Natural radionuclides-containing substances (NORM) contain natural radionuclides and cause radiation exposure. In Korea, safety management measures were needed to deal with and dispose of radon mattresses containing monazite in relation to such NORM. However, there is no clear safety management system related to NORM waste in Korea. In order to manage this reasonably and systematically, it is necessary to investigate and analyze standards and management measures related to the treatment and disposal of NORM waste. Therefore, this study investigated and analyzed the exemption and clearance level of NORM waste regulations in international organizations and foreign countries. IAEA GSR Part 3, 2013/59/Euratom, ANSI/HPS N13.53, CRCPD SSRCR Part N, and ARPANSA Publications 15 safety management regulations were analyzed to investigate safety management standards for NORM waste. The exemption and clearance level in international organizations and foreign countries were compared and analyzed based on radioactive concentration and dose. In addition, the management measures proposed for each literature were also investigated. As a result of the analysis, IAEA GSR Part 3 applied 1 mSv as a regulatory exemption level, 1 Bq/g for uranium and thorium series as a clearance level, and 10 Bq/g for K-40 nuclides. The IAEA recommends a differential approach to the potential and scale of exposure. The EU applied 1 Bq/g to uranium and thorium families and 10 Bq/g to K-40 nuclides for both regulatory exemption and clearance levels. The EU recommended that it be managed in proportion to the scale and likelihood of exposure as a result of the action. It is analyzed that this is similar to the IAEA’s management plan. In the United States, there was no single federal government radioactive concentration and dose for NORM management. The management plan differed in management status and level from state to state, and K-40 was excluded from regulation unless it was intentionally enriched. In the case of Australia, the radioactive concentration of uranium and thorium was 1 Bq/g as a standard for regulatory exemption and 1 mSv as a dose. As a management plan, it was suggested to dispose of waste by means of accumulation, dilution/dispersion, and reclamation. It was also suggested that the scale of exposure, like international organizations, take into account the possibility. The results of this study are believed to be used as basic data for presenting domestic NORM waste treatment and disposal methods in the future.

Dry active waste (DAW) contains substantial amount of cellulose related materials. The DAW are usually classified as low and/or very low-level waste. In Korea, three types of disposal facilities have been considered: silo, engineering barrier, and land-fill. Currently, only the silo type disposal facility is in operation. Around 27 thousand drums were disposed in silo. Massive amount of cement concrete is used in construction of silo. The ground waste, which flow through the concrete structure, shows higher pH than as it is. It is generally known that the pH of silo is ~12.47 in Korea, when considering construction material, filling material, and property of ground water. It is expected that the cellulose in DAW will be partially transformed to isosaccharinic acid (ISA). It is generally accepted that the ISA plays a negative role in safety analysis of disposal facility by stimulation of specific nuclides. Various factors affect the degradation of cellulose containing radioactive waste, such as degree of polymerization, pH of disposal condition, interaction between concrete structure and ground water, etc. In this paper, the disposal safety analysis of cellulose containing radioactive, usually paper, cotton, wood, etc., are studied. The degradation of cellulose with respect to degree of polymerization, pH of neighboring water, filling material of silo, etc. are reviewed. Based on the review results, it is reasonable to conclude that the substantial amount of DAW could be disposed in silo.

Concerns with colloids, dispersed 1~1,000 nm particles, in the LILW repository are being raised due to their potential to enhance radionuclide release. Due to their large surface areas, radionuclides may sorb onto mobile colloids, and drift along with the colloidal transport, instead of being sorbed onto immobile surfaces. To prevent adverse implications on the safety of the repository, the colloidal impact must be evaluated. In this paper, colloid analysis done by SKB is studied, and factors to be considered for the safety assessment of colloids are analyzed. First, the colloid generation mechanism should be analyzed. In a cementitious repository, due to a highly alkaline environment, colloid formation from wastes may be promoted by the decomposition of organic materials, dissolution of inorganic materials, and corrosion of metals. Radiolysis is excluded when radionuclide inventory is moderate, as in the case of SKB. Second, colloid stability should be evaluated to determine whether colloids remain in dispersion. Stable colloids acquire electric charges, allowing particles to continuously repel one another to prevent coagulation. Thus, stability depends on the pH and ionic condition of the surroundings, and colloid composition. For instance, under a highly alkaline cementitious environment, colloids tend to be negatively charged, repelling each other, but Ca2+ ion from cement, acting as a coagulant, makes colloid unstable, promoting sedimentation. As in the case of SKB, the colloidal impact is assumed negligible in the silo, BMA, and BTF due to their extensive cement contents, but for BLA, with relatively less cement source, the colloidal impact is a potential concern. Third, colloid mobility should be assessed to appraise radionuclide release via colloid transport. The mobility depends on the density and size of colloids, and flow velocity to commence motion. As a part of the assessment, the filtration effect should also be included, which depends on pore size and structure. As in the case of SKB, due to static hydraulic conditions and engineering barriers, acting as efficient filters, colloidal transport is expected to be unlikely. In the domestic underground repository, the highly alkaline environment would lead to colloid formation, but due to high Ca2+ concentration and low flow velocity, colloids would achieve low stability and mobility, thus colloidal impact would be a minor concern. In the future, with further detailed analysis of each factor, waste composition, and disposal condition, reliable data for safety evaluation could be generated to be used as fundamental data for planning waste acceptance criteria.

Since high-level radioactive wastes contain long-lived nuclides and emit high energy, they should be disposed of permanently through a deep geological disposal system. In Korea, the first (2016.07) and the second (2021.12) basic plans for the management of high-level disposal systems were proposed to select sites for deep geological disposal facilities and to implement business strategies. Leading countries such as Finland, Sweden and France have developed and applied safety cases to verify the safety of deep geological disposal systems. By examining the regulatory status of foreign leading countries, we analyze the safety cases ranging from the site selection stage of the deep geological disposal system to the securing of the permanent disposal system to the investigation, analysis, evaluation, design, construction, operation, and closure. Based on this analysis, we will develop safety case elements for long-term safety of deep geological disposal systems suitable for domestic situation. To systemically analyze data based on safety cases, we have established a database of deep geological disposal system regulations in leading foreign countries. Artificial intelligence text mining and data visualization techniques are used to provide database in dashboard form rather than simple lists of data items, which is a limitation of existing methods. This allows regulatory developers to understand information more quickly and intuitively and provide a convenient interface so that anyone can easily access the analyzed data and create meaningful information. Furthermore, based on the accumulated bigdata, the artificial intelligence learns and analyzes the information in the database through deep learning, and aims to derive a more accurate safety case. Based on these technologies, this study analyzed the legal systems, regulatory standards, and cases of major international leading countries and international organizations such as the United States, Sweden, Finland, Canada, Switzerland, and the IAEA to establish a database management system. To establish a safety regulation base suitable for the domestic deep geological disposal environment, the database is provided as data to refer to and apply systematic information management on regulatory standards and regulatory cases of overseas leading countries, and it is expected that it will play a key role as a forum for understanding and discussing the level of safety of deep geological disposal system among stakeholders.

Domestic nuclear power plants have developed radiological emergency plans based on the USNRC’s NUREG-0654/FEMA-REP-Rev.1 report and the Korea Institute of Nuclear Safety’s (KINS) research report on radiation emergency criteria for power reactors (KINS/RR-12). NUREG-0654 is a US emergency planning guide for nuclear power plants and provides detailed technical requirements for the content of radiological emergency plans. The document classifies radiological emergencies into three levels: Alert, Site Area Emergency, and General Emergency, which correspond to the white, blue, and red emergency levels used in domestic nuclear power plants. KINS/RR-12 is a technical guidance document published by the Korea Institute of Nuclear Safety in 2012, which divides radiological emergency criteria into criteria for pressurized water reactors (PWRs) and criteria for boiling water reactors (BWRs), and describes in detail the regulatory position and implementation of radiological emergency criteria for domestic PWRs and BWRs. The physical protection-related radiation emergency criteria included in the radiological emergency plan are specified in the radiological emergency criteria guidelines. There are two items each related to white and blue emergencies and one item related to red emergencies. Standard order of emergency plan lists the physical protection-related radiological emergency criteria for domestic PWRs and BWRs, which are identical according to the radiological emergency criteria guidelines. To enhance the physical protection regulation, the legal and regulatory basis for target set identification and vital area identification need to be established by considering radiological and physical protection emergency plan.

In this study, computer simulation of the drawbridge structure was performed to verify the validity of the design and to evaluate its safety. For this, the follower bracket was modeled, and the parts of the follower bracket were connected using 1D elements. The boundary condition applied moments to the rotation shaft of the girder gear in the clockwise and counterclockwise directions, and the connection between the upper parts was modeled using 1D elements to model the bolted connection. In case of rotational shaft deformation, an analysis was performed on the displacement occurring in the structure during the opening/closing operation. As a result of structural analysis of the follower bracket for various cases, the stress at the connection was lower than the tensile strength and yield strength, so it was evaluated as safe. Through this, we intend to use it as a data that can identify anomalies.

국제사회는 글로벌 기후위기 극복을 위해 2050년까지 탄소중립(Net Zero)을 목표로 다양한 탈탄소 에너지원 개발을 지속하고 있다. 우리 정부에서도 ‘재생에너지 3020’ 정책을 수립하고 태양광이나 풍력을 이용한 에너지 개발계획을 추진함에 따라 해상 풍력발전단 지와 같이 연안해역에서 기존에는 볼 수 없었던 대규모 해양개발사업이 추진되고 있다. 해양시설물은 선박의 입장에서 볼 때는 항행 장 애물의 일종이며, 해양시설물 설치에 따라 좁아진 수역에서 선박 간 충돌사고 발생 또는 선박과 해양시설물의 접촉사고 발생시 환경오염 및 인명피해 등의 발생이 우려된다. 이에 국내외의 해상풍력발전단지 개발계획을 살펴보고 풍력단지에서 선박의 안전한 통항을 보장하기 위한 제도적 장치가 완비되어 있는지 분석하였으며, 해외의 입법 사례와 국내 법규를 비교하여 법적 사각지대를 해소하기 위한 새로운 법령안을 제안함으로써 대한민국의 관할해역에서 해양시설물의 안전한 운영과 선박의 안전한 통항을 기대하였다.

This study tried to analyze the keywords of the papers published in the Korea Safety Management Science by using the social network analysis. In order to extract the keywords, information on journal articles published from 2018 to 2021 was extracted from the SCIENCE ON. Among the keywords extracted from a total of 129 papers, the keywords with similar meanings were standardized. The keywords used in the same paper were visualized by connecting them through a network. Four centrality indicators of the social network analysis were used to analyze the effect of the keyword. Safety, Safety management, Apartment, Fire hose, SMEs, Virtual reality, Machine learning, Waterproof time, R&D capability, and Job crafting were selected as the keywords analyzed with high influence in the four centrality indicators.

국제해상충돌예방규칙은 선박이 다른 선박이나 해저 등 어떠한 물체에도 충돌하지 아니하도록 제정된 국제협약이다. 선박의 충돌예방을 위한 규칙은 19세기 중반부터 성문화되고 다듬어져 현재에 이르고 있다. 따라서 COLREGs에서 사용된 용어와 문장 또한 뚜렷 한 학문적, 법률적 의미를 갖고 있다. 그러나 COLREGs를 국내법으로 반영한 해사안전법에서는 ‘충돌의 위험성’과 ‘충돌의 위험’을 구분하 지 않은 채 혼용하고 있다. 이에 ‘위험성’의 정의에 대하여 국제연합 산하의 권위 있는 국제기구인 국제해사기구 및 널리 알려진 비정부 간 기구인 국제표준화기구에서 정의한 내용을 살펴봄으로써 ‘위험’과 ‘위험성’의 차이를 분석하였으며, COLREGs에서 관련 문장을 살펴봄 으로써 이를 구분해야할 근거를 제시하였다. 안전한 항해라는 측면에서 볼 때 향후 해사안전법에 ‘위험’과 ‘위험성’의 구분이 명확해 짐으 로써 이를 준수해야 하는 해기사들의 해상충돌예방을 위한 노력이 한층 체계화되기를 기대하였다.

This paper proposes a method to evaluate the structural safety of a large wide-width greenhouse structure against wind load caused by a typhoon through a fluid structure interaction analysis technique. The conventional method consisted of roughly estimating the wind load based on the relevant laws and regulations, and determining safety through structural analysis. However, since the wind load changes nonlinearly according to the wind speed distribution and wind direction around the greenhouse and the external shape of the structure, there are many uncertainties in the existing structural safety evaluation method, and it is difficult to accurately determine the design margin. In this study, a systematic method was developed to accurately calculate the wind load acting on a greenhouse structure and evaluate structural safety by considering the characteristics of wind through a fluid structure interaction analysis using coupled computational fluid dynamics and computational structural mechanics. Using the proposed method, it is possible to significantly reduce the manufacturing cost because it is possible to obtain an optimal design that reduces the over-conservative design margin while securing the structural strength of the greenhouse.

In this paper, we propose a analysis of domestic and foreign standards on protecting human body from EMF(Electromagnetic filed) and effect of the human body through EMF analysis of military electronic equipment in operation. We measured the EMF intensity of the side lobe and back lobe main beam on Radar Equipment at an accessible position. As a result, it was confirmed that the measured EMF intensity of three types of radar equipment did not exceed the standard on domestic protecting human body from EMF.

With the implementation of the “Critical Disaster Punishment Act” in 2022, the safety and health management system within the organization is being established and awareness of the importance of safety culture is spreading. Measuring the level of safety culture in an organization can grasp the perception and attitude of members about safety. You can also identify the safety-related problems and improvements of the organization. In this study, prior studies on the safety culture level scale were considered, focusing on domestic literature studied from 2001 to 2021. Domestic literature was analyzed by research period, research field, author, core terms, and constituent factors of scale. The implications of the research trend analysis results of the safety culture level scale were derived.