목적 : 본 연구는 Orthokeratology(OK) 렌즈와 기존의 단안렌즈(SV) 안경을 착용한 근시 청소년의 굴절이상을 분석하여 OK 렌즈가 근시 진행에 미치는 영향을 살펴보고자 하였다. 방법 : 연구방법은 중국 길림성 북화대학부속병원 안과를 방문한 청소년 환자 100명을 대상으로 50명의 환자를 OK렌즈군과 단초점 안경군으로 나누었다. 두 그룹의 환자 모두 1년 동안 추적관찰하여 시력(VA), 구면등가굴절 (SE), 안축 길이(AL), 각막 내피 세포 수(CEC), 중심 각막 두께(CCT) 및 압력(IOP)의 변화를 비교하였다. 통계분 석은 SPSS 소프트웨어를 이용하여 독립표본 T-test로 데이터를 분석하였으며, p<0.050을 통계적으로 유의한 것 으로 간주하였다. 결과 : Euclid Orthokeratology(OK)렌즈를 착용한 환자의 시력이 서서히 향상되었으나, 단초점 안경을 착용한 환자들은 시력이 감소하는 추세를 보였으며, 두 그룹 간의 차이는 통계적으로 유의하였다(p<0.010). 굴절검사 결과 는 OK 렌즈를 착용한 후 굴절이상이 유의하게 감소하였으며, 안경을 착용한 환자들은 굴절이상이 증가한 것으로 나타났다. 두 그룹 간의 차이는 통계적으로 유의하게 증가하였다(p<0.010). 또한, 안축 길이의 분석 결과, OK 렌 즈를 착용한 환자들의 안축 길이는 기준값 대비 0.18±0.18 mm 증가하였고, 안경을 착용한 환자들의 안축 길이는 기준값 대비 0.61±0.20 mm 증가하였다. 두 그룹 간의 차이는 통계적으로 유의하게 증가하였다(p<0.001). OK 렌즈를 착용한 환자들은 안압, 각막 내피 세포 수 및 중심 각막 두께에서 기준값 대비 유의한 변화가 없었다 (p>0.050). 결론 : 안경 대비 각막교정렌즈가 구면 등가 구면굴절력(SE)를 감소시키고 시력을 향상시켰으며, 안축 연장을 늦추는데 더 효과적임을 알 수 있었다.

본 연구는 거리화단 화훼경관 조성 전·후의 스트레스 변화 를 알아보기 위하여, 순창 소재의 경찰관 총 18명을 대상으로 타액 채취 및 설문조사를 실시하였다. 생리 측정은 타액 코르 티솔, 혈압, 심리 측정은 식물 재배 활동 수준, 스트레스수준, 거리화단 화훼경관에 대한 간이 SD 감성을 측정하였다. 타액 코르티솔, 혈압의 사전/후 비교는 대응표본 t-test, 타액 코르 티솔, 혈압의 성별에 따른 집단간 사전/후 비교는, 독립표본 t-test, 스트레스수준, 간이 SD는 윌콕슨 부호 순위 검정 등으 로 분석하였다. 화훼경관 조성 전보다 조성 후 총 코르티솔 수 치가 낮아졌고, 식물 재배 활동 수준은 높아졌으나 통계적 유 의성은 없었다. 혈압은 여자의 경우 거리화단 화훼경관 조성 전과 조성 후 모두 정상 혈압이었고, 남자의 경우 거리화단 화 훼경관 조성 전 고혈압 전단계에서 조성 후 주의혈압으로 낮 아지는 긍정적 효과가 있었다. 거리화단 화훼경관 조성 전·후 의 스트레스수준을 총 4단계(총 4단계: 단계가 높을수록 스트 레스가 높은 수준임)로 문항 전체의 총합 수치로 알아본 결과, 화훼경관 조성 전에는 4단계(50.0%), 2단계(38.9%), 3단계 (11.1%) 순이었으나, 조성 후에는 4단계(44.5%), 2, 3단계(각 22.2%), 1단계(11.1%) 순으로 거리화단 화훼경관 조성 전에 는 1단계(정상적인 스트레스 상태로 스트레스요인 자체가 심 각하지 않거나 좋은 스트레스로 받아들인 경우)가 0%에서 조 성 후 11.1%로 높아졌다. 화훼경관 조성 전·후 SD법을 이용 하여 쾌적감, 자연감, 그리고 진정감에 대해 평가한 결과, 화 훼경관 조성 후 쾌적감, 자연감, 진정감이 높은 것으로 나타났 다(p<.05). 거리화단 화훼경관에 따른 식물 재배 활동 수준과 주요 변수간의 상관관계를 알아본 결과, 화훼경관 조성 후 식 물 재배 활동 수준과 스트레스수준, 스트레스수준과 진정감은 부(-)의 상관관계, 식물 재배 활동 수준과 쾌적감, 자연감, 진정 감과는 0.5 이상의 높은 정(+)의 상관관계가 있었다(p<.05). 따라서 식물 재배 활동 수준이 높아질수록 쾌적감, 자연감, 그 리고, 진정감은 높아지고, 거리화단 화훼경관이 없는 공간보 다 화훼경관이 있는 공간에서 쾌적감, 자연감, 그리고 진정감 을 더 크게 느끼는 것으로 판단되었다. 본 연구에서 거리화단 화훼경관을 통하여 고위험군의 높은 스트레스는 줄여주고 식 물에 대한 흥미, 관심과 심리적 안정효과는 높여 줄 수 있는 유용한 가능성이 있을 것으로 생각되었다.

Rice ratooning is the cultural practice that easily produces secondary rice from the stubble left behind after harvesting the main crop. ‘Daol’ is an extremely early growing rice variety. Planting this variety early allows for an additional ratoon harvest after the primary rice harvest. The plant growth and yield of ratoon rice were very low compared to those of main rice. Protein, amylose content, and head rice rate were higher in ratoon rice than in main rice. The distribution by the rice flour particle size of main and ratoon rice was similar. The damaged starch content in ratoon rice was relatively high at 6.1%. Ratoon rice required a longer time and higher temperature for pasting than main rice. Compared to the original rice, peak viscosity (PV), hot paste viscosity (HPV), cool paste viscosity (CPV), and breakdown (BD) were very low, and setback (SB) was high. As a result of analyzing the gelatinization properties of main and ratoon rice using differential calorimetry, it was found that the onset (To), peak (Tp), and conclusion (Tc) of ratoon rice starch were processed at a lower temperature than those of main rice. The gelatinization enthalpy of both samples was similar. The distribution of amylopectin short chains in ratoon rice was higher than that in main rice.

현대사회는 인터넷과 스마트 기기의 발달로 모든 세대에게 게임을 포함한 디지털 미디어 이용이 보 편화 되었다. 인터넷은 시간과 공간을 초월하고 세대를 넘어서 인간과 정보를 연결한다. 스마트폰의 보급으로 누구나 인터넷에 쉽게 접근하게 되어 미디어 이용이 더욱 증가하고 있다. 스마트폰은 접 근성이 좋고 시간과 장소에 구애 없이 사용할 수 있어서 게임을 포함한 미디어중독에 노출될 수 있 다. 수많은 스마트폰 어플리케이션은 인터넷 세계로 이끄는 요인이 된다. 아버지의 일-가정 양립은 양육스트레스를 증가시키고, 양육스트레스는 게임을 포함한 인터넷과 스마트폰 중독을 예측하는 중 요한 요인이다. 부모의 미디어중독이 자녀의 인터넷 게임중독에 영향을 미치는 측면이 있으므로 아 버지의 미디어중독에 대하여 살펴볼 필요가 있다. 본 연구는 아버지의 양육스트레스와 미디어중독 의 관계에서 부부갈등의 매개효과를 살펴보는 데 목적이 있다. 이를 위해 한국육아정책연구소에서 제공하는 한국아동패널 13차 조사자료를 사용하였다. 자료는 SPSS 27.0 프로그램과 Process macro 4.1 을 사용하여 분석하였다.

The Wolsong unit 1 decommissioning project is the world’s first commercial pressurized heavy water reactor decommissioning project. Although there is a lot of accumulated experience and technology for decommissioning of pressurized water reactors around the world, it can be said that there is great difficulty as there is lack of prior experience and reference materials for pressurized heavy water reactor. On the other hand, if the world’s first pressurized heavy water reactor project is completed, it is possible to enter the overseas market for pressurized heavy water reactor decommissioning. It is also a good opportunity to do so. Accordingly, the current status of operation, plans, and construction of infrastructure related to decommissioning of pressurized heavy water reactors in Canada, which can be said to be the home country of pressurized heavy water reactor, were reviewed. So, this study seeks to present considerations for entering the pressurized heavy water reactors decommissioning market in the future.

Kori unit 1 and Wolsong unit 1 were permanently shut down in 2017 and 2019, respectively. Both plants were decided to demolish the building without reuse. Large structures must be demolished after removing systems and components in the building, and in the case of large structures, thorough planning is required because of the large scale of work. Therefore, in this study, important considerations in the phase of the demolition plan of large structures when decommissioning were analyzed. The demolition of large structures at nuclear facilities is major one phase of work within a broader decommissioning plan. Furthermore, the actual demolition of the structure (i.e., physical process) represents the last step in a process that begins with extensive planning and analysis. The National Demolition Association (NDA) has provided checklist items that should be considered before the start of a commercial demolition project and/or in the bid process. Important Considerations in the Phase of the demolition plan of large structures when decommissioning of nuclear facilities are Site knowledge and programs, Engineering survey/demolition plan, Hazardous and radioactive materials, Open air demolition, Financial and project management, Permits, Code adherence, and Special programs, Disposal pathway, Final site condition. The results of this study can be used as a basis for the Planning large structures demolition of the Kori unit 1 and Wolsong unit 1.

The type of radioactive waste that may occur in the process of nuclear power plant dismantling can be classified into solid, liquid, gas, and mixed waste. The amount of these wastes must be defined in the Final Decommissioning Plan for approval of the licensing. Also, in the case of Metal radioactive waste, it is necessary to calculate the generation amount in order to treat radioactive waste at a Radioactive Waste Treatment Facility (RWTF). Since a large quantity of metal radioactive waste is generated during the decommissioning of a nuclear power plant, the application of a metal melter for reduction is considered. The metal waste is heated to a temperature above the melting point and separated into liquid and gas forms. Nuclides existing on the surface of metal waste vaporize in a melting furnace to become dust or collect in sludge. Nonvolatile nuclides such as Co, Fe and Mn remain in ingot, but other nuclides can be captured and reduced with dust and sludge. And the types of melting furnaces to be applied can be broadly classified into Atmospheric Induction Melter (AIM) and Vacuum Induction Melter (VIM). Therefore, this review intends to compare the two types of metal furnaces to be included in RWTF.

Activated carbon (AC), extensively used across various industrial sectors, serves as a sponge for different types of gases due to its porous carbon material. These gases are attracted to the carbon substrate via van der Waals forces. In nuclear power plants, AC is commonly used to adsorb radioactive gases such as 86Kr and 134Xe, as well as radioiodine sources like 131I and 133I from gaseous effluents. Even if the adsorbed radioactive gases and radioiodine decay into non-radioactive elements, the spent AC still contains radioactive species with long half-lives, such as 3H (Tritium, T) and 14C (radiocarbon). Minimizing and separating waste that contains long-lived nuclides (e.g., 14C) are pivotal components of an efficient waste management approach. A challenging aspect of effectively managing disposed AC is to minimize long-lived radioactive substances by eliminating them. This paper explores and summarizes the technology used to remove pollutants (3H, 14C) trapped within the pores of Activated carbon through thermochemical vacuum and surface oxidation processes. By recycling and reusing spent Activated carbon, we anticipate a reduction in the volume of radioactive waste, leading to decreased disposal costs. Furthermore, this paper will contribute as a valuable reference in future studies, enhancing the understanding of vacuum thermal desorption and surface oxidation of used Activated carbon.

Bentonite, primarily composed of montmorillonite, plays a crucial role as one of the engineering barrier materials in a deep geological repository (DGR). The advantageous properties of montmorillonite, such as its swelling capacity, low permeability, and low thermal conductivity, make it a key component as a buffer material for isolating high-level radioactive waste from the surrounding natural environment. It has been known that the stability of montmorillonite is influenced by a wide range of pressure-temperature-composition (P-T-X) conditions relevant to the DGR environment. When considering potential geological events, of notable concerns are its interactions with groundwater or seawater at elevated temperatures, leading to safety hazards within the system. In this study, therefore, we investigated the hydration and dehydration reactions of Ca-montmorillonite with saline fluids such as NaCl and KCl solutions at elevated pressures and temperatures by conducting in-situ X-ray diffraction experiments using both a capillary sample heating cell and a resistive-heated diamond anvil cell. As a result, we observed different hydration states of montmorillonite depending on the chemical composition of fluids, i.e., tri-hydrated layers in NaCl and bi-hydrated layers in KCl solutions, respectively. Furthermore, we identified that montmorillonite undergoes distinct stepwise dehydration with increasing temperature, and the dehydration temperature of montmorillonite significantly increases with increasing water pressure. Consequently, this study would provide insights into the stability of hydrated montmorillonite in a seawater-dominated fluid environment and its implications for the long-term safety of the disposal system.

The mobility of uranium (U) in various disposal environments of a deep geological repository is controlled by various geochemical conditions and parameters. In particular, oxidation state of uranium is considered as a major factor to control the mobility of uranium in most of geological environments. In this study, therefore, we investigated the geochemical behaviors of uranium in grounwater samples from natural analogue study sites located in the Ogcheon Metamorphic Belt (OMB). Groundwater samples were taken using a packer system from Boeun Hoenam-myun site and Geumsan Suyoung-ri site where several boreholes were dilled with various depths. The geochemical properties and parameters such as temperature, pH, Eh, EC, and DO were directly measured in the site using an in-line measurement method. The concentrations of major cations and anions in the groundwater samples were measured by using ICP-OES (Inductively Coupled Plasma-Optical Emission Spectrometry) and IC (Ion Chromatography), respectively. The concentrations of trace elements including U and Th were measured by using ICP-MS (Inductively Coupled Plasma-Mass Spectrometry) The concentrations of U in the groundwater samples are very low for the Hoenammyun site (0.03~0.69 ppb) and Suyoung-ro site (0.39~1.74 ppb) even though the two sites are uranium deposits and redox conditions are weakly oxidizing. The speciation, saturation index (SI), pH-Eh (Poubaix) diagram were calculated using the Geochemist’s Workbench (GWB 9.0) program and the recent OECD/NEA thermochemical database for U. Calculation results for U speciation in the groundwater samples show that major dissolved uranium species in the groundwater samples are mainly as calcium uranyl carbonate complexes such as Ca2UO2(CO3)3(aq) and CaUO2(CO3)3 2- for almost all groundwater samples. The calculated results for SI and Poubaix diagram also show that the dominant uranium solid phase is a uranyl silicate mineral, uranophane (Ca(H2O)(UVIO2)2 (SiO2)2(OH)6), not uraninite (UIVO2). Since the determination of Eh values for natural groundwater samples is very difficult and uncertain work, we analyzed and discussed the effect of Eh on the geochemical behaviors of U in the groundwater. However, these calculation results are not consistent with the observation for U minerals in rock samples using electron microscopic techniques. Thus, we need further studies to explain the discrepancy between calculation and observation results.

This study aimed to provide better understanding of the bedrock aquifer bacterial communities and their functions in deep geological repository (DGR) environment. Two study sites of uranium deposits in the Ogcheon Metamorphic Belt were selected: Boeun and Guemsan. From two study sites, six groundwater samples were obtained with different boreholes and depths: OB1 (Boeun, 25 m), OB3 (Boeun, 80 m), GS1 (Guemsan, 25 m), GS2 (Guemsan, 85-90 m), GS3-I (Guemsan, 32- 38 m), GS3-II (Guemsan, 70-74 m). The physicochemical properties of groundwater were analyzed by multi-parameter sensors, ion chromatography (IC), and inductively coupled plasma optical emission spectroscopy (ICP-OES). Illumina Miseq sequencing was performed to investigate bacterial community in six groundwater samples. In addition, the number of sulfate-reducing bacteria (SRB) was quantified by a quantitative PCR (qPCR). Bacterial community composition varied in response to boreholes and depths. A total of 14 different phyla and 36 classes were detected from six groundwater samples. Overall, Proteobacteria, Actinomycetota, and Bacteroidota were dominant in the phylum level. SRB and iron-reducing bacteria (IRB) were detected in all groundwater samples even though organic carbon sources were not abundant (0.7-3.3 mg-total organic carbon/L). This result shows a potential to immobilize uranium in DGR environment. In particular, SRB, Desulfosporosinus fructosivorans and Humidesulfovibrio mexicanus were mainly detected in GS1 and GS2 groundwater samples, which attributed to higher dissimilatory sulfite reductase functional gene copy number in GS1 and GS2 groundwater samples. Statistical analysis was performed to understand the correlation between environmental factors and core bacterial species. Dissolved oxygen (DO), Fe, and Mn concentrations were positively correlated with Curvibacter fontanus while Undibacterium rivi had a negative correlation with pH. These results indicate that bacterial community could be changed in response to environmental variation. Further study with a greater number of samples is necessary to obtain statistically reliable and meaningful results for a safe DGR system.

Uranium (U) is a hazardous material that can lead to both chemical and radiological toxicity, including kidney damage and health issues associated with radiation exposure. In South Korea. In Korea, where shallow weathered granitic aquifers are widespread, several previous studies have reported high levels of radioactivity in shallow groundwater. This ultimately led to the closure of 60 out of 4,140 groundwater production wells in South Korea. In this study, we examined aquifers currently dedicated to drinking water supply and investigated a dataset of 11,225 records encompassing 103 environmental parameters, based on the random forest classifier. This dataset comprises 80 physical parameters associated with the hydraulic system and 23 chemical parameters linked to water-rock interactions. Among the hydraulic parameters, the presence of a coarse loamy texture in the subsoil displayed a notable positive relationship with the concentration of uranium, implying that it plays a significant role in forming redox conditions for the leaching of uranium from host rocks. Fluorine (F), a major product of water-rock interaction in granitic aquifers, exhibited a positive correlation with the distribution of uranium concentrations. The positive relationship between F concentration and uranium levels suggests that the dissolved uranium originates from groundwater interacting with granites. In conclusion, our findings indicate that two key factors, namely the infiltration capacity of soil layers and the aqueous speciation in groundwater resulting from interactions with local solids, play important roles in determining uranium concentrations in granitic aquifers.

One of released radioactive gases from a spent fuel is cesium (137Cs) as semi-volatile fission products and reticulated ceramic foam could be used for capturing the gaseous cesium. It has threedimensional open-pore structures and consumes cesium above 600°C to form cesium species including Cs-nepheline (CsAlSiO4) and pollucite (CsAlSi2O6) phases. Kaolinite-based foam filter is a favorable ceramic filter because they exhibit superior capture characteristics compared to other aluminosilicate minerals and other shape filters. However, for usage in special conditions, structural limitations such broken struts must be improved. Here, recoating by using centrifugation, followed by a pre-sintering cycle was conducted for covering the cracks and voids, resulting from the burnout of the polyurethane sponge as a sacricial template. The slurry including additives was chosen by considering viscous behavior of slurries for the centrifugation. The microstructure and strength was improved by the recoating.

Reticulated foams have a continuous skeleton network consisting of aluminosilicates and are used for capturing gaseous cesium released from spent nuclear fuel at high temperature. It has high stability to high temperature and good capturing performance. Homogeneous cell distribution and modified surface structures are indispensable conditions for stable operation and handling. In particular, triangularly shaped holes inside the struts were generated during the pyrolysis of polyurethane sponge as a sacricial template, which lead to limite the strength of the reticulated foam as well as cracks. However, several attempts have been focused on the increasing the strut thickness. Here, we have prepared ceramic foams by the polyurethane sponge replication method with roller squeezing. Ceramic slurry including additives was determined with consideration of its viscous behavior. After pre-sintering, infiltration under vacuum was conducted. Metakaolin slurry was filled partially into the triangular void. As a result, the compression strength was improved by structure modification without composition change.

The potential use of cost-effective carbon anodes, as an alternative to expensive platinum, in the reduction of oxides within LiCl-Li2O molten salt at elevated cell potentials presents a promising avenue. However, this elevated potential gives rise to the generation of a complex mixture of anodic gases, including hazardous and corrosive species such as chlorine (Cl2), oxygen (O2), carbon monoxide (CO), and carbon dioxide (CO2). In this study, we investigate the influence of applied potential and salt composition on the composition of the generated gas mixture. Real-time gas analysis was conducted during the TiO reduction reaction in the molten salt at 650°C using a MAX-300-LG gas analyzer. Simultaneously, electronic signals, including current, potential, and salt composition, were monitored throughout the oxide reduction process. Additionally, XRD investigations were performed to verify the crystal structure of the resulting products. This research provides valuable insights into optimizing carbon anode-based reduction processes for improved efficiency and safety.

Pyroprocessing is a crucial method for recovering nuclear fuel materials, particularly uranium and transuranic elements (TRU), through electrochemical reactions in a LiCl or LiCl-KCl molten salt system, which is highly stable medium at elevated temperatures. In the electrochemical reduction stage, actinide metal oxides are effectively transformed into their metallic forms and retained at the cathode within a molten LiCl-Li2O environment at 650°C. Simultaneously, oxygen ions (O2-) are generated at the cathode and then transported through the molten salt to be discharged at the anode, where they combine to form oxygen gas (O2) on the anode’s surface. One notable challenge in this electrochemical process is the generation of various byproducts during the anode oxide reduction step, including oxygen, chlorine, carbon dioxide, and carbon monoxide. Consequently, significant amounts of corrosion products tend to accumulate on the upper region of the anode’s immersion area over time. This report introduces a novel solution to mitigate corrosion-related challenges within the specified temperature range. We propose a selective oxidation treatment for the NiCrAl-based 214 Haynes alloy, involving exposure to 1,100°C in a reducing atmosphere. The objective is to stimulate the growth of protective α-Al2O3 scales on the alloy’s surface. The resulting oxide scales have undergone thorough characterization using SEM, EDS, and XRD techniques. The pre-grown alumina scale has demonstrated commendable adherence and thermal stability, even when subjected to a chlorine-oxygen mixed atmosphere at the specified temperature.

This study examined the heat balance in the electrolytic reducer during oxide reduction of pyroprocessing. The adoption of carbon anodes instead of conventional platinum anodes in the oxide reduction process has made it possible to apply high currents, and it has been observed that the temperature of the molten salt of in the reactor rises rapidly when applying high currents, so it is important to maintain an optimal operational temperature range. In this study, salt resistant heat, reaction heat, and decay heat were identified as factors affecting heat balance during the operation of oxide reduction process. Equations describing the relationships among these factors were established. Then using this, a correlation was developed to understand the relationship between applied current and the molten salt temperature in the reactor observed in the actual operation of the carbon anode electrolytic reducer of KAERI. Furthermore, this study proposed strategies to mitigate excessive temperature elevation during oxide reduction operation. A comparative assessment of these approaches was conducted. Considering KAERI electrolytic reducer operation environment, among the considered cooling strategies, the cooling effectiveness was calculated to be highest in the following order: heat transfer to extra salt, convection, conduction, argon gas bubbling.

In pyroprocessing, the residual salts (LiCl containing Li and Li2O) in the metallic fuel produced by the oxide reduction (OR) process are removed by salt distillation and fed into electrorefining. This study undertook an investigation into the potential viability of employing a separate LiCl salt rinsing process as an innovative alternative to conventional salt distillation techniques. The primary objective of this novel approach was to mitigate the presence of Li and Li2O within the residual OR salt of metallic fuel, subsequently facilitating its suitability for electrorefining processes. The process of rinsing the metallic fuel involved immersing it in a LiCl salt environment at a temperature of 650°C. During this immersion process, the residual OR salt contained within the fuel underwent dissolution, thereby reducing the concentrations of Li2O and Li generated during the OR process. Furthermore, the Li and Li2O dissolved within the LiCl salt were effectively consumed through chemical reactions with ZrO2 particles present within the salt. Importantly, even after the metallic fuel had been subjected to rinsing in a conventional LiCl salt solution, the concentration of Li and Li2O within the salt remained consistent with its initial levels, due to the utilization of ZrO2. Moreover, it was observed that the Li- Li2O content within the metallic fuel was significantly diluted as a result of the rinsing process.

In compliance with the amended export control of strategic items and technology in Jan. 2014, KAERI should pay attention to the export control of ITT (Intangible Technology Transfer). To control an ITT (Intangible Technologies Transfer) effectively and efficiently, the Korean government encourages the R&D institute and universities obtaining the ICP (Internal Compliance Program) from the relevant authority, MOTIE. This means that the exporters can control the ITT by themselves, because the exporters know very well the counterparts of the trading and the exporting items and technologies. In fact, ICP is for export control of dual-use items and technology in Korea. However, KAERI has tried to obtain a license from the authority, MOTIE. In an effort to do so, KAERI completed enacting a new internal self–regulation for export controls in 2016, and proceeded to apply for an ‘AA’ license of ICP in 2017 and obtained the ICP license in 2018 and re-obtained the license in 2021 from the MOTIE. In light of KAERI’s case, to obtain the ‘AA’ license of ICP is one of the best methods to increase the ability of export controls. As of now, there is no R&D institutes sponsored by the Korean government to obtain the ‘AA’ license of ICP except KAERI. KAERI can provide the actual methods as a standard case to the R&D institutes in Korea for obtaining an ‘AA’ license of ICP. According to the internal regulation of KAERI for export control, KAERI implemented an inner self-audit for export control in Nov. 2022. This is the first real self-audit for export control at KAERI. The main purpose of the self-audit is to check the transfer management of ITT and the relationship of relevant office through the interview of the staffs in the ICP organization. KAERI self-audit planed specifically and implemented for the achievement of the basic principal of selfaudit. The specific contents of this self-audit is as follows - The interview of the relevant offices: physical protection office, manpower planning office, manpower management office, nuclear education and training center, technology transfer office and international cooperation office, nuclear control and management office - Building the self-audit checklist considering the characteristics of each office - The confirmation of the inner procedure and the status of management on the export controls Through the interview of the relevant office, KAERI checked the inner procedure and the status of management on the export controls and tried to provide the supplementary measures of each relevant offices. The followings are the main results of the inner self-audit implemented in Nov. 2022. - Generally, the staffs know the meaning and relevant regulation such as foreigner’s management and the intangible technology transfer - Each office reflects the necessities of export controls on the relevant regulation and procedures and make DB for the proper duty. However, there is no indication for export controls on the DB - In the case of foreigner’s temporary visit for simple work and site tour, there is a difficult situation not to be able to check all the visitors by checking the denial lists - If necessary, KAERI may build the TFT (Task force Team) for the efficiency of export controls - Others

Microbes in insect gut significantly influence host physiology. While Lepidoptera is a diverse insect order, the relationship between microbial symbiosis and host development remains elusive, especially concerning role of gut-colonizing bacteria in metamorphosis. We investigated the gut microbial diversity in Galleria mellonella throughout its life cycle using 16S rRNA amplicon sequencing. Our findings revealed a predominance of Enterococcus spp. in larvae and Enterobacter spp. in pupae. Remarkably, removing Enterococcus spp. hastened the larval-to-pupal transition. Transcriptome analysis showed an upregulation of immune response genes in pupae and hormone genes in larvae. Notably, the production of antimicrobial peptides in the host gut varied with developmental stages. Some of these peptides suppressed the growth of Enterococcus innesii, a dominant gut bacterium in G. mellonella larvae. This research underscores the pivotal role of gut microbiota shifts in metamorphosis, driven by the secretion of antimicrobial peptides in the G. mellonella digestive system.