In recent years, there has been a growing trend of occupational accidents involving foreign workers. As the number of foreign workers continues to increase, the risk of occupational accidents is also on the rise. Therefore, it is crucial to take proactive measures to prevent occupational accidents among foreign workers. To establish a common safety culture among foreign workers with varied backgrounds and educational experiences, and which is harmonized with Korean workplace. Safety communication, which includes culture respect and participation in the workplace, plays a significant role in shaping and developing the safety culture of foreign workers. Therefore, this study aims to assess the level of safety culture in workplace employing foreign workers by analyzing the reliability and validity of factors such as 'occupational accident awareness' and 'safety communication,' which constitute the safety culture at these workplace. Additionally, the mediating effect of 'work proficiency' on the relationship between 'safety communication' and the level of improvement in 'occupational accident awareness' using the validation method proposed by Baron & Kenny(1986). As a result of statistical analysis, The influence of‘safety communication’on‘occupational accident awareness’is β=0.339, and it has been found that this influence decreases to β=0.113 when‘work proficiency’is introduced, indicating partial mediation.

Over the years, in the field of safety assessment of geological disposal system, system-level models have been widely employed, primarily due to considerations of computational efficiency and convenience. However, system-level models have their limitations when it comes to phenomenologically simulating the complex processes occurring within disposal systems, particularly when attempting to account for the coupled processes in the near-field. Therefore, this study investigates a machine learning-based methodology for incorporating phenomenological insights into system-level safety assessment models without compromising computational efficiency. The machine learning application targeted the calculation of waste degradation rates and the estimation of radionuclide flux around the deposition holes. To develop machine learning models for both degradation rates and radionuclide flux, key influencing factors or input parameters need to be identified. Subsequently, process models capable of computing degradation rates and radionuclide flux will be established. To facilitate the generation of machine learning data encompassing a wide range of input parameter combinations, Latin-hypercube sampling will be applied. Based on the predefined scenarios and input parameters, the machine learning models will generate time-series data for the degradation rates and radionuclide flux. The time-series data can subsequently be applied to the system-level safety assessment model as a time table format. The methodology presented in this study is expected to contribute to the enhancement of system-level safety assessment models when applied.

The effect of various physicochemical processes, such as seawater intrusion, on the performance of the engineered barrier should be closely analyzed to precisely assess the safety of high-level radioactive waste repository. In order to evaluate the impact of such processes on the performance of the engineered barrier, a thermal-hydrological-chemical model was developed by using COMSOL Multiphysics and PHREEQC. The coupling of two software was achieved through the application of a sequential non-iterative approach. Model verification was executed through a comparative analysis between the outcomes derived from the developed model and those obtained in prior investigations. Two data were in a good agreement, demonstrating the model is capable of simulating aqueous speciation, adsorption, precipitation, and dissolution. Using the developed model, the geochemical evolution of bentonite buffer under a general condition was simulated as a base case. The model domain consists of 0.5 m of bentonite and 49.5 m of granite. The uraninite (UO2) was assigned at the canister-bentonite interface as the potential source of uranium. Assuming the lifetime of canister as 1,000 years, the porewater mixing without uranium leakage was simulated for 1,000 years. After then, the uranium leakage through the dissolution of uraninite was initiated and simulated for additional 1,000 years. In the base case model, where the porewater mixing between the bentonite and granite was the only considered process, the gypsum tended to dissolve throughout the bentonite, while it precipitated in the vicinity of bentonite-granite boundary. However, the precipitation and dissolution of gypsum only showed a limited effect on the performance of the bentonite. Due to the low solubility of uraninite in the reduced environment, only infinitesimal amounts of uranium dissolved and transported through the bentonite. Additional cases considering various environmental processes, such as seawater or cement porewater intrusion, will be further investigated.

This study aimed to verify the validity of the evaluation items and weight determination of the indoor environmental safety area, which has the most frequent accidents, among the safety certification evaluations of educational facilities by the Ministry of Education of the Republic of Korea, which has been conducted since May 2021. As a preceding study, the evaluation items of the school safety evaluation checklist being implemented in the US state of Vermont were compared, and the causes of accidents judged by teachers in the accident experiences written by 200 Korean teachers were compared with the safety certification evaluation items belonged to the Ministry of Education. In addition, research literature using the AHP analysis technique on safety risks of elementary and secondary schools in China and safety evaluation index study cases of 539 elementary school children in Indonesia were analyzed. Through these preceding studies, measures to add and adjust evaluation items were derived and the validity and importance rankings of evaluation items were calculated through AHP questionnaires to teachers and safety experts. In addition, a survey was conducted on 104 ordinary people to verify the results of expert analysis. As a result of expert AHP analysis, 'safety education and disaster response training (.396)' was the highest priority for the relative importance of the first layer, followed by 'safety measures (.387)' and 'building materials'. Safety (.216)' was found to be the highest priority. In the overall importance ranking of the 13 second-tier screening items, safety accident prevention education had the highest priority and disaster preparedness training ranked second, proving that the Ministry of Education's review weight was underestimated. In addition, slip and collision accident countermeasures, which were not in the existing Ministry of Education review items, ranked 4th, laboratory practice room safety measures ranked 6th, and sanitation, cleanliness, hazardous substance management, and cafeteria/cooking room safety measures ranked 9th, indicating a significant level of importance. Referring to the importance ranking, which is the result of this study, it is suggested that it is necessary to review the weight of each review item again.

Safety has once again emerged as a social issue due to the enforcement of the Serious Disasters Punishment Act and the occurrence of major disasters recently. As such, the safety culture related to unsafe human behavior is drawing attention as various discussions about the importance of safety and accident prevention are currently being undertaken. This study aims to determine whether changes in the level of safety culture in companies affect the accident rate. To this end, we targeted three workplaces in the same company in the domestic manufacturing industry, and 2,790 people were surveyed using DNV's Safety Will(ISRS-C version 4.0) for safety culture level diagnosis. The change in safety culture level and accident rate were compared and analyzed after carrying out safety culture level improvement activities for 5 years. As a result, the level of safety culture increased by 5.8 points, an overall improvement of 9.5%, while the total number of accidents decreased by 20%, from 5 to 4, indicating a general decreasing trend in accident occurrence. Results confirmed that the change in the level of safety culture affects the accident rate, and the improvement in the level of safety culture affects a reduction in accidents. Therefore, this study suggests that efforts to improve the level of safety culture within a company can be associated with accident reduction and accident prevention outcomes.

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.

In Korea, 483,102 assemblies of spent fuel have been discharged and stored in sites, as of 2019. However, total capacity for site storage is 529,748 assemblies, and more than 90% is already saturated. Wolsong site, the most saturated site, started to construct more dry storage to extend the capacity in 2020. Spent fuel and high-level waste (HLW) is a big concern in Korean nuclear industry. Then, master plan for management of spent fuel is once announced by Ministry of Trade, Industry and Energy (MOTIE) in 2016 and reviewed by civil committee in 2019. The core contents of the plan are establishing schedule for construction of HLW management facility in one area, and construction of temporary dry storage in each site, if unavoidable. For HLW management facility, there are three following schedules: siting of Underground Research Laboratory (URL) and Interim Storage by 2020, operation of facilities initiated by 2030, and operation of final disposal facility initiated by 2050. Final repository will be designed as deep geological repository. The concept of deep geological disposal is that spent nuclear fuel is placed in disposal containers that can withstand corrosion and pressure in long-term, permanently isolated from the human sphere of life, and dumped in deep geological media, such as crystalline rocks and clay layer, at a depth of 300 to 1,000 meters underground. The safety assessment of waste disposal sites focuses on determining whether the disposal sites meet the safety requirements of national regulatory authority. This safety assessment evaluates the potential radiation dose of radionuclides from the disposal site to humans or the environment. In this case, the calculation is performed assuming that all engineering barriers of the disposal site have collapsed in a long-term period. Then radionuclides are released from the waste, and migrated in groundwater. The dose resulting from the release and migration of radionuclides on the concentration of nuclides in groundwater. In general, metallic nuclides may exist in water in various ionic states, but some form colloids. This colloid allows more nuclides to exist in water than in solubility. Therefore, more doses may occur than we know generally predict. To determine the impact of colloids, we performed the safety assessment of the Yucca Mountain repository as an example.

This study examined the certification effects of safety and health management system (SHMS) on the establishment level of SHMS and accident statistics in construction industry. This study obtained the establishment level of SHMS for 106 construction companies surveyed from our previous study. In addition, three major accident statistics (mortality rate, accidental mortality rate, and injury rate) for the companies were collected from the database in Korean Occupational Safety and Health Agency. The statistical analysis results revealed that the establishment level for SHMS certified companies was significantly higher than those for uncertified or certification preparing companies. Furthermore, SHMS certified companies showed significantly smaller accident statistics compared to uncertified or certification preparing companies. The results of this study support the positive effects of SHMS on reducing major industrial accidents in construction companies.

The mechanical safety of the container designed according to the IP-2 type technology standard was analyzed for the temporary storage and transportation of Very-Low-Level-Waste (VLLW) for liquid occurring at the nuclear facilities decommissioning site. The container was designed and manufactured as a composite shielding container with the effect of storing and shielding liquid radioactive waste using High Density Polyethylene (HDPE) and eco-friendly shielding material (BaSO4) with corrosion and chemical resistance. The main material of the composite shielding container is HDPE and BaSO4, the material of the cover, cage and pallet is SUS304, and the angle guard is elastic rubber. The test and analysis requirements were analyzed for structural analysis of container drop and lamination test. As test requirements for IP-2 type transport containers should be verified by performing drop and lamination tests. There should be no loss or dispersion of contents through the 1.2 m high free-fall drop and lamination test for a load five times the amount of transported material. ABAQUS/Explicit, a commercial finite element analysis program, was used for structural analysis of the drop and lamination test of the transport and storage container. (Drop test) It was confirmed that the container was most affected when it falls from a 45-degree slope. Although plastic deformation was observed at the edge axis of the cover, it was evaluated that the range of plastic deformation was limited to the cover and cage, and stress within the elastic limit occurred in the inner container. In the analysis results for other falling direction conditions, it was evaluated that stress within the elastic limit was generated in the inner container except for minor plastic deformation. In the case of on-site simulation evaluation, deformation of the inner container and frame due to the drop impact occurred, but leakage and loss of contents, which are major evaluation indicators, did not occur. (Lamination test) The maximum stress was calculated to be 19.9 MPa under the lamination condition for a load 5 times the container weight, and the maximum stress point appeared at the corner axis of the pallet. The calculated value for the maximum stress is about 10%, assuming the conservative yield strength of SUS304 is 200 MPa. It was evaluated that stress within the limit occurred. In the case of on-site simulation evaluation, it was confirmed that there was no container deformation or loss of contents due to the load.

The purpose of this study is to investigate the effect of organizational safety and health management activities on safety and health performance by using the results of safety activity level evaluation of public organizations. To this end, a research model was established by using three fields as independent variables among the four areas of the safety activity level evaluation index: safety and health system, safety and health activity plan, and safety and health activity level, and the safety and health activity performance field as a dependent variable. Correlation analysis and regression analysis between major variables were performed. As a result of the correlation analysis, the safety and health activity performance had a significant positive (+) correlation with all of the safety and health system, safety and health activity plan, and safety and health activity level. The safety and health system had a significant positive (+) correlation with the safety and health activity plan and safety and health activity level, and the safety and health activity plan had a significant positive (+) correlation with the safety and health activity level. And as a result of the regression analysis, it was found that the organization’s safety and health system, safety and health activity plan, and safety and health activity level all had a significant positive (+) effect on safety and health activity performance.

본 연구는 반추동물용 섬유질배합사료(TMR) 제조업체 의 사료안전관리 인식 및 사료 중 위해인자 오염도를 조사 하기 위해 138개소 TMR 제조시설을 대상으로 약 10개월 동안 설문조사를 실시하였다. 조사표는 총 17개 문항으로 구성하였으며, 얻어진 자료는 기술통계분석, 교차분석 및 신뢰도 검정을 통해 분석하였다. TMR 제조시설의 평균 일 일 생산능력은 81.38톤 이었다. 평균 개업연도는 2004년 및 종사인원은 13.7명이었고, 유통경로는 직접거래가 80.4%로 가장 많았다. 사료안전관리 시스템 도입은 사료안전관리의 제도적 여건이 조성된 후 도입이 필요하다는 인식이 주를 이루었으며, 사료안전관리 시스템 구축을 위해서는 사료안 전정보 제공 및 공유가 가장 필요한 조건으로 나타났다. 사료안전성 및 위해물질 관리에 가장 취약한 분야는 곰팡 이 독소인 것으로 조사되었으며, 사료 제조과정에서 가장 위험한 위해인자는 쇠, 파편, 흙 등과 같은 이물질로 나타 났다. 사료 중 위험인자 오염도 조사에서 카드뮴, 비소 및 셀레늄은 허용기준치를 초과한 제품이 일부 조사되었고, 오크라톡신류 및 아플라톡신류는 허용범위내로 조사되었 다. 잔류농약, BSE, 푸모니신 및 살모넬라는 검출되지 않았 으며, 멜라민 및 비단백태질소화합물은 각각 11.35ppm 및 5%로 최댓값을 나타냈다. 규모별 TMR 제조시설의 사료 내 위해인자 오염도는 규모별로 차이가 많았으며, 같은 규 모 내에서도 제조시설에 따라 위해인자의 검출량이 다르 게 나타났다. 또한 소규모에 비해 중규모 및 대규모에서 위해인자 검출량이 더 높아지는 경향을 보였다. 따라서 본 조사결과 TMR 제조시설의 사료안전관리 시스템을 구축하 기 위해서는 사료안전에 대한 정보제공 및 공유가 정책적 으로 제도화되어야 하고, 사료 내 발생하는 곰팡이 독소방 지 및 이물질 제거를 위한 사료관리법의 강화와 원료 공급 처에서 이물질을 제거할 수 있는 장치 도입을 의무화할 필 요가 있다고 판단된다.

경주 방사성폐기물 처분시설은 향후 80만 포장물을 처분할 계획이며 다양한 처분방식 및 관리형태를 가진 복합계가 될 것 이다. 본 논문에서는 전체부지 처분용량(80만 포장물) 처분시설의 단계별 개발에 따른 영향을 평가하기 위하여 처분시설 종 합개발계획(안)에 따른 예비안전성평가를 수행하였다. 각 시나리오에 대한 안전성평가결과 처분시설의 성능목표치를 만족 하였다. 다만, 전체처분시설의 안전성 평가결과에 중준위 방사성폐기물로 인하여 1단계 동굴 처분시설이 가장 크게 영향을 미치므로 처분시설의 안전성 향상을 위하여 처분방사능량제한 설정 등 관리방안이 필요하다. Safety Case 단계별 구축을 통 하여 중·저준위 방사성폐기물 처분시설 종합개발 과정에서 인지된 불확실성을 저감하여 안전성을 증진 시킬 수 있을 것으 로 판단된다.

고준위방사성폐기물 심층처분에서 처분안전성의 신뢰도를 향상시킬 수 있는 방안으로 그리고 처분 프로그램 개발 및 인허가를 위해 많은 나라들에서 자국에 적합한 safety case를 개발하고 있다. 본 연구에서는 방사성폐기물 처분을 위한 safety case 의 의의, 필요성, 개발과정들을 정리하고 소개하였다. 그리고 처분안전성을 safety case의 다양한 측면에서 논의하였다. 아울러 스위스, 일본, 미국, 스웨덴, 핀란드 등 해외의 safety case 개발 현황과 현재 KAERI에서 개발 중인 safety case의 개발 전략을 간략히 소개하였다. 고준위방사성폐기물 처분안전성의 신뢰도 향상을 위해 safety case 기반 하에서 어떤 노력들이 필요한지를 분석하였다. 그리고 국내 상황을 반영하여 신뢰할 수 있는 정보자료의 구축, 안전성 관련 과정들의 이해, 안전성 평가의 불확실성 저감, 이해당사자와의 의사소통, 공정성과 투명성 확보 등의 실행 방안을 제안하고 논의하였다. 본 논문에 제시된 내용들은 심층처분 safety case를 이해하고, 국내에서 개발하고 있는 고준위방사성폐기물 처분 safety case 개발을 통한 처분안전성 신뢰도 향상에 기여할 수 있을 것으로 기대한다.

The purpose of this study is to understand how to affect the safety behavior to the organization's trustees to investigate the level of safety awareness, safety awareness via the distribution center workers prepare the logistics industry disaster prevention measures. The survey was analyzed data to target by the clothing distribution center employees of 182 people. Analysis First, the level of safety awareness showed on a positive effect on organization trust. Second, it was found on the safety level of consciousness a positive effect on the safety behavior. Third, the level of safety awareness affect the safety behavior showed that the mediating role of organization trust. That is a higher level of safety awareness, such as the strict practice of business activities, investments, safety rules on safety education and training emphasis on safety increases confidence in the organization. It was confirmed the higher the confidence in the safety organization appears behavior such as actively participating in the work carried out in a safe manner, safety education and training. In addition, the effect was mediated by the organizational impact on confidence in the safety of personnel safety awareness actions. Based on that research results prepared safety awareness was raised through the industrial accident prevention measures