The two most well-known Chinese characters dictionaries are Songben Yupian from China and Quanyun Yupian from Korea. These dictionaries contain a wealth of information on Chinese characters at the diachronic and synchronic level, while also retaining much information on Chinese characters during the period of its movement overseas. This paper is a corpus-based study which analyzes the differences in the style of arrangement, phonetic notation mode, interpretation, form interpretation, and other aspects of the two dictionaries, and further summarizes the laws of the development of Chinese characters in overseas dissemination. The result of this study indicates that the function of the two dictionaries is different, that the Chinese characters remained stable during their transmission to other countries, and that the overall trend in the evolution of the characters is toward simplification, and that the main way that Chinese characters morph extraterritorially is via phonetic and semantic replacement.

In this study, we explore and catalog Korean astronomical heritages that are known to be preserved in foreign countries. We exclude old astronomical books from the catalog because they have been well studied and exist in numbers far too large for the scope of this study. From various documents and online collections, we find a total of 38 Korean astronomical heritages in six countries: 10, 11, and 14 items from the UK, France, and Japan, respectively, and 1 item from Germany, the US, and China each. These include items that are suspected to be of Chinese heritage and items of unconfirmed possession status. We divide the astronomical heritages primarily into two groups: time-keeping instruments (18 items) and astronomical charts (20 items). In this paper, we briefly review them according to country. We believe that this study provides a foundation for further detailed studies on each item, such as the Gujang-Cheonsang-Yeolcha-Bunya-Jido (舊藏天象列次分野之圖) preserved in the Library of Congress, United States.

The demand for transportation is increasing due to the continuous generation of radioactive wastes. Especially, considering the geographical characteristics of Korea and the location characteristics of nuclear facilities, the demand for maritime transportation is expected to increase. If a sinking accident happens during maritime transportation, radioactive materials can be released into the ocean from radioactive waste transportation containers. Radioactive materials can spread through the ocean currents and have radiological effects on humans. The effect on humans is proportional to the concentration of radioactive materials in the ocean compartment. In order to calculate the concentration of radioactive materials that constantly flow along the ocean current, it is necessary to divide the wide ocean into appropriate compartments and express the transfer processes of radioactive materials between the compartments. Accordingly, this study analyzed various ocean transfer evaluation methodologies of overseas maritime transportation risk codes. MARINRAD, POSEIDON, and LAMER codes were selected to analyze the maritime transfer evaluation methodology. MARINRAD divided the ocean into two types of compartments that water and sediment compartments. And it was assumed that radionuclides are transfered from water to water or from water to sediment. Advection, diffusion, and sedimentation were established as transfer process for radionuclides between compartments. MARINRAD use transfer parameters to evaluate transer processes by advection, diffusion, and sedimentation. Transfer parameters were affected by flow rate, sedimentation rate, sediment porosity, and etc. POSEIDON also divided the ocean into two types that water and sediment compartment, each compartments was detaily divided into three vertical sub-compartment. Advection, diffusion, resuspension, sedimentation, and bioturbation were established as transport processes for radionuclides between compartments. POSEIDON also used transfer parameters for evaluating advection, diffusion, resuspension, sedimentation, and bioturbation. Transfer parameters were affected by suspended sediment rates, sedimentation rates, vertical diffusion coefficients, bioturbation factors, porosity, and etc. LAMER only considered the water compartment. It divided the water compartment into vertical detailed compartments. Diffusion, advection and sedimentation were established as the nuclide transfer processes between the compartments. To evaluated the transfer processes of nuclides for diffusion and advection, LAMER calculated the probability with generating random position vectors for radionuclides’ locations rather than deterministic methods such as MARINRAD’s transfer parameters or POSEIDON’s transfer rates to evaluate transfer processes. The results of this study can be used as a basis for developing radioactive materials’ ocean transfer evaluation model.

A disposal of radioactive wastes is one of the urgent issues in worldwide. Considering upcoming plans for decommissioning of nuclear power plants, this problem is unavoidable and should be discussed very thoughtfully before long. There are variety of methods to deal with radioactive wastes, including Incineration process, conventional gasification process and plasma gasification process and so on. Among them, plasma gasification process is in the limelight due to its ecofriendly features and very large volume reduction effects. So, lots of countries like Japan, Taiwan, Russia, Bulgaria are already utilizing commercial plasma melting facilities and researching their own characteristics & disposal abilities and so on. Within the scope of this paper, I would like to introduce other countries current status of plasma melting facilities, and reach the conclusion on the directions to go for realistic radioactive wastes treatment.

In general, radioactive waste with high radioactivity is made into a solid form with performance such as leaching restriction, shape retention, and structural stability so that radioactive waste does not affect humans and the environment as much as possible. This should be applied equally to radioactive waste, whether homogeneous or heterogeneous. The requirements are stipulated in the “Low and Intermediate Level Radioactive Waste Delivery Regulations” notice of the Korea Nuclear Safety and Security Commission. On the other hand, the waste acceptance criteria for domestic disposal facilities require immobilization of heterogeneous waste when the activity concentration is above a certain level, but do not provide specific immobilization performance requirements. In this study, the immobilization requirements applied to heterogeneous radioactive waste in various overseas countries operating low and intermediate-level radioactive waste disposal facilities were studied. First, the IAEA’s safety standards for radioactive waste immobilization, domestic regulations, and disposal facility waste acceptance criteria were reviewed. Countries operating surface disposal facilities such as the United States, France, Spain, and Japan and countries operating underground disposal facilities such as Sweden and Finland were divided to review the current status of immobilization application to heterogeneous waste in overseas countries. When reviewing overseas cases, each country’s disposal methods, types of disposal waste, and waste treatment criteria were also reviewed. It was found that the immobilization requirements for heterogeneous radioactive waste vary depending on the disposal method and the type of barrier used to ensure disposal safety in each country. The common point is to surround heterogeneous radioactive waste within a concrete lining of a certain thickness, and to apply the thickness, compressive strength, and diffusion coefficient of the concrete lining as immobilization performance requirements. Through this study, the immobilization performance requirements for heterogeneous radioactive waste in various overseas countries that stably operate low- and intermediate-level radioactive waste were confirmed, which is expected to contribute to specifying the performance requirements for immobilization of heterogeneous radioactive waste in domestic disposal facilities.

A disposal system for spent nuclear fuel mainly divides into two parts; Engineered barriers include spent nuclear fuel, canister, buffer and backfill and natural barriers mean a host rock surrounding engineered barriers. If radionuclides released from a repository, they can migrate to the ecosystem. Sorption plays an important role in retarding the migration of released radionuclides. Hence, the safety assessment for the disposal of a spent nuclear fuel should consider the migration and retardation of radionuclides in geosphere. Distribution coefficient is one of input parameters for the safety assessment. In this work, distribution coefficients for crystalline rock as a natural barrier were collected and evaluated for the purpose of safety assessment for the deep geological disposal of a spent nuclear fuel. The radionuclides considered in this work are as follows; alkali and alkaline earth metals (Cs, Sr, Ba), lanthanides (Sm), actinides (Ac, Am, Cm, Np, Pa, Pu, Th U), transition elements (Nb, Ni, Pd, Tc, Zr), and others (C, Cl, I, Rn, Se, Sn). The sorption of radionuclides is influenced by various geochemical conditions such as pH/carbonates, redox potential, ionic strength, radionuclide concentration, kinds and amounts of minerals, and microbes. For the evaluation of distribution coefficients, the data from Sweden (SKB), Finland (Posiva), Switzerland (Nagra), and Japan (JAEA) were collected, analyzed, and the recommended distribution coefficients have been suggested.

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.

PURPOSES : This study proposes a framework for promoting future expressway remodeling projects by reviewing similar overseas cases and comparing them with current Korean expressway remodeling projects. METHODS : Based on a literature review, this study examines the major issues in expressway remodeling projects and proposes the development of a framework for establishing and promoting such projects. This framework provides detailed guidance by categorizing the project into legal system adjustments, traffic management plans, and social consensus. RESULTS : The diagnosis of issues in domestic expressway remodeling projects revealed significant problems in conceptual aspects, criteria for project evaluation, formulation of traffic diversion strategies, and deficiencies in related legal frameworks. To address these issues, a framework for advancing future remodeling projects was established based on the results of overseas case studies. CONCLUSIONS : As roads deteriorate, the demand for remodeling projects to restore them increases. However, the current implementation of remodeling projects lacks systematic procedures. This study serves as foundational research for establishing an environment conducive to the smooth progress of such projects. By initiating subsequent research, conditions for the smooth progress of remodeling projects are expected to be established.

우리나라 해양환경에 유출되는 위험·유해물질(Hazardous Noxious Substances, HNS)의 해양환경 및 사회환경 영향평가 결과 와 HNS 확산 영역, 해양환경 정보, HNS 실태조사 결과 등 관련 연구 결과 및 자료를 정책결정자와 연구자들에게 공유할 수 있는 HNS 국내 용 플랫폼을 구축하고자 한다. 국내의 HNS 관리 및 배출 체계 마련을 위한 의사결정 지원이 가능하고 국내 실정에 적합한 플랫폼의 설계 를 위하여 유해물질의 데이터 관리 및 유출 시 대응 도구, 기초적인 정보 등 플랫폼에 관련된 기술동향을 분석하는 등 국내·외의 플랫폼 개발 사례를 고찰하였다. 유속 벡터의 전처리 기능 개발, 전처리 결과에 따른 동적 시각화 구현, 해양산업시설 배출 HNS의 유출량과 유출 범위의 전처리 모듈, HNS 해양환경 영향평가 연산 모듈 프로토타입을 개발하였다. HNS 해양환경 영향평가를 위한 국내용 HNS 플랫폼은 초기 위해성을 평가하고 대응 및 관련 법제화 시 과학적인 기초 도구로써 활용될 수 있을 것으로 기대된다.

Under increased complexity and uncertainty of overseas construction projects, it is important for construction companies to improve their own project risk management capabilities instead of risk-taking strategies to secure competitiveness in the overseas construction market. Although most of the risks occur in project execution stage, many previous studies focused on planning stage including risk identification and analysis among PRM process. Therefore, this study aims to verify the effectiveness of whole PRM process during project execution stage through empirical study on participants of overseas construction projects. As the result it was found that first, the factor directly affects the project success is the execution process of PRM. It implies that appropriate actions such as appointing charged manager for risks, timely implementation of responding plan, continuous risk monitoring and updating established plan are the key for contribution to the project success. Second, the importance of communication in PRM is also found, which is not conducted at a specific but throughout the entire PRM process and need to be managed as essential factor for successful PRM..

본 연구의 목적은 미국, 영국, 독일, 일본의 학교안전 법제를 살펴봄으로 써, 국내 학교안전에 시사하는 바를 논하고 제시하는 데에 있다. 외국사례를 통해 우리나라 학교안전사고 예방 및 학교안전관리시스템이 보다 실효성 있 게 작동하도록 몇 가지 적용 및 시사점을 제시하였다. 첫째, 학교 안전관리 책임을 명확히 하고 학교안전교육을 지원하는 법제의 명문화와 「학교폭력예 방법」, 「학교안전법」, 「학교보건법」을 「학교안전보건법」으로 통합할 필요가 있다. 둘째, 국가 책임을 강화하는 차원에서 충분한 예산 지원과 인력 확보 및 교직원의 안전 전문성 향상을 위한 제도 마련, 그리고 일원화된 전문기관 등이 필요하다. 셋째, 「학교안전법」을 「산업안전보건법」 수준으로 업그레이 드할 필요가 있고, 독일의 사회보험 수준으로 학교안전공제회의 역량을 제고 할 필요가 있다. 넷째, 체계적인 시스템과 실효성 있는 매뉴얼에 의해 작동되 도록 학교안전망을 촘촘하게 구축할 필요가 있다. 다섯째, 예방활동과 안전 교육의 패러다임을 전환할 필요가 있다. 여섯째, 평소 지역 유관기관·단체 등 과 안전시스템을 긴밀하게 공유, 연계할 필요가 있다. 일곱째, 실효성 있는 학교안전 위험성 평가를 실시하여 사고 발생률을 낮출 필요가 있다. 여덟째, 학교 보안을 더욱 강화할 필요가 있다. 아홉째, 학생안전 법제에 학생의 권리 와 의무를 함께 명시할 필요가 있다. 열 번째, 우리나라도 ‘갭 이어(Gap Ye ar)’ 제도 도입을 검토할 필요가 있다. 이상의 논의와 제시를 통해, 국내 학 교안전 및 학교안전 법제의 긍정적 변화를 기대한다.

Background: The globalization of the healthcare industry and the increasing demand for skilled professionals in the global healthcare industry have opened up opportunities for specialized biotech healthcare professionals to seek overseas employment and career advancement. Objects: This study aimed to develop educational content essential for the overseas employment of digital bio-health professionals. Methods: A survey was conducted among 196 participants. Google Forms (Google) were utilized to create and administer the survey, employing purposive sampling, a non-probability sampling method. Data analysis was performed using IBM SPSS 25.0 (IBM Co.), including Cronbach’s α and independent sample t-tests to assess significant differences. Results: About half of college students are interested in overseas employment and international careers, while the other half had not. The most common reason for wanting to work or go overseas was “foreign experience will be useful for future activities in Korea.” Students who had experience taking courses from the Bio-health Convergence Open Sharing University preferred overseas programs more than those who did not have that experience. In terms of the degree of desire for overseas education courses provided by universities, contents related to human health were the highest, followed by bio-health big data. Conclusion: Many students wanted to work and go overseas if there is sufficient support from the university. The findings in this study suggest that universities are necessary to play an important role in supporting students' aspirations to work or go overseas by providing language education, education and training programs, information on overseas jobs, and mentoring programs.

The US NRC developed a program called NRCDose3 to evaluates the environmental impact of radiation around nuclear facilities. The NRCDose3 code is a software suite that integrates the functionality of three individual LADTAP II, GASPAR II, and XOQDOQ Fortran codes that were developed by the NRC in the 1980’s and have been in use by the nuclear industry and the NRC staff for assessments of liquid effluent and gaseous effluent, and meteorological transport and dispersion, respectively. Through the integrated program, it is possible to conduct safety assessment and environmental impact assessment from liquid and gaseous effluent when operating permits are granted. In addition to a more user-friendly graphic user interface (GUI) for inputting data, significant changes have been made to the data management and operation to support expanded capabilities. The basic calculation methods of the LADTAP II, GASPAR II, and XOQDOQ have not been changed with this update to the NRCDose3 code. Several features have been added. The previous program used only ICRP-2 dose conversion factor, but the new program can additionally use dose conversion factor of ICRP-30 and ICRP-72. In the previous program, 4 age groups (infant, child, teen, and adult) were evaluated during dose evaluation, but when ICRP-72 was selected, 6 age groups (infant, 1-year, 5-year, 10-year, 15-year, and adult) could be evaluated. In addition, when selecting ICRP-72, many user-modifiable parameters such as food intake and exposure time were added. It will be referred to E-DOSE60, a program currently under development.

Around the world, Nuclear Power Plants (NPPs) have been operated since the 1950s and are used as a major power source. In Korea, Kori unit 1 stared commercial operation for the first time in 1978, and as of 2023, 25 units of NPPs are in operation. NPPs produce electricity for about 40 to 60 years after receiving an operating license, and after securing safety through a safety evaluation, the operating period is extended. NPPs that operate for a long time are systematically evaluated for safety at regular intervals through Periodic Safety Review (PSR) recommended by the IAEA. In Korea, PSR has been introduced and performed since 2000. This study reviewed the process of the PSR by comparing with the international PSR procedure. The PSR process is established through the IAEA SSG-25 document and proceeds in the order of establishment of basis document - individual factor evaluation - global assessment - integrated improvement plan. In Korea, PSR is carried out in a similar process, but there are some differences from the IAEA’s procedure. The safety factor review is conducted under the agreement of basis document between the licensee and the regulatory body, but the prior agreement procedure with the regulatory body is not reflected in Korea. As a result, if the licensee and the regulatory body have different opinions on the current licensing basis and the modern safety standards after the evaluation is performed, a difference may occur in the review results and safety enhancement items, which may lead to inefficient PSR progress. PSR is conducted for the continuous safe operation and management of NPPs, and it is important to refer to overseas standards and cases. Although procedures, guidelines, and regulatory requirements are in place in Korea, continuous review and improvement are required. It is necessary to improve procedures such as basis document and global assessment in order to more efficiently carry out PSR evaluation by regulatory agency and licensee’s safety enhancement actions of domestic NPPs

Among domestic Nuclear Power Plants (NPPs), there are a total of 10 nuclear power plants whose operating license expires by 2030, excluding Kori unit 1 and Wolsong unit 1, which are permanently shut downed. Continued operation of these nuclear power plants is being reviewed as a government task. For continued operation, nuclear power plant owners must prepare periodic safety review and other evaluation reports to receive reviews to maintain safety even during continued operation. In the safety evaluation of NPP, it is important to refer to overseas cases and operation experiences. In this study, the matters of radioactive waste management for continued operation of NPP was considered by analyzing the safety evaluation reports and safety enhancements of license renewal of NPP in USA, Radioactive waste generated from NPPs can be classified into solid, liquid, and gaseous states. Radioactive waste generated during the operation and maintenance of power plants is classified, stored and treated in the radioactive waste management system according to the source. Equipment and monitors related to radioactive waste management are continuously operated, managed, inspected according to standards and maintain their original functions. Various activities to reduce the generation and emission of radioactive waste from NPPs are performed. After reviewing the NRC’s safety evaluation report on the application documents for license renewal of US NPPs (Sequoyah, Byron and braidwood) the evaluation details and matters requiring enhancement for the radioactive waste management system were confirmed. As a major check, selective leaching occurred in the body of the gray cast iron valve and the heat exchanger shell containing the copper alloy exposed to the radioactive waste liquid. Selective leaching causes loss of material and may interfere with the original function of the facility, so management is required. For the safe operation and management of NPPs, it is important to refer to overseas cases and experiences. Among the safety evaluations for the continued operation of domestic NPPs, in the field of the radioactive waste management system, if the case of the US NPP is referred to, the review by the regulatory body and the action taken by the licensee will be more efficient.

KHNP’s vitrification technology introduced a commercialized vitrification facility to the Hanul nuclear power site after a commercialization test through a lab test and a pilot plant at KHNP-CRI. France’s ANADEC (consortium with CEA, Orano, ECM Technologies and Andra) conducted a feasibility evaluation from FY2018 to FY2021 to apply In-Can vitrification, which was developed to treat Fukushima Effluent Treatment Waste (FETW) such as carbonate slurry and ferric slurry generated from ALPS (Advanced Liquid Processing System-Multi Radionuclides Removal) facilities for waste treatment in Fukushima, Japan. For commercialization, the following method was used. First, through the Laboratory scale studies, the possibility of high waste loading (60wt% in dry mass) of slurry on borosilicate matrix was tested. In addition, the volatility of radionuclide was evaluated through radionuclides surrogates with a Bench-scale mockup and glass discharge (100 kg) was evaluated through In-Can vitrification process verification. The feeding system was improved through a pilot scale test, and finally, glass discharge (300 kg) was evaluated after large amount of waste was treated through an industrial prototype (Fullscale) at the CEA Marcoule site (France).

A disposal system for spent nuclear fuel divides into two parts; (1) engineered barriers including spent nuclear fuel, canister, buffer and backfill, (2) natural barriers surrounding engineered barriers. Sorption and diffusion are main retardation mechanisms for the migration of released radionuclides. We analyzed the sorption properties of radionuclides for bentonite as a buffer material and collected/ evaluated the distribution coefficients for the purpose of safety assessment for the deep geological disposal of a spent nuclear fuel. Through this, we presented recommended distribution coefficients for radionuclides required for the safety assessment. This work included the radionuclides as follows; alkali and alkaline earth metals (Cs, Sr, Ba), lanthanides (Sm), actinides (Ac, Am, Cm, Np, Pa, Pu, Th U), transition elements (Nb, Ni, Pd, Tc, Zr), and others (C, Cl, I, Rn, Se, Sn). The sorption of radionuclides affected various geochemical conditions such as pH/carbonates, redox potential, ionic strength, radionuclide concentration, kinds and amounts of minerals, and microbes. Among the evaluated radionuclides, Cs, Ni, Pd, and Ra is sensitive to the ionic strength, while Np, Pu, U, Se, and, Tc is sensitive to the redox condition. For the evaluation of distribution coefficients, the data from Sweden (SKB), Finland (Posiva), Switzerland (Nagra), and Japan (JAEA) were collected, analyzed, and the recommended distribution coefficients were suggested.