Sr nuclides and evaluated the physicochemical properties of the waste form. Also, the radiological and thermal characteristics of the Sr waste form were evaluated by predicting the composition of Sr nuclides separated through the nuclide management process, and the estimation of centerline temperature was carried out using the experimental thermal data and steady state conduction equation in a long and solid cylinder type waste form. These results provided fundamental data for long-term storage and management of Sr waste.