For the release of the nuclear power plant site after the decommissioning, a reliable exposure dose assessment considering the environmental impact of residual radionuclides is essentially required. In this study, the Derived Concentration Guideline Level (DCGL) for the hypothetically contaminated surface soil at the Wolsong nuclear power plant (NPP) unit 1 site was preliminarily calculated by using the RESRAD-OFFSITE computational code and compared with the other case studies. Moreover, radiation exposure dose for local residents and relevant exposure pathways were quantitatively analyzed based on the calculation model established through this work. For the target site modeling, the source term was determined by referring to the previous case studies regarding the nuclear power plant decommissioning, quantification analysis data of pressure tubes of Wolsong NPP unit 1, and radionuclide data estimated by using the MCNP/ORIGEN-2 code. In total, 14 different radioisotopes such as Ag-108m, C-14, Co-60, Cs-134/137, Fe-55, H-3, Nb-93m/94, Ni-63, Sb-125, Sn-121m, Sr-90, and Zr-93 were considered as target radionuclides. In addition, the geological structure model of the Wolsong NPP site was established based on the final safety analysis report of Wolsong NPP unit 1. The distribution coefficients (Kd) were taken from the JAEA-SDB to estimate the migration/retardation behavior of various radionuclides under the groundwater condition of the Wolsong NPP site. In the present work, the DCGL values were calculated according to the site release criterion of 0.1 mSv/yr, which indicates the radiation protection standard for the site release. Moreover, the exposure pathway and sensitivity analyses were conducted to assess the sensitive input parameters remarkably influencing the calculation result. For the evaluation of exposure dose for local residents, a site layout centered around Wolsong NPP unit 4, located in the closest proximity to the residents’ habitation area, was alternatively established and all potential exposure pathways were considered as a comprehensive resident farmer scenario. The results obtained from this study are expected to serve as a preliminary case study for the DCGL values regarding the surface soil at the Wolsong NPP unit 1 site and for evaluating the radiation exposure dose to local residents resulting from the residual radioactivity at the site after the decommissioning.

The decommissioning of domestic Nuclear Power Plants (NPPs) in Korea is expected to begin with the Kori-1, which was permanently shutdown in 2017. In addition, Wolsong-1 has been also permanently shutdown, and another type will be the decommissioning project following Kori-1. KHNP is promoting operation and decommissioning projects as the owner of NPPs, and the Central Research Institute (CRI) has been developing a Final Decommissioning Plan (FDP) for the decommissioning license document. The FDP consists of 11 major chapters in the order of overview of the project, characteristic evaluation, safety assessment, radiation protection, decontamination & dismantlement activities, waste management, etc. The contents described in each chapter are individual chapters, but there are also parts that consider the connection with other chapters. The CRI, which develops the FDP for the first decommissioning project in Korea, has spent a lot of time and effort considering this and has been proceeding through trial and error until the present stage. Therefore, this study aims to explain the current status of FDP, a license document for domestic decommissioning projects, and the link between major input data in major chapters. It can be said that System, Structure, and Components (SSCs) subject to dismantling are considered as the scope of FDP. Chapters that perform estimations on these dismantling targets may include safety assessments, exposure dose assessments for workers and residents, and waste inventory assessments. Therefore, an important part of performing the estimation works is to consider the entire scope of decommissioning activities, and as a way, it can start from data based on the inventory data. After generating the inventory data, the waste treatment classification for the inventory is designated by reflecting the results of the characterization. In addition, for cost estimation, the cost of decommissioning project is predicted by inputting some data (i.e., UCF) such as work process, number of workers, and time required for each item with data reflected in quantity and characterization. After that, based on these inventory, characterization, and UCF data, accident scenarios and industrial safety evaluation are performed for the safety assessment. The worker exposure dose is estimated by considering the dose rate of the workspace with these data. In the case of the amount of waste, the final amount of waste is estimated by considering the factors of reduction and decontamination. In summary, the main estimation contents of FDP are evaluated by adding elements required for the purpose of each chapter from data combined with inventory, characterization, and UCF, so the contents of these chapters are based on the logic of considering the entire scope of decommissioning in common.

The nuclear facilities at Korea Atomic Energy Research Institute (KAERI) have generated a variety of organic liquid radwaste and radiation levels are also varied. At KAERI, the organic liquid radwaste has been stored at Radioactive Waste Treatment Facility (RWTF) temporarily due to the absence of the recognized treatment technique while inorganic liquid radwaste can be treated by evaporation, bituminization, and solar evaporation process. The organic liquid radioactive waste such as spent oil, cutting oil, acetone, ethanol, etc. was generated from the nuclear facilities at KAERI. Among the organic liquid radioactive wastes, spent oil is particularly significant. According to the nuclear safety act, radioactive waste can be cleared by incineration and landfilling if it meets the criteria of less than 10 μSv/h for individual dose and 1 person – Sv/y for collective dose. Dose assessment was performed on some organic liquid radioactive waste with a very low possibility of radioactive contamination stored in RWTF at KAERI. As a result, it was confirmed that some wastes met the regulatory clearance standards. Based on this, it was approved by the regulatory body, and this became the first case in Korea and KAERI for permission for regulatory clearance of organic liquid radioactive waste by landfill after incineration.

The decommissioning of Korea Research Reactor Units 1 and 2 (KRR 1&2), the first research reactors in South Korea, began in 1997 and the decommissioning status is currently proceeding with phase 3. It is expected that more than 5,000 tons of dismantled wastes will be generated as the contaminated building is demolished. Since these dismantled wastes must be disposed of in an efficient method considering economic feasibility, it is desirable to clearance extremely low-level wastes whose contamination is so minimal that the radiological risk is negligible. In Korea, in order to approve the clearance of radioactive waste, it must be proven that the nuclide concentration standards are met or that the dose to individuals and collectives is below the allowable dose value. At the KRR 1&2 decommissioning site, dismantled wastes have been steadily being disposed of through clearance procedure since 2021. Clearance was approved by the Korean Institute of Nuclear Safety (KINS) for one case of concrete waste in 2021 and two cases of metal waste in 2022. In 2023, the clearance of metal waste and asbestos waste has been approved so far, and in particular, this is the first case in Korea for asbestos waste. In this study, we compared the dose assessment methods and results of clearance wastes at the KRR 1&2 decommissioning site from 2021 to present. Dose assessment was conducted by applying the landfill scenario for concrete and asbestos and the recycling scenario for metal waste. The calculation codes used were RESRAD-onsite 7.2 and RESRAD-recycle 3.10. The dose conversion factors (DCF) for each age group (infant, 1y, 5y, 10y, 15y, adult) of the target nuclide used the values presented in ICRP-72, and in particular, geo-hydrological data of the actual landfill site was used as an input factor when evaluating landfill scenarios. As a result of the dose assessment, when landfilling concrete wastes in 2020, the personal dose and collective dose were evaluated the most at 2.80E+00 μSv/y and 4.83E-02 man·Sv/y, respectively.

Recently, the nuclear decommissioning and environmental restoration industries has significantly attracted as a new industry field due to the decision to decommission the KORI#1 and WOLSONG #1 nuclear power plant. In order to dispose of the decommissioning radioactive wastes generated during nuclear decommissioning, proper analysis is required, and disposal decisions are determined based on the analysis results. When dismantling a nuclear power plant, a few thousand of tons decommissioning waste are produced, so these require analysis for proper disposal. Therefore, a radionuclide facility for decommissioning waste analysis is essential for the disposal of the large quantities of decommissioning waste generated during nuclear power plant decommissioning. Korea Research Institute of Decommissioning (KRID) was established radionuclide analysis facilities to address above issues and support nuclear power plant decommissioning projects. The plan is to perform classification by type and radionuclide for all waste produced during nuclear power plant decommissioning and to support the disposal of radioactive wastes. In addition, we plan to establish validation methods for samples where verification methods are not established, in order to conduct efficient analysis and management. In this presentation, we will introduce the radionuclide facility currently under construction at KRID and present the space design, equipment layout, and utilization plans.

Kori Unit 1 was permanently shut down in 2017 and is currently being prepared for decommissioning. Decommissioning waste generated during the decommissioning of a nuclear power plant has the characteristic of being generated in large quantities over a short period. Therefore, if proper management is not carried out, abnormal situations (i.e., unauthorized disposal, diversion, etc.) may occur. According to IAEA General Safety Report Part 6, radioactive waste shall be managed for all waste streams in decommissioning. This means ensuring that all waste streams are managed by the recorded inventory of all decommissioning waste and verifying that the recorded inventory is reasonable. The radioactive waste management has been managed in units such as mass and radioactivity. However, in the case of decommissioning waste, the amount is very large, so management by radioactivity is expected to have limitations. Therefore, in this study, a simple test was conducted to verify the decommissioning waste generated by a hypothetical scenario by mass. In this study, establish a scenario assuming various flows of decommissioning waste expected to be generated and calculate the expected inventory of decommissioning waste using Microsoft Excel. Specifically, using “Material Unaccounted For” (MUF), a material balance equation in IAEA Services Series 15, Nuclear Material Accounting Handbook, the error inventory was calculated as the difference between the physical inventory of decommissioning waste in the area and the ending inventory. We propose a simple test scenario to verify the flow of decommissioning waste by verifying that the error inventory reasonably matches the set allowable error. This study aims to verify the inventory of decommissioning waste using the material balance methodology used for nuclear material accounting. It is expected that the safety and reliability of the nuclear power plant decommissioning process can be secured by verifying that the total inventory of equipment before decommissioning and the inventory of remaining equipment and decommissioning waste after decommissioning are reasonably consistent.

There is a large amount of radioactive waste in waste storage in the Korea Atomic Energy Research Institute. Some of the radioactive waste was generated during the dismantling process due to Korea Research Reactor 1&2 and it accounts for 20% of the total waste. Radioactive waste must be reduced by appropriate disposal methods to secure storage space and to reduce disposal costs. Research Reactor wastes include wastes that are below the acceptable criteria for selfdisposal and non-contaminated wastes, so they can be treated as wastes subject to self-disposal through contamination analysis and reclassification. In order to deregulation radioactive waste, it is necessary to meet the self-disposal standards stipulated in the Domestic Nuclear Act and the treatment standards of the Waste Management Act. The main factors of deregulation are surface contaminant, radionuclide activity and dose assessment. To confirm the contamination of waste, surface contaminant and gamma nuclide analysis were performed. After homogenizing the waste sample, it was placed in 1 L Mariinelli beaker. When collecting waste samples, 1 kg per 200 kg of waste was collected. The concentrations of the major radionuclides Co-60, Cs-134, Cs-137, Eu-152, and Eu-154 were analyzed using HPGe detector. To evaluate radiation dose, various computational programs were used. A dose assessment was performed with the analyzed nuclide concentration. The concentrations of representative nuclides satisfied the deregulation acceptance criteria and the results of the dose assessment corresponding to self-disposal method was also satisfied. Based on this results, KAERI submitted the report on waste self-disposal plan to obtain approval. After final approval, Research Reactor waste is to be incinerated and incineration ash is to be buried in the designated place. Some metallic waste has been recycled. In this study, the suitability of deregulation for self-disposal was confirmed through the evaluation of the surface contaminant analysis, radionuclide concentration analysis and dose assessment.

We conducted safety assessments for the disposal of spent resin mixed waste after the removal of beta radionuclides (3H, 14C) in a landfill facility. The spent resin tank of Wolsong nuclear power plant is generated by 8:1:1 weight ratio of spent ion exchange resin, spent activated carbon and zeolite. Waste in the spent resin tank was classified as intermediate-level radioactive waste due to 14C. Other nuclides such as 60Co and 137Cs exhibit below the low-level radioactive waste criteria. The techniques for separating mixed waste and capturing 14C have been under development, with a particular focus on microwave-based methods to remove beta radionuclides (3H, 14C) from spent activated carbon and spent resin within the mixed waste. The spent resin and activated carbon within the waste mixture exhibits microwave reactivity, heated when exposed to microwaves. This technology serves as a means to remove beta isotopes within the spent resin, particularly by eliminating 14C, allowing it to meet the low-level radioactive waste criteria. Using this method, the waste mixture can meet disposal requirements through free water and 3H removal. These assessments considered the human intrusion scenarios and were carried out using the RESRAD-ONSITE code. The institutional management period after facility closure is set at 300 years, during which accidental exposures resulting from human intrusion into the disposal site are accounted for. The assessment of radiation exposure to intruders in a landfill facility included six human intrusion scenarios, such as the drilling scenario, road construction scenario, post-drilling scenario, and post-construction scenario. Among the six human intrusion scenarios considered, the most conservative assessment about annual radiation exposure was the post-drilling scenario. In this scenario, human intrusion occurs, followed by drilling and residence on the site after the institutional management period. We assumed that some of the vegetables and fruits grown in the area may originate from contaminated regions. Importantly, we confirmed that radiation doses resulting from post-institutional management period human intrusion scenarios remain below 0.1 mSv/y, thus complying with the annual dose limits for the public. This research underscores the importance of effectively managing and securing radioactive waste, with a specific focus on the safety of beta radionuclide-removed waste during long-term disposal, even in the face of potential human intrusion scenarios beyond the institutional management period.

The safe disposal of high-level radioactive waste has become a prominent global concern, necessitating rigorous safety assessments for deep geological disposal facilities. In Korea, crystalline rock with low-permeability is considered as the host rock for radioactive waste disposal, and fluid flow and solute transport in a low-permeability rock formation predominantly occur through interconnected fracture network. To analyze and predict fluid flow and solute transport behavior within the fractures, a comprehensive understanding of solute mixing at fracture intersections is crucial. However, difficulty in direct observation of the mixing processes occurring within microscale fracture intersections has led only to analytical and numerical studies, which requires thorough experimental study based on direct observations and measurements for a fundamental understanding of the mixing processes in fracture intersections. In this study, elaborate experiments are being prepared and conducted to measure the complex flow velocity/structure and solute concentration at rough-walled fracture intersections, using a microscale visualization technique of micro Particle Image Velocimetry (micro-PIV) system. Most analytical and numerical studies have shown that at high Peclet number (Pe) > 1,000, streamlinerouting model plays a major role in redistributing solutes at the fracture intersection, at which the mixing ratio converges to zero. As opposed to the conventional mixing model, our experiments found the rebounding of the mixing ratio in the inertial flow regime, indicating an enhanced solute mixing at the intersection. Flow visualization has demonstrated that the inertial flow features, such as the development of large-scale eddies and the straightening of main streamlines, enhance the physical mixing of solutes at rough-walled fracture intersections. The findings provide insights into the influence of fracture geometry on flow dynamics and its significant impact on solute mixing at fracture intersections.

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.

As drones expand beyond military purposes to the private sector, the level of use of drones in various fields is increasing. However, the world was shocked by the attempt to attack with a drone equipped with a C4 bomb in the US and the attempt to assassinate a head of state using a drone in Venezuela. Drone threats to domestic nuclear power plants are also increasing due to the expansion of drone use, terrorist threats, and North Korea’s invasion of drones. Overseas, various drone threats to nuclear power plants have occurred. In October 2014, French electricity company Electricite de France confirmed that it had observed unauthorized drones over seven nuclear power plants across France. A drone threat occurred at the Savannah River Site (SRS), a U.S. Department of Energy facility that processes and stores nuclear materials. In 2016, eight drones were observed by security personnel. In 2016, a drone flew over the cooling tower of the Liebstadt nuclear power plant in Switzerland, and publicly shared the filmed video on YouTube. In July 2018, Greenpeace activists intentionally crashed a drone into the outer wall of the spent fuel building in Boughey, France. In January 2019, they used drones to drop smoke bombs and release videos at Orangeo’s nuclear facility containing irradiated fuel. In January 22, Sweden saw drones flying over three nuclear power plants. Drone was also seen at the Forsmark nuclear power plant on Friday and at two other Swedish nuclear power plants in Oskarshamn and Ringhals on Monday. Anti-drone technology to counter the threat of drone terrorism is also developing. Anti-drone technology detects, tracks, and identifies illegal drones to neutralize them. Various technologies such as radar, EO/IR cameras, Lidar, sensor, and RF scanners are being developed for drone detection. Depending on the detection technology, it has advantages such as detection distance and remote control drone detection. However, there are also disadvantages, such as obstacles, weather condition, and the inability to detect drones that do not transmit signals. Methods such as jammer, capture, and destruction have been developed for incapacitation technology. While it has advantages such as stability and portability, it has disadvantages such as limited use and damage to the surroundings. Accordingly, it is necessary to draw realistic measures to defend against the threat of nuclear power plants by paying constant attention to the various detection, identification, and neutralization anti-drone systems that continue to evolve.

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

The Agency needs to maintain a solid and reliable foundation for recruited inspectors by providing practical training at commercial nuclear power plants. The Comprehensive Inspection Exercise (CIE) is a basic training which consists of a simulation of a Design Information Verification (DIV) Visit, a Physical Inventory Verification (PIV) at a nuclear power plant, including Complementary Access. The basic curriculum includes a pre-course session, auditing exercises, fresh fuel (bundles and assemblies) measurements, spent fuel (bundles and assemblies) measurements, verification of design features, as well as nuclear material flow. ROK has been holding the lightwater reactor (LWR) / heavy-water reactor (CANDU) training course (CIE) from 2010 every year with about 2 weeks curriculum through MSSP (Member State Support Program). LWR and CANDU are operated by KHNP. To efficiently carry out the safeguards, IAEA receives the contribution through the ROK support program and implement R&D for the nuclear material inspection. ROK has been supporting and contributing total 22 tasks to IAEA in-cash and in-kind. Among them, this training provides for a course on safeguards verification activities at CANDU and LWR facilities. This course offers inspectors a unique opportunity to understand diversion scenarios and to familiarize themselves with instruments specifically used at CANDU and LWR facilities (OFPS and DCVD), as well as spent fuel dry storage transfer verification activities and dry storage dual sealing arrangements. KINAC performs PoC (Point of Contact) on behalf of NSSC and coordinates work between IAEA and KHNP. Additionally, KINAC first discusses with KHNP that can host light-water reactors and heavy-water reactors with KHNP at the beginning of each year. In order to hold a successful training, ROK plans and carries out a lot of process including agenda, accommodation, equipment movement, logistics and so on in consultation with the IAEA and facilities.

이 연구는 임도 개설 전·후 년차별로 식물상과 식생의 변화를 분석하고 관리 방안을 제공하기 위하여 전북 무주군 설천면 미천리에 소재한 민주지산 임도를 대상으로 임도 개설 전년도인 2012년부터 임도 개설 후 2022년까지 7차례에 걸쳐 수행되었 다. 임도 개설 조사구간 내의 식물군락은 북서사면에서 신갈나무군락, 남서사면에서 굴참나무군락과 일본잎갈나무군락으로 구분되어 남서사면과 북서사면에서 군락의 차이를 보였다. 임도 개설 전·후 년차별로 식물상의 변화는 임도 개설 전인 2012년 도 총 66분류군(44과 59속 51종 13변종 2품종)에서 2015년도에는 207분류군(71과 153속 176종 27변종 4품종)으로 141분 류군이 증가하였고, 2022년도에는 278분류군(78과 172속 242종 1아종, 31변종 4품종)으로 212분류군이 증가하였다. 특히 임도절토사면과 임도연접사면부의 조사구에서는 년차적으로 높은 식피율과 새로운 분류군의 증가를 보였는데, 이는 임도 개설에 따른 광량의 급격한 증가와 귀화식물 및 1년생 초본류의 유입으로 인해 일어난 현상으로 사료된다. 임도 개설 10년후 연차적으로 조사된 식생 조사 결과를 보면, 임도 개설 초년도에는 식피율과 종수가 빠른 속도로 증가하다가 일정 기간이 경과 하면 식피율과 출현 종수는 줄어들고 안정된 숲이 형성되어 우점종의 비율이 증가하였다. 특히 임도연접사면에서 관목층 과 초본층을 살펴보면, 임도 개설 직후 몇 년간은 초본층의 식피율이 현저히 증가하다가 시간이 경과 할수록 초본층의 피도는 감소하고, 관목층의 피도가 현저히 증가하였다. 그리고 임도산지사면에서는 초본층과 관목층의 피도는 현저히 감소하고, 아교목층과 교목층의 피도가 증가하였다.

이 연구는 오늘날 해외 한국학이 비약적으로 발전할 수 있었던 요인 중 하나로 한국의 경제성장을 주목하며, 미국 주요 대학의 한국 경제 관련 강좌의 특징을 분석하였다. 그 결과, 첫째 ‘한국 경제’에만 초점을 둔 강좌는 찾기 어려웠으나, 한국의 역사, 문화, 사회를 이해하기 위한 한국학 강좌에서 한국의 경제는 한국을 읽어내는 주요 배경 또는 한국 사회에 영향을 미친 핵심적인 요인으로 나타났다. 둘째, 한국 경제 관 련 강좌는 ‘한국 경제’라는 특정 주제에 주목하기보다, 아시아 국가 간 관계, 그리고 아시아 지역 국가들의 경제, 산업, 금융, 무역이 어떻게 연결되며 그 특징이 무엇인지 집중하고 있으며, 경제‧경영 이론을 설명 할 때 하나의 사례로 제시되는 특징이 있다.

PURPOSES : In this study, the initial behaviors of shoulder concrete slabs and tiebars at the longitudinal construction joints between the shoulder JCP and mainline CRCP are investigated. METHODS : The strains of concrete and tiebars were measured at the longitudinal construction joint between the CRCP and JCP. Measurements were performed using data accumulated over a month after concrete placement. The contact conditions were investigated by comparing the strains at each location. RESULTS : The longitudinal construction joints between the shoulder JCP and mainline CRCP exhibited the composite behavior of bonding and friction, and a virtual neutral axis was formed inside the JCP. At the connection of the shoulder concrete, the strain and temperature of the concrete were inversely proportional. The tiebars connecting the CRCP and JCP exhibited different behaviors depending on the bonding conditions around the tiebars of the construction joints. In the presumed state in which the bonding condition was maintained, the concrete temperature and tiebar strain were directly proportional; however, the presumed state of the separation condition exhibited an inversely proportional relationship. In the 24-h behaviors of the tiebars, the effects of the horizontal and curling movements overlapped, and the strains of the measured tiebars increased at the minimum and maximum temperatures of the shoulder JCP. CONCLUSIONS : The strains in the tiebars and concrete slabs primarily depended on the boundary conditions (bonding and friction) of the longitudinal construction joint between the shoulder JCP and mainline CRCP.

새만금 호의 수질 개선을 위하여 국가에서 해수 유통을 증가시킴에 따라 해수 유통 빈도 증가로 인한 새만금 호 내 염분과 저 층수 교환 변화를 알아보기 위하여, EFDC(Environmental Fluid Dynamics Code) 모델을 이용하였다. 갑문 개폐 횟수를 하루 1회에서 2회로 증 가했을 때, 새만금 호 내부 수위는 최대 약 0.7 m 상승하였다. 염분은 서측 방조제 근방에서 2.12 psu 증가하였으며, 담수 유입 부근에서는 1.18 psu 감소하였다. 입자추적을 이용하여 저층수 교환 정도 분석한 결과, 수심 5m 이하 입자 잔류율은 Case 2(1일 2회 개방)에서 Case 1(1 일 1회 개방)에 비해 2.52% 감소한 것으로 나타났다. 이는 수문 개폐 횟수를 증가시켰을 때, 저층수 교환이 더 활발해 질 수 있다는 것을 알 수 있다. 따라서 해수 유통 증가에 따른 염분 및 저층수 교환 증가로 새만금 호의 수질 개선이 될 수 있다고 판단된다.

Ricania sublimata are insects invaded in South Korea from China 2011. It has been happening continuously since invaded and It is established and continues to increase and occur in various crops such as persimmons, peaches, and apples. The nymphs and adults of R. sublimata causes damage by sucking the stems and leaves of trees. Yellow, blue, and white sticky traps (25x15cm) were installed in the 1000m2 Omija(Schizandra Chinesis Baillon) orchard september 2020 and the trap captures by color was investigated. In addition, yellow sticky traps were installed at heights of 1m, 1.7m, and 2m, and the trap captures according to the height was investigated. As a result of attraction according to the color of the sticky trap, yellow trap was the most attractive, blue and white traps had little attraction. And result of capture according to the yellow sticky trap height the most were caught at 1.7m height, followed by 1m and 2m in that order. Therefore, it is considered reasonable to investigate the density and monitoring of R. sublimata using yellow sticky trap.

열대거세미나방이 2019년 국내에 첫 비래한 이후 매년 비래하고 있으며 옥수수 등에서 피해를 주고 있음에 따라 전북지역 주요 옥수수 재배지역에서의 열대거세미나방 발생양상과 약제방제 효과를 조사하였다. 2022년 도에 성페로몬트랩을 이용하여 성충유인량을 조사한 결과 7월 1일 첫 채집되었으며 8월 중순이후 채집량이 증가 하여 9월 중순과 10월 중순에 발생최성기를 보였으며 11월 상순까지 유인되었다. 2022년과 2023년에 식용 옥수 수 재배지역에서 열대거세미나방 유충 피해 조사 결과 6월 수확하는 옥수수에서는 열매피해가 없었으나 9월에 수확하는 옥수수에서는 피해열매율이 30% 이상인 포장들이 관찰되어 재배시기에 따라 피해 정도 차이가 매우 큰 경향이었다. 옥수수 포장에서 열대거세미나방 유충 방제를 위해 2~3령기에 인독사카브 액상수화제를 7일 간격으로 2회 살포한 결과 처리 7일 후 방제효과는 91.7%로 높았다.

우리나라에 서식하는 주요 말벌류는 벌목(Hymenoptera)의 말벌아과(Vespinae)에 속하는 종들로 10종의 말벌속 (Vespa) 중 8종[장수말벌(V. mandarinia), 꼬마장수말벌(V. ducalis), 등검은말벌(V. velutina nigrithorax), 좀말 벌(V. analis), 말벌(V. crabro flavofasciata), 검정말벌(V. dybowskii), 털보말벌(V. simillima simillima), 황말벌 (V. simillima xanthoptera)]이 주를 이루고 있다. 특히 2003년 부산에서 처음 발견되었던 등검은말벌이 급속도로 확산되어 우리나라 양봉산업에 치명적인 피해를 주고 있는 현실이다. 이에 본 연구는 충남 주요 양봉지역인 공주, 청양, 논산에서 말벌 유인액을 주입한 포획기를 이용하여 4월부터 6월까지 봄철 출현하는 여왕말벌의 포획된 말벌 류 개체들을 조사하여 분포도와 특성을 알아보았다. 말벌 포획 개체수 조사결과, 등검은말벌의 분포율이 공주 76.3%, 청양 74.1%, 논산 58.0%로 가장 큰 비율을 보였으며, 꼬마장수말벌이 다음으로 공주와 청양지역은 밤나무 숲으로 12.4~16.0%를 보였던 반면, 소나무 숲을 이룬 논산에서는 31.8%로 최대 2.5배 정도 높은 분포 비율을 나타냈 다. 그리고 장수말벌은 5.2~8.6%의 분포율을 보였으며, 다른 지역보다 해발이 높았던 청양지역에서 장수말벌이 많게 조사되었다. 봄철 3개 지역에서 포획된 여왕말벌류의 총개체수(266마리)에 대한 평균 분포 비율은 등검은말 벌 69.5%, 꼬마장수말벌 19.9%, 장수말벌 6.8%, 말벌 2.6%, 그리고 좀말벌 1.1% 순으로 조사되었다.