With changing dietary trends, active research is underway to substitute rice flour for wheat flour, commonly added to various processed foods. This study aimed to explore whether Baromi2, a floury rice incorporated in the production of Sujebi, can effectively replace wheat flour at appropriate levels based on its physicochemical and cooking characteristics. Baromi2 was categorized based on particle size (100, 140, and 200 mesh) and added in proportions of 10% and 20% relative to the weight of wheat flour. As the amount of Baromi2 increased, the protein and lipid content of the mixed flour also increased. Simultaneously, the dough strength decreased as the noodles became thinner, reducing hardness, gumminess, and chewiness. Additionally, a decrease in particle size increased peak viscosity and breakdown viscosity, whereas setback viscosity decreased. When Baromi2 was added at a 10% ratio, it displayed a low cooking loss, demonstrating desirable characteristics for Sujebi and was considered the most suitable proportion for production. These results provide foundational data for developing various rice-processed products using Baromi2, contributing to expanding consumption and enhancing utility.

이 연구는 해양경찰공무원의 환경 적합성이 조직 및 직무 애착에 미치는 영향을 검증하기 위해 해양경찰공무원 150명을 대상 으로 연구를 진행하였다. 이 연구의 독립변수인 환경 적합성의 하위변인은 조직 적합성, 직무 적합성, 상사 적합성으로 분류하였다. 연구 결과 조직 애착에 영향을 미치는 독립변인은 조직 적합성만이 유일하였고, 직무 애착의 경우 조직 적합성, 상사 적합성, 직무 적합성 모두 영향을 미치는 것으로 나타났다. 이러한 결과를 통해 해양 경찰 조직의 발전을 위한 제언 및 향 후 개인적 특성에 따른 후속 연구를 제안 하였다.

본 연구는 국립공원 재계획중 타당성조사 기준과 방법의 적절성 분석을 목적으로 하였다. 가야산국립공원, 설악산과 주왕산국립공원은 절대평가(제2차) 방법이 상대평가(제3차) 보다 ‘해제 대상’이 낮은 비율로 도출되었다. 제3차 평가방 법이 해제가능지역 10%라는 비율을 정해놓고 해제보다는 존치를 통한 공원면적 유지를 지향한 방법임에도 절대평가 방법이 결코 해제가능 지역을 더 많이 추출하지는 않았다. 연구대상지에 제2차와 제3차 생태기반평가를 적용했을 때 2011년 실제 해제지역이 나타나는지를 분석한 결과 제2차, 제3차 생태기반평가 모두 해제지역을 반영하지 못했다. 생태기반평가는 해제지역을 결정하는 중요한 의사결정 수단이 아닌 보조수단일 뿐이었다. 공원계획 타당성조사의 구역조정 중 해제는 외적 요소인 상호교환, 해제기준의 우선적용 등이 더욱 중요하게 작용함을 알 수 있었다.

PURPOSES : The wedge-type anchorage system requires a complex analysis of not only the tensile stress of the CFRP plate, but also the compressive stress and shear stress generated by the wedge action. The purpose of this study is to find a composite material failure theory that is suitable for analyzing the behavior of wedge-type anchorage system among various failure theories. METHODS : In this study, numerical analysis of various composite material failure theories was performed to analyze the anchorage strength and failure mode of the wedge-type anchorage system according to each failure theory, and compared with actual test results to determine the composite material failure theory most suitable for analyzing the behavior of a wedge-type anchorage system. RESULTS : Since the Maximum Stress failure theory shows similar results to the actual test in terms of failure mode and anchorage strength, there is no significant problem in applying it to the wedge-type anchorage system. However, it is judged to be difficult to apply under property conditions where interactions between stresses are highlighted. The Tsai-Hill and Tsai-Wu failure theories are considered unsuitable for application to wedge-type anchorage systems because the wedge angle conditions at which the most advantageous anchorage strength occurs are significantly different from other theories and the fracture type cannot be predicted. The Hashin-Rotem failure theory is considered to be the most appropriate to apply as a failure theory for the wedge-shaped anchorage system because the anchorage strength was slightly lower than the actual test results, but there was no significant difference, and the failure mode was consistent with the test results. The Hashin failure theory is judged to be unsuitable for application as a failure theory for the wedge-type anchorage system because the anchorage strength and failure mode were interpreted differently from the actual test results. CONCLUSIONS : The Hashin-Rotem failure theory was presented as the composite material failure theory most suitable for analyzing the behavior of wedge-type anchorage system.

Radioactive waste (hereinafter referred to as mixed waste) containing hazardous substances (heavy metals, organic and inorganic waste liquids, asbestos, etc.) has been continuously generated from domestic nuclear power plants, nuclear facilities, and other industrial facilities, and heavy metals were released during the dismantlement of Kori Unit 1 and Wolseong Unit 1. Lead, cadmium, mercury, arsenic), asbestos, decontamination waste liquid (organic/inorganic waste liquid), etc. may be generated. Although hazardous waste related to the nuclear industry continues to be generated, only the regulation direction for hazardous substances is presented in the provisions related to hazardous substances in the delivery regulations for low and intermediate-level radioactive waste and the acceptance criteria for low and intermediate-level radioactive waste disposal facilities. In particular, because there is no clear definition of “hazardousness” and specific standards such as concentration and characteristics for classification of hazardous substances, as well as hazard removal procedures when the hazardousness of radioactive waste is confirmed, no hazardous substances have been delivered in Korea to date and many mixed wastes are stored at each generation facility or at the NPP. As a plan to improve delivery standards related to mixed waste is being prepared recently, it is believed that if the acceptance standards are revised accordingly, it will be possible to confirm the suitability for disposal of drums produced after the establishment of the acceptance standards in 2015. However, it is believed that securing disposal suitability for waste that was packed in 200L drums and compressed under super high pressure in the absence of specific technical standards and regulatory guidelines for the disposal of radioactive waste containing hazardous substances would still remain a difficult problem. In this report overseas acceptance standards related to hazardous waste were reviewed and a plan to secure the disposal suitability of 200 L drums compressed with of super high pressure was proposed.

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.

최근 국내에서 외래 곤충인 (가칭)마른나무흰개미(Cryptotermes domesticus)가 서울에 위치한 주택에서 발견되었다. 이 종은 국내에 정착할 경우 잠재적으로 목재나 목조건물에 피해를 줄 수 있어 시급한 국내 발생 조사가 필요하다. 본 연구에서는 종 분포 모델 기법을 활용하여 마른나 무흰개미의 정착 가능성과 관련된 기후적합성을 추정하는 것을 목표로 하였다. 문헌 자료를 바탕으로 전세계 분포 정보를 수집하고, 생물기후변 수를 활용하여 4개의 모델링 알고리즘으로 기후적합성 예측 모델을 구동하였다. 개발한 모델들의 결과를 종합하여 최종적으로 마른나무흰개미 의 평균 발생 확률로 표현되는 앙상블 모델을 개발하였다. 그 결과 마른나무흰개미는 열대 지방에서에서 해양성 기후를 보이는 연안이나 도서지 역에서 기후적합성이 높을 것으로 예상되었다. 국내에서는 기후적합성이 전반적으로 낮을 것으로 추정되었다. 하지만, 마른나무흰개미의 정착 및 확산 가능성을 염두해두고, 최근 발생이 보고된 지점을 중심으로 정밀 역학 조사가 필요할 것으로 보인다.

굴은 패류 양식생산량 중 가장 큰 비율(평균 76%)을 차지하는 중요한 양식생물이다. 본 연구에서는 자란만의 굴 양식장에 대 해, 수온, 염분, 해수 유동, DO, SS, Chl.a를 어장적지평가 인자로 활용한 서식지 적합 지수(Habitat Suitability Index, HSI)를 산정하여 최적 서 식지를 탐색하였다. 조사결과 만 입구가 넓고 해수 유속이 빠르게 나타난 대상해역 남동쪽에서 만 내측으로 갈수록 적합한 서식지로 나 타났고, 굴의 생산량과 본 연구의 HSI는 0.710(p<0.05)의 유의한 상관성을 보였다. 만 내의 원활한 해수 교환으로 먹이공급 등 양식생물 성 장에 도움을 주는 해수 유동은 굴 생산량과 높은 상관성(0.709, p<0.05)을 보여 Chl.a보다 서식 적합도에 더 큰 영향을 미치는 것으로 나타 났다. 본 연구 결과는 양식장 재배치 등 효율적인 연안어장 보전, 이용과 관리에 도움이 될 수 있을 것으로 판단된다.

수달(Eurasian otter, Lutra lutra)은 식육목 족제비과에 속하는 동물이다. 수달은 수계환경 먹이그물의 최상위에 존재하는 포식자로 핵심종(keystone species)이자 건강한 수계환경을 대변하는 지표종(Indicator species)이다. 현대에 이르면서 남획과 서식지 파괴, 환경 오염 등에 의하여 한강 도심 수계에서 사라졌지만, 2016년 다시 발견된 이후 2021년 1월에도 한강의 지류인 청계천, 중랑천과 성내천에서 서식함을 확인하였다. 수달의 서식지 보호와 관리 방안 수립을 위하여 잠재 서식지 평가가 시급하나, 기존의 수달 서식지 관련 연구는 자연형 하천과 저수지 위주로 이루어져 한강 도심 지류와 같이 좁은 공간에 인위적으로 한정된 서식지에 적용하기에는 한계가 있다. 본 연구에서는 인공하천인 청계천이 수달의 잠재 서식지로 적합한지를 서식지 적합성 지수(Habitat Suitability Index, HSI)를 활용하여 평가하였다. 서식지 적합성 지수는 수달의 서식 환경을 나타내는 지표, 먹이자원, 위협 요소 환경 특성을 종합하여 추정하였다. 그 결과 성북천과 청계천의 합류 지점과 청계천과 중랑천의 합류 지점이 적합한 서식지로 나타났다. 본 연구에서 추정한 HSI는 도심 하천의 수달 서식지 평가가 가능하였으며, 따라서 청계천을 포함한 한강 도심 지류에서의 효과적인 수달 모니터링과 수달 인공 서식지 장소 선정을 위한 기반 자료가 될 수 있을 것으로 판단된다.

Background: After the coronavirus disease 2019 (COVID-19) pandemic, many changes in education were observed, particularly non-face-to-face classes. Many studies have focused on the suitability of non-face-to-face classes and the satisfaction of both students and teachers with this teaching method. However, no study on the suitability of numerous teaching methods in teaching physical therapy subjects has been conducted. Objectives: To investigated the suitability of three teaching methods, namely, face-to-face, non-face-to-face, and mixed classes, in teaching physical therapy subjects. Design: Survey research. Methods: 336 students studying physical therapy participated. A survey was conducted on the suitability of face-to-face, non-face-to-face, and mixed classes for 16 subjects. The survey was conducted using a Google questionnaire. Results: Face-to-face classes were found to be suitable for teaching the basic fields of physical therapy, and face-to-face and mixed classes were suitable for teaching the principle of diagnostic evaluation. Furthermore, faceto- face classes were found to be suitable for teaching physical therapy interventions. In other subjects, face-to-face classes were suitable for teaching rehabilitation medicine, non-face-to-face classes were suitable for teaching medical terms, and mixed classes were suitable for teaching daily life activities. Conclusion: The results of this study can be used as a basis for choosing the appropriate methods for learning and teaching physical therapy subjects.

Various social and environmental problems have recently emerged due to global climate change. In South Korea, coniferous forests in the highlands are decreasing due to climate change whereas the distribution of subtropical species is gradually increasing. This study aims to respond to changes in the distribution of forest species in South Korea due to climate change. This study predicts changes in future suitable areas for Pinus koraiensis, Cryptomeria japonica, and Chamaecyparis obtusa cultivated as timber species based on climate, topography, and environment. Appearance coordinates were collected only for natural forests in consideration of climate suitability in the National Forest Inventory. Future climate data used the SSP scenario by KMA. Species distribution models were ensembled to predict future suitable habitat areas for the base year (2000-2019), near future (2041-2060), and distant future (2081-2100). In the baseline period, the highly suitable habitat for Pinus koraiensis accounted for approximately 13.87% of the country. However, in the distant future (2081- 2100), it decreased to approximately 0.11% under SSP5-8.5. For Cryptomeria japonica, the habitat for the base year was approximately 7.08%. It increased to approximately 18.21% under SSP5-8.5 in the distant future. In the case of Chamaecyparis obtusa, the habitat for the base year was approximately 19.32%. It increased to approximately 90.93% under SSP5-8.5 in the distant future. Pinus koraiensis, which had been planted nationwide, gradually moved north due to climate change with suitable habitats in South Korea decreased significantly. After the near future, Pinus koraiensis was not suitable for the afforestation as timber species in South Korea. Chamaecyparis obtusa can be replaced in most areas. In the case of Cryptomeria japonica, it was assessed that it could replace part of the south and central region.

In operating or permanently shut down nuclear power plants which were built between 1970s and 1990s, asbestos was widely used for ceiling materials, wall materials, and gaskets. Furthermore, it was mainly treated as a heat-resistant material like insulation. In Kori Unit 1, radioactive asbestos was replaced or removed through maintenance and repair in the containment building during the operation period of about 40 years, but radioactive asbestos still remains that need to be partially dismantled. Generally, it is more difficult to handle because it belongs to two different waste categories, radioactive waste and hazardous waste. In addition, the risk increases further due to radioactivity with the asbestos hazards itself. Therefore, it is very important to accurately determine the amount of radioactive asbestos waste and to evaluate the treatment method and disposal reduction rate before the decommissioning is started. According to the Korean Waste Management Act, three methods are recommended for the asbestos (hazardous waste) treatment: landfill, solidification, and high-temperature melting. Landfill is commonly used in Korea and the United States while high-temperature melting and solidification are additionally recommended only in Korea. Considering the situation in Korea, landfill is not appropriate due to the limitations of landfill capacity and potential risks (hazards still remain). Therefore, the other two methods can be considered sufficiently in terms of safety, detoxification, and reduction rate. This paper evaluates the amount of radioactive asbestos waste at Kori Unit 1 based on the actual asbestos building material data (as of February 2022) of the Asbestos Management Comprehensive Information Network. Vitrification is considered as a sufficient alternative for treating radioactive asbestos waste. And, it is checked whether the vitrified waste through the high-temperature melting method, plasma torch, meets the requirements such as detoxification, compressive strength and leachability for storage and disposal stability. It is expected to be useful to prepare a radioactive mixed waste management standard and to reduce the disposal cost through the reduction of final waste.

Currently, Hanul NPP packages glass fiber classified as particulate waste in plastic packaging bags and stores them in 200 L drums. KORAD’s Waste Acceptance Criteria (WAC) presents that very low-level soil can be immobilized by loading it in a soft bag and then packaging it in a 200 L or 320 L steel drum. As currently accepted method of packaging with soft bag applies to only very low-level soils among the wastes with a risk of dispersion, it is necessary to develop a non-dispersible treatment suitable for the characteristics of other particulate waste in the future. Therefore, in order for Hanul packaging pack to be approved as an alternative method for immobilization of dispersible substances, it is necessary to verify the suitability of the packaging bag. In this paper, whether the glass fiber packaging bag used in Hanul NPP satisfies the characteristic of the soft bag presented in the WAC and the possibility of being considered as a non-dispersible measure for particulate are examined. The soft bag must meet the following requirements: material and structure, shape, drop test, and immersion test. The results of the review are as follows. First, since the glass fiber is already packaged in the drum, only the role of the inner layer, made of polyethylene, having a watertight function may be required. Second, when packaging a drum, the packaging bag is compressed into a shaped frame having an inner size of a 200 L drum, so it is packaged with little empty space in the drum. Third, as a result of a drop test of a packaging pack containing 20 kg of contents from a height of 1.2 m, it was confirmed that there was no leakage of contents. Fourth, the packaging bag was immersed in a 1-m depth water tank for 30-minutes, and the performance corresponding to the IPX7 was satisfied. As a result of reviewing the soft bag characteristic of Hanul glass fiber packaging bag, it is considered that the bag can be used as one of the non-dispersible measures because it meets almost the characteristics required by the WAC. In addition, the acceptance criteria of overseas disposal sites present various secure packaging methods in place of immobilization as a non-dispersible measure for waste containing particulate matter. It is necessary to reflect these overseas cases in the establishment of non-dispersible measures for domestic waste acceptance in the future.

As the decommissioning of Kori Unit 1 progresses, securing technology for treatment and disposal of radioactive wastes that have not been disposed of so far, such as spent filters, is recognized as an urgent task. In this study, a method of confirming the disposal suitability of spent filters was presented by reviewing the waste characteristics as presented in the waste acceptance criteria (WAC). The waste characteristics to be satisfied to ensure disposal suitability of waste are largely classified into general requirements, solidification and immobilization requirements, radiological requirements, physical requirements, chemical requirements, and biological requirements. First, the general requirement is to prove that the prohibited waste form has not been introduced into items related to waste form and packaging, and to confirm the suitability of disposal through step-by-step packaging photos, generation information, X-ray inspection, and visual inspection. Second, in the solidification and immobilization requirements, spent filters are non-homogeneous waste, and if the total radioactivity concentration of nuclides with a half-life of more than 20 years is 74,000 Bq·g−1 or more, they must be immobilized. Third, in order to meet the characteristic criteria for nuclides and radioactivity concentration, sampling and scaling factors development are required and based on this, nuclides must be identified and demonstrated to be below the disposal concentration limits. Surface dose rate and surface contamination should be measured in accordance with standardized procedures and disposal suitability should be confirmed through document tests recording the measured values. Fourth, in order to satisfy the physical requirements of the particulate matter and filling rate characteristics, the spent filter must be immobilized, if necessary, thereby ensuring disposal suitability. Meanwhile, free water in the spent filter should be removed through pre-drying and dehydration, and the disposal suitability should be confirmed by applying a test. Fifth, the criteria for chelating agents should be checked for disposal suitability through operation records and component analysis of spent filters, and documents, that can prove harmful substances are removed in advance and no harmful substances are included in the package, should be provided. Lastly, in biological requirements, if the spent filters contain corrosive or infectious substances, they should be removed in advance and disposal suitability should be confirmed by providing documents that can prove that such substances are not included in the package.

This study established a process to ensure the disposal suitability of spent filters stored in the untreated state in Kori unit 1 and presented the following procedures and requirements for confirming the disposal suitability for each process. The process for securing spent filter disposal suitability consists of collecting spent filters, compression, immobilization, analysis and packaging, and storage stages. The requirements for confirming the acceptance criteria for each process are as follows. (1) Collecting: Since the high radioactivity spent filters are being stored in the filter room of Kori unit 1, those are collected by a remote system to minimize the exposure dose of workers due to spent filter handling. In order to satisfy the surface dose rate requirements, spent filters with a surface dose rate of 10 mSv·hr−1 or more are classified and collected, and stored temporary storage place until a separate treatment plan is determined. The checkpoints in this process are the surface dose rate, etc. (2) Compression: The collected spent filters are analyzed gamma nuclides such as Co-60 and Cs-137, using a field-applicable nuclide analyzer, and then applying the scaling factors to determine whether it is disposable. Spent filters whose radioactivity concentration is confirmed to be less than the disposal concentration limit is compressed into compression ratios determined by surface dose rate. The checkpoints in this process are nuclide information, surface dose rate, compression ratio, spent filter loading quantity, etc. (3) Immobilization: A spent filter is a non-homogeneous waste that is immobilized with a proven safety material such as cement if the total radioactivity concentration of nuclides with a half-life of more than 20 years is 74,000 Bq·g−1. Meanwhile, immobilization of inhomogeneous waste can be considered to satisfy disposal criteria such as particulate matter and filling rate. The checkpoints in this process are the immobilizing material, filling rate, etc. (4) Analysis and Packaging: Immobilized drums shall be determined to be 95% or more of the total radioactivity of waste packages by measuring the radioactivity concentration of nuclides using a nuclide analysis device. Finally, measure the surface dose rate and surface contamination of the package, and attach the package label recording the identification number, date, total radioactivity, surface dose rate, and surface contamination information to the packaging container. (5) Storage: Packaging containers are moved to and stored in a temporary waste storage or storage area before disposal.